Science.gov

Sample records for nuclear industry support

  1. Supporting Our Nation's Nuclear Industry

    ScienceCinema

    Lyons, Peter

    2016-07-12

    On the 60th anniversary of the world's first nuclear power plant to produce electricity, Assistant Secretary for Nuclear Energy Peter Lyons discusses the Energy Department's and the Administration's commitment to promoting a nuclear renaissance in the United States.

  2. Supporting Our Nation's Nuclear Industry

    SciTech Connect

    Lyons, Peter

    2011-01-01

    On the 60th anniversary of the world's first nuclear power plant to produce electricity, Assistant Secretary for Nuclear Energy Peter Lyons discusses the Energy Department's and the Administration's commitment to promoting a nuclear renaissance in the United States.

  3. DOE/Industrial Matching Grant to Support Nuclear Engineering and Nuclear-Related /Disciplines

    SciTech Connect

    Slaughter, David M.

    2002-08-31

    Final Report - Assurance is given that monies received through the matching grant were, in general, disburse as outlined in the original proposal. Specifically, the grant funded graduate students who participated in the nuclear engineering course opinions. The contract provided for a number of research stipends and student salaries for graduates working with industrial partners affiliated with the CENTER/NEP program (i.e., Envirocare, E-cubed, Aerotest, Little Mountain/Boeing). When necessary, supplies were purchased that supported these student activities. No funds were distributed for faculty or staff salaries.

  4. Nuclear Industry Support Services by the Buffalo Materials Research Center

    SciTech Connect

    Henry, L.G. )

    1993-01-01

    The Buffalo Materials Research Center (BMRC) is located on the campus of the State University of New York at Buffalo, Principal facilities within BMRC include a 2-MW PULSTAR, low-enrichment reactor, an electron accelerator, and irradiated materials remote testing facilities. The reactor and the materials testing facilities have been utilized extensively in support of the power reactor community since 1961. This paper briefly highlights the nature and scope of this service. The BMRC is operated for the university by Buffalo Materials Research, Inc., a private for-profit company, which is a subsidiary of Materials Engineering Associates, Inc. (MEA), a Maryland-based materials testing company. A primary mission of MEA has been research on the effects of neutron irradiation on reactor structural materials, including those used for pressure vessel and piping systems. The combined resources of MEA and BMRC have played a pivotal role in the assessment of reactor pressure vessel safety both in the United States and abroad and in the development of new radiation-resistant steels.

  5. Tenth International RETRAN Conference Overview: RETRAN's Role in Supporting the Nuclear Industry's Vision

    SciTech Connect

    Agee, Lance J

    2003-04-15

    The nuclear industry's current 'vision' for 2020 is for growth in U.S. nuclear to a 23% share of generation in 2020. To support this vision, the Electric Power Research Institute's Nuclear Power Division has developed a strategic bridge plan. The major objectives of the plan are discussed. Of key importance is the U.S. Nuclear Regulatory Commission (NRC) staff's proposed framework for risk-informed regulations. RETRAN-3D will undoubtedly be used by the industry to support Risk-Informed Regulation, specifically option 3.The reason that RETRAN-3D is the most logical tool to support Risk-Informed Regulation is that in January 2001 the NRC issued a safety evaluation report (SER) on RETRAN-3D. The significance of the SER to the RETRAN community is described, and a list of the most important SER conditions provided.Next, the new and unique applications of RETRAN-3D are referenced. Finally, discussion of the future direction of safety software indicates what the author feels is needed to adequately support both existing plant upgrades and future plant designs.

  6. Utilization of the Cornell University research reactors in support of the Nuclear Power Industry

    SciTech Connect

    Aderhold, A.C. )

    1993-01-01

    Cornell University is licensed to operate two research reactor facilities on its main campus in Ithaca, New York: a 500-kW pulsing TRIGA and a 100-W zero-power reactor (ZPR). The initial criticality of both reactors took place in 1962, and the utilization of each has been, and continues to be, dedicated to the teaching and research programs of Cornell's many academic departments. As the nation's nuclear power industry grew, the demand for services at research and test reactors increased. As a result, and in large part because of special design features of the TRIGA, Cornell responded to a few requests for reactor testing services while maintaining the policy that these services would not interfere with teaching and research programs. The frequency of service requests suddenly mushroomed in November of 1989, when the nation's major testing reactor was shut down for repairs. In spite of a small staff of two full-time reactor operators, a decision was made to support the nuclear industry to the fullest extent possible without jeopardizing Cornell's teaching and research programs. This turned into a monumental task of tight scheduling and meeting precise deadlines. It could only be accomplished by working late evenings and weekends and, on a number of occasions, staying at the facility for up to 5 days continuously.

  7. Industry Support

    NASA Technical Reports Server (NTRS)

    2003-01-01

    NASA Glenn Research Center (GRC) is responsible for the Advanced Communications for Air Traffic Management (AC/ATM) Project, a sub-element task of the Advanced Air Transportation Technologies (AATT) Project of the NASA Aviation System Capacity Program (ASC). The AC/ATM Project is developing new communications technologies and tools that will improve throughput in the U.S. Air Traffic Control System. The goal of the AC/ATM Project is to enable a communications infrastructure providing the capacity, efficiency, and flexibility necessary to realize benefits of the future mature Free-Flight environment. The capabilities and scope of communications technologies needed to accomplish this goal depend on characteristics of the future Free-Flight environment. There are many operational concepts being proposed for a future ATM system to enable user flexibility and efficiency. GRC s focus is on developing new technologies and techniques to support the digital communication of information involving airborne and ground-based users. However, the technologies and techniques must be integrated with the systems and services that industry and the Federal Aviation Administration (FAA) are developing. Thus, GRC needs to monitor and provide input to the various industry and FAA organizations and committees that are specifying new systems and services. Adoption of technologies by the FAA is partially dependent on acceptance of the technology by the aviation community. The commercial aviation community in particular would like to adopt technologies that can be used throughout the world. As a result, the adoption of common or at least compatible technologies by European countries is a key factor in getting commitments to those technologies by the US aviation community. GRC desires to keep informed of European activities that relate to aviation communication technologies, particularly those that are being supported by Eurocontrol.

  8. Interdisciplinary studies on the development of nuclear-fueled circulatory support systems: Collaboration of industry and academe

    NASA Technical Reports Server (NTRS)

    Norman, J. C.

    1974-01-01

    The purpose of this report is to acquaint the Houston community with specific areas of available technology, both public and private, to demonstrate to industry how this technology may be acquired and put to use to provide new and useful services for man. Much of the technology utilized in the development of nuclear-fueled circulatory support systems in our laboratories has evolved from industry, NASA, and AEC; our projects involve radiation biology, thermodynamics, energy transfers, hemodynamics, hematology, pathology, and surgery.

  9. Nuclear industry will be short of engineers

    SciTech Connect

    Yates, M.

    1990-09-13

    This article discusses the potential shortage of nuclear engineers due to reduction of educational and training facilities and difficulty in attracting minorities into nuclear engineering. The article reports on recommendations from the National Research Council Nuclear Education Study Committee on attracting minorities to nuclear engineering, increasing DOE fellowships, funding for research and development, involvement of utilities and vendors, and support of the American Nuclear Society's advocacy of nuclear engineering education.

  10. Concrete waterproofing in nuclear industry.

    PubMed

    Scherbyna, Alexander N; Urusov, Sergei V

    2005-01-01

    One of the main points of aggregate safety during the transportation and storage of radioactive materials is to supply waterproofing for all constructions having direct contact with radiating substances and providing strength, seismic shielding etc. This is the problem with all waterside structures in nuclear industry and concrete installations in the treatment and storage of radioactive materials. In this connection, the problem of developing efficient techniques both for the repair of operating constructions and the waterproofing of new objects of the specified assignment is genuine. Various techniques of concrete waterproofing are widely applied in the world today. However, in conditions of radiation many of these techniques can bring not a profit but irreparable damage of durability and reliability of a concrete construction; for instance, when waterproofing materials contain organic constituents, polymers etc. Application of new technology or materials in basic construction elements requires in-depth analysis and thorough testing. The price of an error might be very large. A comparative analysis shows that one of the most promising types of waterproofing materials for radiation loaded concrete constructions is "integral capillary systems" (ICS). The tests on radiation, thermal and strength stability of ICS and ICS-treated concrete samples were initiated and fulfilled in RFNC-VNIITF. The main result is--ICS applying is increasing of waterproofing and strength properties of concrete in conditions of readiation The paper is devoted to describing the research strategy, the tests and their results and also to planning of new tests.

  11. Emergence of the nuclear industry and associated crime. Master's thesis

    SciTech Connect

    Vaught, J.W.

    1991-08-01

    Nuclear energy, in weapons production and electrical power generation, is a technology that has endured public scrutiny since the late 1940s. Societal acceptance of this industry has been affected by controversy in the following areas: health effects of exposure to radiation, possible consequences resulting from accidents, and nuclear nonproliferation. The literature review begins in Chapter 2 by examining the changing public perceptions of nuclear energy over the last forty years. Support for the ideals and practices of the industry has often wavered, due to media representation of incidents, accidents, and potential catastrophic events. The second part of the chapter highlights the crimes associated with nuclear energy in a chronological order of concern by nuclear industry security specialists. Research has found certain types of crime to be more prevalent during particular eras than others. Crimes instigated by spies, peace activists, terrorists, and the insider (employee) are reviewed, with an emphasis on insider crime.

  12. Artificial intelligence applications in the nuclear industry

    SciTech Connect

    Majumdar, D.

    1988-10-01

    This is a state-of-the-art review of artificial intelligence (AI) applications in the nuclear industry. It was initiated as a result of the American Nuclear Society-sponsored conference on ''Artificial Intelligence and Other Innovative Computer Applications in the Nuclear Industry,'' held in Snowbird, Utah, August 1987. This conference brought together a large number of international experts and showed extensive worldwide applications of expert systems in the nuclear industry. This document is a postconference review and a reflection on the current status and the future of AI in the nuclear industry. Because artificial intelligence techniques can analyze large and complex arrays of information, develop smaller sets of higher-level conclusions, incorporate human expertise, and present information suitable for human intelligence, it is very appropriate for applications in complex nuclear power plant operation. Some advances have already been made in several areas. However, among the many applications in the nuclear industry, there does not appear to be any outstanding application to date such as the ones found in the medical or geological fields. What comes out clearly is that the nuclear industry is experimenting in many areas with the expert system technology and determining its usefulness for the industry. On the international scene, the United States is the current leader in knowledge and applications, followed by Japan and France. However, the Japanese appear to have embraced the AI concept more wholeheartedly. This review encompasses a large number of areas including fault diagnosis, reactor control, plant operation, alarm filtering, accident management, robotics, probabilistic risk assessment, and the human element of expert systems. The potential for useful application of AI technology in the nuclear industry is shown to be promising. 383 refs., 13 figs., 11 tabs.

  13. Options contracts in the nuclear fuel industry

    SciTech Connect

    Fuller, D.M.

    1995-04-01

    This article discusses options trading in the nuclear fuels industry. Although there now exists no formal options market in the nuclear industry, flexibilities, or embedded options, are actually quite common in the long-term supply contracts. The value of these flexibilities can be estimated by applying the methods used to evaluate options. The method used is the Black-Scholes Model, and it is applied to a number of examples.

  14. Long-Term Nuclear Industry Outlook - 2004

    SciTech Connect

    Reichmuth, Barbara A.; Wood, Thomas W.; Johnson, Wayne L.

    2004-09-30

    The nuclear industry has become increasingly efficient and global in nature, but may now be poised at a crossroads between graceful decline and profound growth as a viable provider of electrical energy. Predicted population and energy-demand growth, an increased interest in global climate change, the desire to reduce the international dependence on oil as an energy source, the potential for hydrogen co-generation using nuclear power reactors, and the improved performance in the nuclear power industry have raised the prospect of a “nuclear renaissance” in which nuclear power would play an increasingly more important role in both domestic and international energy market. This report provides an assessment of the role nuclear-generated power will plan in the global energy future and explores the impact of that role on export controls.

  15. Human factors aspects of advanced instrumentation in the nuclear industry

    SciTech Connect

    Carter, R.J.

    1989-01-01

    An important consideration in regards to the use of advanced instrumentation in the nuclear industry is the interface between the instrumentation system and the human. A survey, oriented towards identifying the human factors aspects of digital instrumentation, was conducted at a number of United States (US) and Canadian nuclear vendors and utilities. Human factors issues, subsumed under the categories of computer-generated displays, controls, organizational support, training, and related topics were identified. 20 refs., 2 tabs.

  16. Graphite for the nuclear industry

    SciTech Connect

    Burchell, T.D.; Fuller, E.L.; Romanoski, G.R.; Strizak, J.P.

    1991-01-01

    Graphite finds applications in both fission and fusion reactors. Fission reactors harness the energy liberated when heavy elements, such as uranium or plutonium, fragment or fission''. Reactors of this type have existed for nearly 50 years. The first nuclear fission reactor, Chicago Pile No. 1, was constructed of graphite under a football stand at Stagg Field, University of Chicago. Fusion energy devices will produce power by utilizing the energy produced when isotopes of the element hydrogen are fused together to form helium, the same reaction that powers our sun. The role of graphite is very different in these two reactor systems. Here we summarize the function of the graphite in fission and fusion reactors, detailing the reasons for their selection and discussing some of the challenges associated with their application in nuclear fission and fusion reactors. 10 refs., 15 figs., 1 tab.

  17. Industry-Supported Team Students' Projects.

    ERIC Educational Resources Information Center

    Glozman, Vladimir

    The industry-supported team students' project enhances professional, intellectual, and personal development of students while addressing the needs of local industry. In addition to achieving academic excellence, the students are exposed to industry requirements, and excel in effective oral communication and cooperative teamwork. The teamwork…

  18. Supporting industries energy and environmental profile

    SciTech Connect

    None, None

    2005-09-21

    As part of its Industries of the Future strategy, the Industrial Technologies Program within the U.S. Department of Energy’s (DOE) Office of Energy Efficiency and Renewable Energy works with energy-intensive industries to improve efficiency, reduce waste, and increase productivity. These seven Industries of the Future (IOFs) – aluminum, chemicals, forest products, glass, metal casting, mining, and steel – rely on several other so-called “supporting industries” to supply materials and processes necessary to the products that the IOFs create. The supporting industries, in many cases, also provide great opportunities for realizing energy efficiency gains in IOF processes.

  19. Contracting and subcontracting by the French nuclear power industry.

    PubMed

    Thébaud-Mony, A

    1999-01-01

    The French nuclear power industry contracts out 80% of the maintenance work in its plants to independent companies. The workers in these companies are seldom protected by unions or by government regulations. The average dose of radiation received by such a worker is four times that received by a permanent employee of the contracting entity. As the contract worker approaches a specified dose limit, he is laid off, with no support other than welfare and no compensation for medical expenses that may arise as a result of the radiation exposure or occupational stress. There is a danger that this pattern of worker exploitation will spread as nuclear power plants proliferate around the world.

  20. Online Monitoring of Plant Assets in the Nuclear Industry

    SciTech Connect

    Nancy Lybeck; Vivek Agarwal; Binh Pham; Richard Rusaw; Randy Bickford

    2013-10-01

    Today’s online monitoring technologies provide opportunities to perform predictive and proactive health management of assets within many different industries, in particular the defense and aerospace industries. The nuclear industry can leverage these technologies to enhance safety, productivity, and reliability of the aging fleet of existing nuclear power plants. The U.S. Department of Energy’s Light Water Reactor Sustainability Program is collaborating with the Electric Power Research Institute’s (EPRI’s) Long-Term Operations program to implement online monitoring in existing nuclear power plants. Proactive online monitoring in the nuclear industry is being explored using EPRI’s Fleet-Wide Prognostic and Health Management (FW-PHM) Suite software, a set of web-based diagnostic and prognostic tools and databases that serves as an integrated health monitoring architecture. This paper focuses on development of asset fault signatures used to assess the health status of generator step-up transformers and emergency diesel generators in nuclear power plants. Asset fault signatures describe the distinctive features based on technical examinations that can be used to detect a specific fault type. Fault signatures are developed based on the results of detailed technical research and on the knowledge and experience of technical experts. The Diagnostic Advisor of the FW-PHM Suite software matches developed fault signatures with operational data to provide early identification of critical faults and troubleshooting advice that could be used to distinguish between faults with similar symptoms. This research is important as it will support the automation of predictive online monitoring techniques in nuclear power plants to diagnose incipient faults, perform proactive maintenance, and estimate the remaining useful life of assets.

  1. Manpower Requirements in the Nuclear Power Industry, 1982-1991.

    ERIC Educational Resources Information Center

    Johnson, Ruth C.

    A study projected employment needs created by growth and employee turnover for the nuclear power industry over the next decade. Only employment by electric utilities in the commercial generation of nuclear power was investigated. Employment data for 1981 were collected in a survey of 60 member utilities of the Institute of Nuclear Power…

  2. The Role of the Sellafield Ltd Centres of Expertise in Engaging with the Science, Environment and Technology Supply Chain and University Sector to Support Site Operations and Decommissioning in the UK Nuclear Industry - 13018

    SciTech Connect

    Butcher, Ed; Connor, Donna; Keighley, Debbie

    2013-07-01

    The development and maintenance of the broad range of the highly technical skills required for safe and successful management of nuclear sites is of vital importance during routine operations, decommissioning and waste treatment activities.. In order to maintain a core team of technical experts, across all of the disciplines required for these tasks, the approach which has been taken by the Sellafield Ltd has been the formation of twenty five Centres of Expertise (CoE), each covering key aspects of the technical skills required for nuclear site operations. Links with the Specialist University Departments: The CoE leads are also responsible for establishing formal links with university departments with specialist skills and facilities relevant to their CoE areas. The objective of these links is to allow these very specialist capabilities within the university sector to be more effectively utilized by the nuclear industry, which benefits both sectors. In addition to the utilization of specialist skills, the university links are providing an important introduction to the nuclear industry for students and researchers. This is designed to develop the pipeline of potential staff, who will be required in the future by both the academic and industrial sectors. (authors)

  3. Nuclear reactor pressure vessel support system

    DOEpatents

    Sepelak, George R.

    1978-01-01

    A support system for nuclear reactor pressure vessels which can withstand all possible combinations of stresses caused by a postulated core disrupting accident during reactor operation. The nuclear reactor pressure vessel is provided with a flange around the upper periphery thereof, and the flange includes an annular vertical extension formed integral therewith. A support ring is positioned atop of the support ledge and the flange vertical extension, and is bolted to both members. The plug riser is secured to the flange vertical extension and to the top of a radially outwardly extension of the rotatable plug. This system eliminates one joint through which fluids contained in the vessel could escape by making the fluid flow path through the joint between the flange and the support ring follow the same path through which fluid could escape through the plug risers. In this manner, the sealing means to prohibit the escape of contained fluids through the plug risers can also prohibit the escape of contained fluid through the securing joint.

  4. Ion exchange in the nuclear industry

    SciTech Connect

    Bibler, J.P.

    1990-01-01

    Ion exchange is used in nearly every part of the nuclear fuel cycle -- from the purification of uranium from its ore to the final recovery of uranium and transmutation products. Ion exchange also plays a valuable role in the management of nuclear wastes generated in the fuel cycle.

  5. Ion exchange in the nuclear industry

    SciTech Connect

    Bibler, J.P.

    1990-12-31

    Ion exchange is used in nearly every part of the nuclear fuel cycle -- from the purification of uranium from its ore to the final recovery of uranium and transmutation products. Ion exchange also plays a valuable role in the management of nuclear wastes generated in the fuel cycle.

  6. Cyber security best practices for the nuclear industry

    SciTech Connect

    Badr, I.

    2012-07-01

    When deploying software based systems, such as, digital instrumentation and controls for the nuclear industry, it is vital to include cyber security assessment as part of architecture and development process. When integrating and delivering software-intensive systems for the nuclear industry, engineering teams should make use of a secure, requirements driven, software development life cycle, ensuring security compliance and optimum return on investment. Reliability protections, data loss prevention, and privacy enforcement provide a strong case for installing strict cyber security policies. (authors)

  7. Tackling the nuclear manpower shortage: industry, educators must work together

    SciTech Connect

    Witzig, W.

    1981-10-01

    A 50% decline in graduate enrollment and an increase to 50% of foreign nationals among the nuclear engineering students since 1973 at Pennsylvania State University is typical of national trends, which have led to the closing of 13 undergraduate programs across the country. Penn State's proximity to Three Mile Island had less effect than its interactions with high schools and utilities in keeping the nuclear program as strong as it is. Penn State operates three separate career programs to interest high school students in a nuclear career. Institute of Nuclear Power Operations (INPO) educational assistance reflects industry interest, but more scholarships are needed to broaden student awareness. (DCK)

  8. System dynamics: An introduction & applications to the nuclear industry

    SciTech Connect

    Hansen, K.F.; Golay, M.W.

    1997-03-01

    The field of nuclear technology has been developing for over 50 years and has moved from the laboratory into a very large commercial industry. The growth in the underlying science and engineering has been remarkable both in its breadth and depth. The ability to design, analyze, and understand the behavior of nuclear plants is firmly established. There remain many challenging technical problems, but success of the industry is not contingent upon solving those technical problems. Rather, the success of the industry will be determined by a wider array of concerns than pure technology. For instance, nuclear plants in the future will have to compete economically against efficient, versatile, and reliable fossil technologies. In addition, potential users must be assured that the indirect costs, such as those of environmental effects and waste disposal, are acceptable. Finally, public perceptions about risks must somehow be allayed, if not resolved. The objective of this paper is to provide an introduction to a tool that may be useful to the industry in addressing the types of issues suggested above. The tool discussed is system dynamics. It has been used with considerable success in many other fields in ways that are similar to the needs of the nuclear field. In the second section of the paper the authors provide some background on the system dynamics method and illustrate how system dynamics models are constructed. In section 3 they discuss two applications in the nuclear field, the first relating to construction of nuclear plants and the second in the operation of a nuclear utility in the social/political environment of today in the United States. They conclude with some summary comments.

  9. Quantity and quality in nuclear engineering professional skills needed by the nuclear power industry

    SciTech Connect

    Slember, R.J.

    1990-01-01

    This paper examines the challenge of work force requirements in the context of the full range of issues facing the nuclear power industry. The supply of skilled managers and workers may be a more serious problem if nuclear power fades away than if it is reborn in a new generation. An even greater concern, however, is the quality of education that the industry needs in all its future professionals. Both government and industry should be helping universities adapt their curricula to the needs of the future. This means building a closer relationship with schools that educate nuclear professionals, that is, providing adequate scholarships and funding for research and development programs, offering in-kind services, and encouraging internships and other opportunities for hands-on experience. The goal should not be just state-of-the-art engineering practices, but the broad range of knowledge, issues, and skills that will be required of the nuclear leadership of the twenty-first century.

  10. Environmental and health effects of the nuclear industry and nuclear weapons: a current evaluation.

    PubMed

    Johnson, C J

    1982-01-01

    The nuclear weapons industry in the U.S. comprises nine major plants, supported by a network of subcontractors and grantee institutions. Weapons development progresses at the Lawrence Livermore and Los Alamos Laboratories under the auspices of the University of California. Fissionable materials and tritium are produced at the Savannah River Plant (du Pont) or at Hanford. Reprocessing of plutonium and weapons grade uranium and manufacture of components are carried out at Rocky Flats (formerly Dow, now Rockwell Int.). Large amounts of radionuclides are generated or involved in operations at most of the nine plants. Internal reports of surveillance efforts by weapons plant personnel to monitor emissions of radioactive gases and particulates have now been released by several of the plants (in one case through litigation). Those reports document major releases of radioactive gases and particulates to the environment in the past, and continuing routine releases of some importance. Few investigations have been made of effects from these potent carcinogens in local populations. There have been several preliminary reports (Rocky Flats, Los Alamos and Savannah River) and one comprehensive report [Ambio 10: 176 (1981)]. Evidence of significantly increased rates of cancer of the more radiosensitive organs has been demonstrated. Adequate cancer registry and vital statistics data are essential for the comprehensive investigations of somatic and genetic effects which should be carried out around all nuclear installations near population centres.

  11. Nuclear energy position in industrial and economics global

    NASA Astrophysics Data System (ADS)

    Aji, Indarta Kuncoro; Permana, Sidik

    2012-06-01

    3E (Energy, Economics and Education) are three concepts of community development, and 3E concepts are interlinked between each other. 3E concept is divided into three levels of regions, remote area or villages, small towns and metropolitan cities, and there are different problems of each region. This paper analyzes the relations between energy, economics and education in the metropolitan and industrial city. Especially the influence of nuclear energy concerning at cost production of the industrial and the contribution of education and research for nuclear energy innovation. This relation can be explained using "S-curve". The results of this study is the comparison between the product involves the use of nuclear energy or not in the production process are explained using "S-curve" and its effect on the global economics.

  12. Fitness for duty in the nuclear power industry: A review of technical issues

    SciTech Connect

    Barnes, V.; Fleming, I.; Grant, T.; Hauth, J.; Hendrickson, J.; Kono, B.; Moore, C.; Olson, J.; Saari, L.; Toquam, J.; Wieringa, D.; Yost, P.; Hendrickson, P.; Moon, D.; Scott, W.

    1988-09-01

    This report presents information gathered and analyzed in support of the United States Nuclear Regulatory Commission's (NRC's) efforts to develop a rule that will ensure that workers with unescorted access to protected areas in nuclear power plants are fit for duty. The primary potential fitness-for-duty concern addressed in the report is impairment caused by substance abuse, although other sources of impairment on the job are discussed. The report examines the prevalence of fitness-for-duty problems and discusses the use and effects of illicit drugs, prescription drugs, over-the-counter preparations and alcohol. The ways in which fitness-for-duty concerns are being addressed in both public- and private-sector industries are reviewed, and a description is provided of fitness-for-duty practices in six organizations that, like the nuclear industry, are regulated and whose operations can affect public health and safety. Methods of ensuring fitness for duty in the nuclear industry are examined in detail. The report also addresses methods of evaluating the effectiveness of fitness-for-duty programs in the nuclear power industry.

  13. Applied nuclear physics in support of SBSS

    SciTech Connect

    Strottman, D.

    1995-10-01

    Since the advent of the 800-MeV proton linear accelerator over 3 decades ago, the facilities on the Clinton P. Anderson Meson Physics Facility (LAMPF) mesa have pioneered many developments that provide unique capabilities within the Department of Energy (DOE) complex and in the world. New technologies based on the use of the world`s most intense, medium-energy linac, LAMPF, are being developed. They include destruction of long-lived components of nuclear waste, plutonium burning, energy production, production of tritium, and experiments for the science-based stockpile stewardship (SBSS) program. The design, assessment, and safety analysis of potential facilities involve the understanding of complex combinations of nuclear processes, which in turn establish new requirements on nuclear data that transcend the traditional needs of the fission and fusion reactor communities. Other areas of technology such as neutron and proton therapy applications are also placing new requirements on nuclear data. The proposed Los Alamos Neutron Science Center (LANSCE) now under discussion combined with the appropriate instrumentation will have unique features and capabilities of which there were previously only aspirations.

  14. Industry supports establishing consortia on superconductivity

    SciTech Connect

    Not Available

    1989-08-01

    This article presents a summary of a survey conducted to determine if an initiative on the manufacture of high-temperature superconductor products holds any promise. The survey included questions on the planning of and participation in industrial consortia, government sponsorship of R and D directions for R and D manufacturing, and a plan for U.S. Department of Defense involvement in high-temperature superconductor consortia. The results of the survey, as well as the conclusions are discussed.

  15. Industry support of graduate medical education in surgery.

    PubMed

    Nakayama, Don K; Bozeman, Andrew P

    2009-05-01

    The role of pharmaceutical and medical device companies ("industry") in graduate medical education (GME) is under debate. We surveyed program directors in general surgery and surgical specialties to determine industry activities in surgical GME. We used an internet-based questionnaire regarding industry marketing and educational activities in surgical programs, and their effects on surgical education. We received 65 responses to 377 requests (17%). Nearly two-thirds reported industry-sponsored meals. Industry-supported travel was infrequent ("never" and "seldom" in 56% of device workshops, 69% of lectures, and 74% of conferences). More than one-half reported support for academic events: paid lecturers and exhibition fees (both 58%), and unrestricted grants (62%). More than one-half (54%) reported industry-sponsored research. One-fourth believed their programs to be dependent on industry for their educational missions. Most disagreed that industry support posed a problem, either in general (55%) or for their program (71%). One-fourth of respondents (25%) advocated profession-wide restrictions of industry involvement with GME. Equal numbers agreed (39%) and disagreed (35%) with the view that pharmaceutical and medical device industries have motivations that are in conflict with those of doctors and their patients. Industry activities are widespread in surgical residencies, with approval of many program directors.

  16. Towards A Unified HFE Process For The Nuclear Industry

    SciTech Connect

    Jacques Hugo

    2012-07-01

    As nuclear power utilities embark on projects to upgrade and modernize power plants, they are likely to discover that traditional engineering methods do not typically make provision for the integration of human considerations. In addition, human factors professionals will find that traditional human performance methods such as function allocation, task analysis, human reliability analysis and human-machine interface design do not scale well to the complexity of a large-scale nuclear power upgrade project. Up-to-date human factors engineering processes, methods, techniques and tools are required to perform these kinds of analyses. This need is recognized widely in industry and an important part of the Department of Energy’s Light Water Reactor Sustainability Program deals with identifying potential impacts of emerging technologies on human performance and the technical bases needed to address them. However, so far no formal initiative has been launched to deal with the lack of integrated processes. Although human factors integration frameworks do exist in industries such as aviation or defense, no formal integrated human factors process exists in the nuclear industry. As a first step towards creating such a process, a “unified human factors engineering process” is proposed as a framework within which engineering organizations, human factors practitioners and regulatory bodies can ensure that human factors requirements are embedded in engineering activities throughout the upgrade project life cycle.

  17. NGNP Nuclear-Industrial Facility and Design Certification Boundaries White Paper

    SciTech Connect

    Thomas E. Hicks

    2011-07-01

    The Next Generation Nuclear Plant (NGNP) Project was initiated at Idaho National Laboratory by the U.S. Department of Energy pursuant to the 2005 Energy Policy Act and based on research and development activities supported by the Generation IV Nuclear Energy Systems Initiative. The principal objective of the NGNP Project is to support commercialization of the high temperature gas-cooled reactor (HTGR) technology. The HTGR is helium cooled and graphite moderated and can operate at reactor outlet temperatures much higher than those of conventional light water reactor (LWR) technologies. Accordingly, it can be applied in many industrial applications as a substitute for burning fossil fuels, such as natural gas, in addition to producing electricity, which is the principal application of current LWRs. These varied industrial applications may involve a standard HTGR modular design using different Energy Conversion Systems. Additionally, some of these process heat applications will require process heat delivery systems to lie partially outside the HTGR operator’s facility.

  18. NMA supports the industry's agenda in Washington

    SciTech Connect

    Fiscor, S.

    2009-02-15

    New leadership takes over at the National Mining Association, while it readies itself to defend mining interest and educate a new presidential administration and congress. Harold 'Hal' Quinn was appointed CEO on 10 September 2008. In an interview he talks about NMA's top priorities. These include mine safety performance, climate change, training and regulatory issues. The NMA's overall objective is to make sure that USA has a public policy environment that ensures a healthy and vital domestic mining industry so that we can provide the energy and material needed for the public on a cost-effective basis. 1 photo.

  19. A Study of Distance Education for the Needs of the Nuclear Power Industry

    ERIC Educational Resources Information Center

    Reckline, Sigmund Joseph

    2010-01-01

    This research presents an examination of student satisfaction related to online training for adult learners in the nuclear power industry. Both groups, the nuclear industry and its associated workforce, have demonstrable needs which might be met by such programs. The nuclear industry itself faces an expansion of facilities and services combined…

  20. Complete machine vision solution for tube inspection in nuclear industry

    NASA Astrophysics Data System (ADS)

    Seulin, Ralph; Voisin, Yvon; Fofi, David; Meriaudeau, Fabrice

    2004-05-01

    This paper presents various applications of machine vision systems. These systems are used at four strategic points in a company manufacturing pipes for the nuclear industry. For each system, the vision problematic is presented including the industrial constraints, then, the proposed solution is detailed (acquisition conditions, image processing algorithms...), finally, the implementation on the industrial line is described and results are discussed. The first system used in the R&D department controls tube deformation under high pressure and high temperature conditions. The second vision system deals with the surface inspection of outer part as well as inner part of the tubes for scratches as well as oxidation mark detection. After the lamination, tubes are heated to release the mechanical constraints which took place during the lamination process. During the heating, oxidation may occur. Based on color analysis, a machine vision system was developed to measure the oxidation time. Once manufactured, tubes are thoroughly cleaned by air propulsed plugs and packaged in boxes. A system which detects any missing or occluded tubes was realized. The results show that the nuclear industry can take important benefits from machine vision systems. The four validated and implemented applications give satisfactory results and are currently used in the factory.

  1. Private Industry Support to Defense Needs.

    DTIC Science & Technology

    1982-04-19

    Board Study completed in 1976 provides the views of the financial comunity with respect to problems facing subcontractors: Subcontractors to the major...willing to invest to achieve it. 4 National policy in support of defense preparedness, both written and verbalized by the country’s leaders through

  2. Crystallographic services and technology support for industry.

    PubMed

    Neels, Antonia; Sereda, Olha; Bandi, Tobias; Maeder, Xavier

    2014-01-01

    The activities of CSEM's XRD Application Lab are oriented towards the analytical support of technology and product development in the fields of materials sciences, microtechnology, physics, chemistry, nanotechnology and life sciences. Non-destructive X-ray diffraction methods are used for the structural investigation of materials, components and systems. New developments are made with a focus on in situ techniques to 'watch the action' - structural transformations in dependence of applied external fields such as temperature, humidity, magnetic fields or mechanical stresses.

  3. TACOM LCMC Industrial Base Engineering Support - Board of Directors

    DTIC Science & Technology

    2011-07-01

    Provide an overview of the U.S. Army Tank Automotive Research, Development and Engineering Center’s (TARDEC’s) capabilities related to LCMC Industrial ...UNCLASSIFIEDUNCLASSIFIED: Dist A. Approved for public release TACOM LCMC INDUSTRIAL BASE ENGINEERING SUPPORT – Board of Directors TARDEC, Engineering ...number. 1. REPORT DATE 26 JUL 2011 2. REPORT TYPE N/A 3. DATES COVERED - 4. TITLE AND SUBTITLE TACOM LCMC Industrial Base Engineering

  4. Business and Industrial Support of High School Science Education.

    ERIC Educational Resources Information Center

    Glass, Lynn W.

    1983-01-01

    Reasons business and industry participate in educational support are grouped into civic duty, career education, and communication. Support is grouped into five broad categories: employment, equipment and materials, facilities, financial, and personnel. Such sources can help replace the reduced level of funding by government. (MP)

  5. Quantitative risk assessment in aerospace: Evolution from the nuclear industry

    SciTech Connect

    Frank, M.V.

    1996-12-31

    In 1987, the National Aeronautics and Space Administration (NASA) and the aerospace industry relied on failure mode and effects analysis (FMEA) and hazards analysis as the primary tools for safety and reliability of their systems. The FMEAs were reviewed to provide critical items using a set of qualitative criteria. Hazards and critical items judged the worst, by a qualitative method, were to be either eliminated by a design change or controlled by the addition of a safeguard. However, it is frequently the case that limitations of space, weight, technical feasibility, and cost left critical items and hazards unable to be eliminated or controlled. In these situations, program management accepted the risk. How much risk was being accepted was unknown because quantitative risk assessment methods were not used. Perhaps the greatest contribution of the nuclear industry to NASA and the aerospace industry was the introduction of modern (i.e., post-WASH-1400) quantitative risk assessment concepts and techniques. The concepts of risk assessment that have been most useful in the aerospace industry are the following: 1. combination of accident sequence diagrams, event trees, and fault trees to model scenarios and their causative factors; 2. use of Bayesian analysis of system and component failure data; 3. evaluation and presentation of uncertainties in the risk estimates.

  6. Support grid for fuel elements in a nuclear reactor

    DOEpatents

    Finch, Lester M.

    1977-01-01

    A support grid is provided for holding nuclear fuel rods in a rectangular array. Intersecting sheet metal strips are interconnected using opposing slots in the strips to form a rectangular cellular grid structure for engaging the sides of a multiplicity of fuel rods. Spring and dimple supports for engaging fuel and guide rods extending through each cell in the support grid are formed in the metal strips with the springs thus formed being characterized by nonlinear spring rates.

  7. Fitness for duty in the nuclear power industry: A review of technical issues

    SciTech Connect

    Moore, C.; Barnes, V.; Hauth, J.; Wilson, R.; Fawcett-Long, J.; Toquam, J.; Baker, K.; Wieringa, D.; Olson, J.; Christensen, J.

    1989-05-01

    This report presents information gathered and analyzed in support of the US Nuclear Regulatory Commission's (NRC's) efforts to develop a rule that will ensure that workers with unescorted access to protected areas of nuclear power plants are fit for duty. This report supplements information previously published in NUREG/CR-5227, Fitness for Duty in the Nuclear Power Industry: A Review of Technical Issues (Barnes et al., 1988). The primary potential fitness-for-duty concern addressed in both of these reports is impairment caused by substance abuse, although other fitness concerns are discussed. This report addresses issues pertaining to workers' use and misuse of alcohol, prescription drugs, and over-the-counter drugs as fitness-for-duty concerns; responds to several questions raised by NRC Commissioners; discusses subversion of the chemical testing process and methods of preventing such subversion; and examines concerns about the urinalysis cutoff levels used when testing for marijuana metabolites, amphetamines, and phencyclidine (PCP).

  8. Personnel supply and demand issues in the nuclear power industry. Final report of the Nuclear Manpower Study Committee

    SciTech Connect

    Not Available

    1981-01-01

    The anticipated personnel needs of the nuclear power industry have varied widely in recent years, in response to both increasing regulatory requirements and declining orders for new plants. Recent employment patterns in the nuclear energy field, with their fluctuations, resemble those of defense industries more than those traditionally associated with electric utilities. Reactions to the accident at Three Mile Island Unit 2 by industry and regulators have increased the demand for trained and experienced personnel, causing salaries to rise. Industry, for example, has established several advisory organizations like the Institute for Nuclear Power Operations (INPO). At the same time, the US Nuclear Regulatory Commission (NRC) has imposed many new construction and operating requirements in an effort to take advantage of lessons learned from the Three Mile Island incident and to respond to the perceived public interest in better regulation of nuclear power. Thus, at present, utilities, architect-engineer firms, reactor vendors, and organizations in the nuclear development community have heavy workloads.

  9. IAEA support to medical physics in nuclear medicine.

    PubMed

    Meghzifene, Ahmed; Sgouros, George

    2013-05-01

    Through its programmatic efforts and its publications, the International Atomic Energy Agency (IAEA) has helped define the role and responsibilities of the nuclear medicine physicist in the practice of nuclear medicine. This paper describes the initiatives that the IAEA has undertaken to support medical physics in nuclear medicine. In 1984, the IAEA provided guidance on how to ensure that the equipment used for detecting, imaging, and quantifying radioactivity is functioning properly (Technical Document [TECDOC]-137, "Quality Control of Nuclear Medicine Instruments"). An updated version of IAEA-TECDOC-137 was issued in 1991 as IAEA-TECDOC-602, and this included new chapters on scanner-computer systems and single-photon emission computed tomography systems. Nuclear medicine physics was introduced as a part of a project on radiation imaging and radioactivity measurements in the 2002-2003 IAEA biennium program in Dosimetry and Medical Radiation Physics. Ten years later, IAEA activities in this field have expanded to cover quality assurance (QA) and quality control (QC) of nuclear medicine equipment, education and clinical training, professional recognition of the role of medical physicists in nuclear medicine physics, and finally, the coordination of research and development activities in internal dosimetry. As a result of these activities, the IAEA has received numerous requests to support the development and implementation of QA or QC programs for radioactivity measurements in nuclear medicine in many Member States. During the last 5 years, support was provided to 20 Member States through the IAEA's technical cooperation programme. The IAEA has also supported education and clinical training of medical physicists. This type of support has been essential for the development and expansion of the Medical Physics profession, especially in low- and middle-income countries. The need for basic as well as specialized clinical training in medical physics was identified as a

  10. The Role of Ceramics in a Resurgent Nuclear Industry

    SciTech Connect

    Marra, J

    2006-02-28

    With fuel oil and natural gas prices near record highs and worldwide energy demands increasing at an alarming rate, there is growing interest in revitalization of the nuclear power industry within the United States and across the globe. Ceramic materials have long played a very important part in the commercial nuclear industry with applications throughout the entire fuel cycle; from fuel fabrication to waste stabilization. As the international community begins to look at advanced fuel cycles that minimize waste and increase proliferation resistance, ceramic materials will play an even larger role. Many of the advanced reactor concepts being evaluated operate at high-temperature requiring the use of durable, heat-resistant materials. Ceramic fuels are being investigated for a variety of Generation IV reactor concepts. These include the traditional TRISO-coated particles as well as advanced inert-matrix fuels. In order to minimize wastes and legacy materials, ceramic processes are also being applied to fuel reprocessing operations. Ceramic materials continue to provide a vital contribution in ''closing the fuel cycle'' by stabilization of associated low-level and high-level wastes in highly durable grout, ceramics, and glass. In the next five years, programs that are currently in the conceptual phase will begin laboratory- and engineering-scale demonstrations. This will require production-scale demonstrations of several ceramic technologies from fuel form development to advanced stabilization methods. Within the next five to ten years, these demonstrations will move to even larger scales and will also include radioactive demonstrations of these advanced technologies. These radioactive demonstrations are critical to program success and will require advances in ceramic materials associated with nuclear energy applications.

  11. Quality user support supporting quality users. [Historical trends and developments in computer support in the oil and gas industry

    SciTech Connect

    Woolley, T.C.

    1994-10-01

    This paper describes how Oryx Energy Co. addressed problems and opportunities created by the explosive growth in computing power and needs coupled with industry contraction. A successful user-support strategy is described. Characteristics of the program include (1) client-driven support, (2) empowerment of highly skilled professionals to fill the support role, (3) routine and ongoing modification of the support plan, (4) use of the support assignment to create highly trained advocates on the line, and (5) integration of the support role to the reservoir management team. Results of the plan include a highly trained work force, stakeholder teams that include support personnel, and global support from a centralized support organization.

  12. Catalytic ammonia decomposition over industrial-waste-supported Ru catalysts

    SciTech Connect

    Pei Fang Ng; Li Li; Shaobin Wang; Zhonghua Zhu; Gaoqing Lu; Zifeng Yan

    2007-05-15

    Industrial solid wastes (fly ash and red mud, a by-product of the aluminium industry) have been employed as supports for preparation of Ru-based catalysts. Physical and chemical treatments on red mud were conducted and these modified supports were also used for preparation of Ru-based catalysts. Those Ru catalysts were characterized by various techniques such as N2 adsorption, H{sub 2} adsorption, XRD, XPS, and temperature-programmed reduction (TPR), and were then tested for catalytic ammonia decomposition to hydrogen. It was found that red-mud-supported Ru catalyst exhibits higher ammonia conversion and hydrogen production than fly-ash-supported catalyst. Heat and chemical treatments of the red mud greatly improve the catalytic activity. Moreover, a combination of acid and heat treatments produces the highest catalytic conversion of ammonia. 35 refs., 4 figs., 4 tabs.

  13. Examination of pump failure data in the nuclear power industry

    SciTech Connect

    Casada, D.

    1996-12-01

    There are several elements that are critical to any program which is used to optimize the availability and reliability of process equipment. Perhaps the most important elements are routine monitoring and predictive maintenance elements. In order to optimize equipment monitoring and predictive maintenance, it is necessary to fundamentally and thoroughly understand the principal failure modes for the equipment and the effectiveness of alternative monitoring methods. While these observations are general in nature, they are certainly true for the {open_quotes}heart{close_quotes} of fluid systems - pumps. In recent years, particularly within the last decade, the capabilities and ease of use of previously existing pump diagnostic technologies, such as vibration monitoring and oil analysis, have improved dramatically. Newer technologies, such as thermal imaging, have been found effective at detecting certain undesirable or degraded conditions, such as misalignment and overheated bearings or packing. The ASME Code and NRC regulatory requirements have been, like essentially all similar code and regulatory bodies, conservative in their adoption or endorsement of newer technologies. The requirements prescribed by the Code and endorsed by the NRC have, in their essence, changed only minimally over more than a dozen years. As a follow-on to studies of check valve failure experience in the nuclear industry that have proven useful in identifying the effectiveness of alternative monitoring methods, a study of nuclear industry pump failure data has been conducted. The results of this study, conducted for the NRC by Oak Ridge National Laboratory, are presented. The historical effectiveness of both regulatory required and voluntarily implemented pump monitoring programs are shown. The distribution of pump failures by application, affected area, and level of significance are indicated. Apparent strengths and weaknesses of alternative monitoring methods are discussed.

  14. Support for Industrialization as a Means to Rural Development.

    ERIC Educational Resources Information Center

    McLean, Edward L.; Colclough, Glenna

    To determine degree of local support for industrialization as a means of rural economic development, leaders and influentials in three South Carolina counties were interviewed in 1977. Each was asked to define "development" and to list and rank three aspects of his county he especially liked and its most important needs or problems.…

  15. Generalized Nuclear Data: A New Structure (with Supporting Infrastructure) for Handling Nuclear Data

    NASA Astrophysics Data System (ADS)

    Mattoon, C. M.; Beck, B. R.; Patel, N. R.; Summers, N. C.; Hedstrom, G. W.; Brown, D. A.

    2012-12-01

    The Evaluated Nuclear Data File (ENDF) format was designed in the 1960s to accommodate neutron reaction data to support nuclear engineering applications in power, national security and criticality safety. Over the years, the scope of the format has been extended to handle many other kinds of data including charged particle, decay, atomic, photo-nuclear and thermal neutron scattering. Although ENDF has wide acceptance and support for many data types, its limited support for correlated particle emission, limited numeric precision, and general lack of extensibility mean that the nuclear data community cannot take advantage of many emerging opportunities. More generally, the ENDF format provides an unfriendly environment that makes it difficult for new data evaluators and users to create and access nuclear data. The Cross Section Evaluation Working Group (CSEWG) has begun the design of a new Generalized Nuclear Data (or 'GND') structure, meant to replace older formats with a hierarchy that mirrors the underlying physics, and is aligned with modern coding and database practices. In support of this new structure, Lawrence Livermore National Laboratory (LLNL) has updated its nuclear data/reactions management package Fudge to handle GND structured nuclear data. Fudge provides tools for converting both the latest ENDF format (ENDF-6) and the LLNL Evaluated Nuclear Data Library (ENDL) format to and from GND, as well as for visualizing, modifying and processing (i.e., converting evaluated nuclear data into a form more suitable to transport codes) GND structured nuclear data. GND defines the structure needed for storing nuclear data evaluations and the type of data that needs to be stored. But unlike ENDF and ENDL, GND does not define how the data are to be stored in a file. Currently, Fudge writes the structured GND data to a file using the eXtensible Markup Language (XML), as it is ASCII based and can be viewed with any text editor. XML is a meta-language, meaning that it

  16. Nuclear Data Activities in Support of the DOE Nuclear Criticality Safety Program

    NASA Astrophysics Data System (ADS)

    Westfall, R. M.; McKnight, R. D.

    2005-05-01

    The DOE Nuclear Criticality Safety Program (NCSP) provides the technical infrastructure maintenance for those technologies applied in the evaluation and performance of safe fissionable-material operations in the DOE complex. These technologies include an Analytical Methods element for neutron transport as well as the development of sensitivity/uncertainty methods, the performance of Critical Experiments, evaluation and qualification of experiments as Benchmarks, and a comprehensive Nuclear Data program coordinated by the NCSP Nuclear Data Advisory Group (NDAG). The NDAG gathers and evaluates differential and integral nuclear data, identifies deficiencies, and recommends priorities on meeting DOE criticality safety needs to the NCSP Criticality Safety Support Group (CSSG). Then the NDAG identifies the required resources and unique capabilities for meeting these needs, not only for performing measurements but also for data evaluation with nuclear model codes as well as for data processing for criticality safety applications. The NDAG coordinates effort with the leadership of the National Nuclear Data Center, the Cross Section Evaluation Working Group (CSEWG), and the Working Party on International Evaluation Cooperation (WPEC) of the OECD/NEA Nuclear Science Committee. The overall objective is to expedite the issuance of new data and methods to the DOE criticality safety user. This paper describes these activities in detail, with examples based upon special studies being performed in support of criticality safety for a variety of DOE operations.

  17. Health physics activities in support of the thermal shield removal/disposal and core support barrel repair at the St. Lucie Nuclear Power Plant.

    PubMed

    Maisler, J J; Buchanan, H F

    1988-02-01

    The health physics activities related to the removal and disposal of a thermal shield at a nuclear power plant and subsequent repairs to the core support barrel required increased planning relative to a normal refueling/maintenance outage. The repair of the core support barrel was a "first" in the nuclear power industry. Pre-job planning was of great concern because of extremely high radiation levels associated with the irradiated stainless steel thermal shield and core support barrel. ALARA techniques used in the preparation of the thermal shield for removal and shipment to the disposal site are discussed.

  18. Development of Interactive Industrial Design Support System Considering Customer's Evaluation

    NASA Astrophysics Data System (ADS)

    Yanagisawa, Hideyoshi; Fukuda, Shuichi

    To respond to rapidly changing and diversifying customers' requirements, an industrial design support system for eyeglass frames which allows the customer to participate in the industrial design process was developed. This system is based on the Interactive Evolutionary Computing (IEC) technique so that a customer can interact with the system to express his or her Kansei requirements through images. The design of an eyeglass frame cannot be determined in isolation but rather must be determined by considering its appearance on the customer. In the developed system, the user evaluates each sample suggested by the system and narrows down the candidate gradually. Its usefulness was demonstrated by operational experiments and questionnaires.

  19. Support arrangement for core modules of nuclear reactors

    DOEpatents

    Bollinger, Lawrence R.

    1987-01-01

    A support arrangement is provided for the core modules of a nuclear reactor which provides support access through the control drive mechanisms of the reactor. This arrangement provides axial support of individual reactor core modules from the pressure vessel head in a manner which permits attachment and detachment of the modules from the head to be accomplished through the control drive mechanisms after their leadscrews have been removed. The arrangement includes a module support nut which is suspended from the pressure vessel head and screw threaded to the shroud housing for the module. A spline lock prevents loosening of the screw connection. An installation tool assembly, including a cell lifting and preloading tool and a torquing tool, fits through the control drive mechanism and provides lifting of the shroud housing while disconnecting the spline lock, as well as application of torque to the module support nut.

  20. Support arrangements for core modules of nuclear reactors. [PWR

    DOEpatents

    Bollinger, L.R.

    1983-11-03

    A support arrangement is provided for the core modules of a nuclear reactor which provides support access through the control drive mechanisms of the reactor. This arrangement provides axial support of individual reactor core modules from the pressure vessel head in a manner which permits attachment and detachment of the modules from the head to be accomplished through the control drive mechanisms after their leadscrews have been removed. The arrangement includes a module support nut which is suspended from the pressure vessel head and screw threaded to the shroud housing for the module. A spline lock prevents loosening of the screw connection. An installation tool assembly, including a cell lifting and preloading tool and a torquing tool, fits through the control drive mechanism and provides lifting of the shroud housing while disconnecting the spline lock, as well as application of torque to the module support nut.

  1. Nuclear Energy R&D Imperative 3: Enable a Transition Away from Fossil Fuel in the Transportation and Industrial Sectors

    SciTech Connect

    David Petti; J. Stephen Herring

    2010-03-01

    security through more effective utilization of our country’s resources while simultaneously providing economic stability and growth (through predictable energy prices and high value jobs), in an environmentally sustainable and secure manner (through lower land and water use, and decreased byproduct emissions). The reduction in imported oil will also increase the retention of wealth within the U.S. economy while still supporting economic growth. Nuclear energy is the only non-fossil fuel that has been demonstrated to reliably supply energy for a growing industrial economy.

  2. The European nuclear power industry: Restructuring for combined strength and worldwide leadership

    SciTech Connect

    Forsberg, C.W.; Norman, R.E.; Reich, W.J.; Hill, L.J.

    1993-06-18

    The European nuclear power industry is being restructured from an industry drawn along national lines to a European-wide industry. This, in part, reflects growth of the European Economic Community, but it also reflects changes in the international nuclear power industry. The objectives of the participants, beyond better integration of the nuclear industry in Western Europe, are to (1) obtain European leadership of the worldwide commercial nuclear power industry, (2) improve medium- and long-term safety of Eastern Europe and the former Soviet Union (FSU) power reactors, and (3) reduce domestic concerns about nuclear power. The activities to achieve these goals include (1) formation of Nuclear Power International (a joint venture of the German and French nuclear power plant vendors for design and construction of nuclear power plants), (2) formation of a utility group to forge agreement throughout Europe on what the requirements are for the next generation of nuclear power plants, and (3) agreement by regulators in multiple European countries to harmonize regulations. This is to be achieved before the end of the decade. These changes would allow a single design of nuclear power plant to be built anywhere in Europe. The creation of European-wide rules (utility requirements, engineering standards, and national regulations) would create strong economic and political forces for other European countries (Eastern Europe and FSU) to meet these standards.

  3. Supporting the future nuclear workforce with computer-based procedures

    SciTech Connect

    Oxstrand, Johanna; Le Blanc, Katya

    2016-05-01

    Here we see that computer-based tools have dramatically increased ease and efficiency of everyday tasks. Gone are the days of paging through a paper catalog, transcribing product numbers, and calculating totals. Today, a consumer can find a product online with a simple search engine, and then purchase it in a matter of a few clicks. Paper catalogs have their place, but it is hard to imagine life without on-line shopping sites. All tasks conducted in a nuclear power plant are guided by procedures, which helps ensure safe and reliable operation of the plants. One prominent goal of the nuclear industry is to minimize the risk of human errors. To achieve this goal one has to ensure tasks are correctly and consistently executed. This is partly achieved by training and by a structured approach to task execution, which is provided by procedures and work instructions. Procedures are used in the nuclear industry to direct workers' actions in a proper sequence. The governing idea is to minimize the reliance on memory and choices made in the field. However, the procedure document may not contain sufficient information to successfully complete the task. Therefore, the worker might have to carry additional documents such as turnover sheets, operation experience, drawings, and other procedures to the work site. The nuclear industry is operated with paper procedures like paper catalogs of the past. A field worker may carry a large stack of documents needed to complete a task to the field. Even though the paper process has helped keep the industry safe for decades, there are limitations to using paper. Paper procedures are static (i.e., the content does not change after the document is printed), difficult to search, and rely heavily on the field worker’s situational awareness and ability to consistently meet the high expectation of human performance excellence. With computer-based procedures (CBPs) that stack of papers may be reduced to the size of a small tablet or even a smart

  4. Commercial Nuclear Power Industry: Assessing and Meeting the Radiation Protection Workforce Needs.

    PubMed

    Hiatt, Jerry W

    2017-02-01

    This paper will provide an overview of the process used by the commercial nuclear power industry in assessing the status of existing industry staffing and projecting future supply demand needs. The most recent Nuclear Energy Institute-developed "Pipeline Survey Results" will be reviewed with specific emphasis on the radiation protection specialty. Both radiation protection technician and health physicist specialties will be discussed. The industry-initiated Nuclear Uniform Curriculum Program will be reviewed as an example of how the industry has addressed the need for developing additional resources. Furthermore, the reality of challenges encountered in maintaining the needed number of health physicists will also be discussed.

  5. Supporting R&D of industrial fuel cell developers.

    SciTech Connect

    Krumpelt, M.

    1998-09-11

    Argonne National Laboratory is supporting the industrial developers of molten carbonate fuel cells (MCFCs) and tubular solid oxide fuel cells (SOFCs). The results suggest that a lithium concentration level of 65-75 mol% in the LiNa electrolyte will improve cell performance. They have made inroads in understanding the interfacial resistance of bipolar plate materials, and they have reduced the air electrode overpotential in OSFCs by adding dopants.

  6. SUPPORT DEVICE FOR USE IN A NUCLEAR REACTOR

    DOEpatents

    Greenhalgh, F.G.; Long, E.

    1959-03-10

    A shock absorbing support device for fuel elements in a nuclear reactor is described. The device is adapted to support a column of moderator material on a lower support plate of a reactor structure and to axially locate the column of moderator with respect to the coolant fluid entry port in the support plate. Located centrally of the device is a vestically extending shaft member telescopingly engaged at its lower end with a tubular member and connected to the tubular member by a shear pin. Below the shear pin embedded in the end of the shaft member are blade members which are adapted to cut into the side of the tubular member in the went the shear pin is destroyed by the impact or a falling fuel element. The cutting action of the blades in the tube absorbes the shock of the fallen element.

  7. Anomalies in Proposed Regulations for the Release of Redundant Material from Nuclear and Non-nuclear Industries

    SciTech Connect

    Menon, S.

    2002-02-26

    Now that increasing numbers of nuclear power stations are reaching the end of their commercially useful lives, the management of the large quantities of very low level radioactive material that arises during their decommissioning has become a major subject of discussion, with very significant economic implications. Much of this material can, in an environmentally advantageous manner, be recycled for reuse without radiological restrictions. Much larger quantities--2-3 orders of magnitude larger--of material, radiologically similar to the candidate material for recycling from the nuclear industry, arise in non-nuclear industries like coal, fertilizer, oil and gas, mining, etc. In such industries, naturally occurring radioactivity is artificially concentrated in products, by-products or waste to form TENORM (Technologically Enhanced Naturally Occurring Radioactive Material). It is only in the last decade that the international community has become aware of the prevalence of T ENORM, specially the activity levels and quantities arising in so many nonnuclear industries. The first reaction of international organizations seems to have been to propose ''double'' standards for the nuclear and non-nuclear industries, with very stringent release criteria for radioactive material from the regulated nuclear industry and up to a hundred times more liberal criteria for the release/exemption of TENORM from the as yet unregulated non-nuclear industries. There are, however, many significant strategic issues that need to be discussed and resolved. An interesting development, for both the nuclear and non-nuclear industries, is the increased scientific scrutiny that the populations of naturally high background dose level areas of the world are being subject to. Preliminary biological studies have indicated that the inhabitants of such areas, exposed to many times the permitted occupational doses for nuclear workers, have not shown any differences in cancer mortality, life expectancy

  8. Supporting the future nuclear workforce with computer-based procedures

    DOE PAGES

    Oxstrand, Johanna; Le Blanc, Katya

    2016-05-01

    Here we see that computer-based tools have dramatically increased ease and efficiency of everyday tasks. Gone are the days of paging through a paper catalog, transcribing product numbers, and calculating totals. Today, a consumer can find a product online with a simple search engine, and then purchase it in a matter of a few clicks. Paper catalogs have their place, but it is hard to imagine life without on-line shopping sites. All tasks conducted in a nuclear power plant are guided by procedures, which helps ensure safe and reliable operation of the plants. One prominent goal of the nuclear industrymore » is to minimize the risk of human errors. To achieve this goal one has to ensure tasks are correctly and consistently executed. This is partly achieved by training and by a structured approach to task execution, which is provided by procedures and work instructions. Procedures are used in the nuclear industry to direct workers' actions in a proper sequence. The governing idea is to minimize the reliance on memory and choices made in the field. However, the procedure document may not contain sufficient information to successfully complete the task. Therefore, the worker might have to carry additional documents such as turnover sheets, operation experience, drawings, and other procedures to the work site. The nuclear industry is operated with paper procedures like paper catalogs of the past. A field worker may carry a large stack of documents needed to complete a task to the field. Even though the paper process has helped keep the industry safe for decades, there are limitations to using paper. Paper procedures are static (i.e., the content does not change after the document is printed), difficult to search, and rely heavily on the field worker’s situational awareness and ability to consistently meet the high expectation of human performance excellence. With computer-based procedures (CBPs) that stack of papers may be reduced to the size of a small tablet or even

  9. Support vector machines for nuclear reactor state estimation

    SciTech Connect

    Zavaljevski, N.; Gross, K. C.

    2000-02-14

    Validation of nuclear power reactor signals is often performed by comparing signal prototypes with the actual reactor signals. The signal prototypes are often computed based on empirical data. The implementation of an estimation algorithm which can make predictions on limited data is an important issue. A new machine learning algorithm called support vector machines (SVMS) recently developed by Vladimir Vapnik and his coworkers enables a high level of generalization with finite high-dimensional data. The improved generalization in comparison with standard methods like neural networks is due mainly to the following characteristics of the method. The input data space is transformed into a high-dimensional feature space using a kernel function, and the learning problem is formulated as a convex quadratic programming problem with a unique solution. In this paper the authors have applied the SVM method for data-based state estimation in nuclear power reactors. In particular, they implemented and tested kernels developed at Argonne National Laboratory for the Multivariate State Estimation Technique (MSET), a nonlinear, nonparametric estimation technique with a wide range of applications in nuclear reactors. The methodology has been applied to three data sets from experimental and commercial nuclear power reactor applications. The results are promising. The combination of MSET kernels with the SVM method has better noise reduction and generalization properties than the standard MSET algorithm.

  10. An Overview of the Regulation of Low Dose Radiation in the Nuclear and Non-nuclear Industries

    SciTech Connect

    Menon, Shankar; Valencia, Luis; Teunckens, Lucien

    2003-02-27

    Now that increasing numbers of nuclear power stations are reaching the end of their commercially useful lives, the management of the large quantities of very low level radioactive material that arises during their decommissioning has become a major subject of discussion, with very significant economic implications. Much of this material can, in an environmentally advantageous manner, be recycled for reuse without radiological restrictions. Much larger quantities--2-3 orders of magnitude larger--of material, radiologically similar to the candidate material for recycling from the nuclear industry, arise in non-nuclear industries like coal, fertilizer, oil and gas, mining, etc. In such industries, naturally occurring radioactivity is artificially concentrated in products, by-products or waste to form TENORM (Technologically Enhanced Naturally Occurring Radioactive Material). It is only in the last decade that the international community has become aware of the prevalence of TENORM, specially the activity levels and quantities arising in so many non-nuclear industries. The first reaction of international organizations seems to have been to propose different standards for the nuclear and non-nuclear industries, with very stringent release criteria for radioactive material from the regulated nuclear industry and up to thirty to a hundred times more liberal criteria for the release/exemption of TENORM from the as yet unregulated non-nuclear industries. There are significant strategic issues that need to be discussed and resolved. Some examples of these are: - Disposal aspects of long-lived nuclides, - The use of radioactive residues in building materials, - Commercial aspects of differing and discriminating criteria in competing power industries in a world of deregulated electric power production. Of even greater importance is the need for the discussion of certain basic issues, such as - The quantitative risk levels of exposure to ionizing radiation, - The need for in

  11. Status and prospect of NDT technology for nuclear energy industry in Korea

    NASA Astrophysics Data System (ADS)

    Lee, Joon Hyun

    2016-02-01

    Innovative energy technology is considered to be one of the key solutions for meeting the challenges of climate change and energy security, which is why global leaders are focusing on enhancing energy technology R&D. In accordance with the global movements to accelerate energy R&D, the Korean government has made significant investments in a broad spectrum of energy R&D programs, including energy efficiency, resources, CCS, new and renewable energy, power generation and electricity delivery, nuclear power and nuclear waste management. In order to manage government sponsored energy R&D programs in an efficient and effective way, the government established the Korea Institute of Energy technology Evaluation and Planning (KETEP) in 2009. Main activities of KETEP include developing energy technology roadmaps, planning, evaluating, and managing R&D programs, fostering experts in the field of energy, promoting international cooperation programs, gathering and analyzing energy statistics, and supporting infrastructure and commercialization. KETEP assists the Ministry of Trade, Industry and Energy in developing national R&D strategies while also working with researchers, universities, national institutes and the private sector for their successful energy technology and deployment. This presentation consists of three parts. First, I will introduce the characteristics of energy trends and mix in Korea. Then, I'll speak about the related national R&D strategies of energy technology. Finally, I'll finish up with the status and prospect of NDT technology for nuclear energy industry in Korea. The development of the on-line structural integrity monitoring systems and the related techniques in Korean nuclear power plant for the purpose of condition based maintenance is introduced. The needs of NDT techniques for inspection and condition monitoring for GEN IV including SFR, small module reactor etc., are also discussed.

  12. Thermal barrier and support for nuclear reactor fuel core

    DOEpatents

    Betts, Jr., William S.; Pickering, J. Larry; Black, William E.

    1987-01-01

    A thermal barrier/core support for the fuel core of a nuclear reactor having a metallic cylinder secured to the reactor vessel liner and surrounded by fibrous insulation material. A top cap is secured to the upper end of the metallic cylinder that locates and orients a cover block and post seat. Under normal operating conditions, the metallic cylinder supports the entire load exerted by its associated fuel core post. Disposed within the metallic cylinder is a column of ceramic material, the height of which is less than that of the metallic cylinder, and thus is not normally load bearing. In the event of a temperature excursion beyond the design limits of the metallic cylinder and resulting in deformation of the cylinder, the ceramic column will abut the top cap to support the fuel core post.

  13. Supported liquid inorganic membranes for nuclear waste separation

    DOEpatents

    Bhave, Ramesh R; DeBusk, Melanie M; DelCul, Guillermo D; Delmau, Laetitia H; Narula, Chaitanya K

    2015-04-07

    A system and method for the extraction of americium from radioactive waste solutions. The method includes the transfer of highly oxidized americium from an acidic aqueous feed solution through an immobilized liquid membrane to an organic receiving solvent, for example tributyl phosphate. The immobilized liquid membrane includes porous support and separating layers loaded with tributyl phosphate. The extracted solution is subsequently stripped of americium and recycled at the immobilized liquid membrane as neat tributyl phosphate for the continuous extraction of americium. The sequestered americium can be used as a nuclear fuel, a nuclear fuel component or a radiation source, and the remaining constituent elements in the aqueous feed solution can be stored in glassified waste forms substantially free of americium.

  14. A computer tool to support in design of industrial Ethernet.

    PubMed

    Lugli, Alexandre Baratella; Santos, Max Mauro Dias; Franco, Lucia Regina Horta Rodrigues

    2009-04-01

    This paper presents a computer tool to support in the project and development of an industrial Ethernet network, verifying the physical layer (cables-resistance and capacitance, scan time, network power supply-POE's concept "Power Over Ethernet" and wireless), and occupation rate (amount of information transmitted to the network versus the controller network scan time). These functions are accomplished without a single physical element installed in the network, using only simulation. The computer tool has a software that presents a detailed vision of the network to the user, besides showing some possible problems in the network, and having an extremely friendly environment.

  15. Development of Asset Fault Signatures for Prognostic and Health Management in the Nuclear Industry

    SciTech Connect

    Vivek Agarwal; Nancy J. Lybeck; Randall Bickford; Richard Rusaw

    2014-06-01

    Proactive online monitoring in the nuclear industry is being explored using the Electric Power Research Institute’s Fleet-Wide Prognostic and Health Management (FW-PHM) Suite software. The FW-PHM Suite is a set of web-based diagnostic and prognostic tools and databases that serves as an integrated health monitoring architecture. The FW-PHM Suite has four main modules: Diagnostic Advisor, Asset Fault Signature (AFS) Database, Remaining Useful Life Advisor, and Remaining Useful Life Database. This paper focuses on development of asset fault signatures to assess the health status of generator step-up generators and emergency diesel generators in nuclear power plants. Asset fault signatures describe the distinctive features based on technical examinations that can be used to detect a specific fault type. At the most basic level, fault signatures are comprised of an asset type, a fault type, and a set of one or more fault features (symptoms) that are indicative of the specified fault. The AFS Database is populated with asset fault signatures via a content development exercise that is based on the results of intensive technical research and on the knowledge and experience of technical experts. The developed fault signatures capture this knowledge and implement it in a standardized approach, thereby streamlining the diagnostic and prognostic process. This will support the automation of proactive online monitoring techniques in nuclear power plants to diagnose incipient faults, perform proactive maintenance, and estimate the remaining useful life of assets.

  16. Fostering a Renewable Energy Technology Industry: An InternationalComparison of Wind Industry Policy Support Mechanisms

    SciTech Connect

    Lewis, Joanna; Wiser, Ryan

    2005-11-15

    This article examines the importance of national and sub-national policies in supporting the development of successful global wind turbine manufacturing companies. We explore the motivations behind establishing a local wind power industry, and the paths that different countries have taken to develop indigenous large wind turbine manufacturing industries within their borders. This is done through a cross-country comparison of the policy support mechanisms that have been employed to directly and indirectly promote wind technology manufacturing in twelve countries. We find that in many instances there is a clear relationship between a manufacturer's success in its home country market and its eventual success in the global wind power market. Whether new wind turbine manufacturing entrants are able to succeed will likely depend in part on the utilization of their turbines in their own domestic market, which in turn will be influenced by the annual size and stability of that market. Consequently, policies that support a sizable, stable market for wind power, in conjunction with policies that specifically provide incentives for wind power technology to be manufactured locally, are most likely to result in the establishment of an internationally competitive wind industry.

  17. NUCLEAR-FUELED CIRCULATORY SUPPORT SYSTEMS IV: RADIOLOGIC PERSPECTIVES

    PubMed Central

    Huffman, F. N.; Norman, J. C.

    1974-01-01

    If an implantable artificial heart can be developed, it should prove beneficial to a significant group of patients. A variety of energy sources, such as biologic, electromagnetic, and nuclear, are under evaluation. Currently, biologic fuel cell technology is not sufficiently advanced to permit its extrapolation to the power levels required for implantable circulatory support systems. Electromagnetic systems have the disadvantage of heavy batteries of considerable bulk requiring frequent recharging. Radioisotope-fueled thermal engine systems have the potential of providing degrees of freedom not possible with rechargeable units. However, radiosotope circulatory support systems subject their recipients to prolonged intracorporeal radiation, add to environmental background radiation, and constitute an exceedingly small, but finite, hazard due to possible violation of fuel containment. PMID:15215965

  18. The alternative strategies of the development of the nuclear power industry in the 21st century

    NASA Astrophysics Data System (ADS)

    Goverdovskii, A. A.; Kalyakin, S. G.; Rachkov, V. I.

    2014-05-01

    This paper emphasizes the urgency of scientific-and-technical and sociopolitical problems of the modern nuclear power industry without solving of which the transition from local nuclear power systems now in operation to a large-scale nuclear power industry would be impossible. The existing concepts of the longterm strategy of the development of the nuclear power industry have been analyzed. On the basis of the scenarios having been developed it was shown that the most promising alternative is the orientation towards the closed nuclear fuel cycle with fast neutron reactors (hereinafter referred to as fast reactors) that would meet the requirements on the acceptable safety. It was concluded that the main provisions of "The Strategy of the Development of the Nuclear Power Industry of Russia for the First Half of the 21st Century" approved by the Government of the Russian Federation in the year 2000 remain the same at present as well, although they require to be elaborated with due regard for new realities in the market for fossil fuels, the state of both the Russian and the world economy, as well as tightening of requirements related to safe operation of nuclear power stations (NPSs) (for example, after the severe accident at the Fukushima nuclear power station, Japan) and nonproliferation of nuclear weapons.

  19. Technical Support Section Instrument Support Program for Nuclear and Nonnuclear Facilities with Safety Requirements

    SciTech Connect

    Adkisson, B.P.

    1995-01-01

    This document describes the requirements, procedures, and responsibilities of the Instrumentation and Controls (I and C) Division's Technical Support Section (TSS) for instruments identified in nonreactor nuclear and nonnuclear facilities at Oak Ridge National Laboratory (ORNL) with Operational Safety Requirements (OSRs) or Limiting Conditions Documents (LCDs). As a result of DOE order 5480.22 Technical Safety Requirements (TSRs), OSRs, and LCDs for nuclear facilities will be eventually replaced by TSRs. OSRs or LCDs will continue to be required for high-, moderate-, or low-level radiological nonnuclear facilities. The objective of this document is to present an instrument surveillance plan for nonreactor nuclear and nonnuclear facility-identified instruments or systems as specified in the facility's OSR, LCD, or TSR. The instrument surveillance plan is a collaborative effort between the facility manager and the I and C Division TSS staff, thereby ensuring that the surveillance requirements stated in the OSR, LCD, or TSR are fulfilled within the required time frame.

  20. Real-time 3D radiation risk assessment supporting simulation of work in nuclear environments.

    PubMed

    Szőke, I; Louka, M N; Bryntesen, T R; Bratteli, J; Edvardsen, S T; RøEitrheim, K K; Bodor, K

    2014-06-01

    This paper describes the latest developments at the Institute for Energy Technology (IFE) in Norway, in the field of real-time 3D (three-dimensional) radiation risk assessment for the support of work simulation in nuclear environments. 3D computer simulation can greatly facilitate efficient work planning, briefing, and training of workers. It can also support communication within and between work teams, and with advisors, regulators, the media and public, at all the stages of a nuclear installation's lifecycle. Furthermore, it is also a beneficial tool for reviewing current work practices in order to identify possible gaps in procedures, as well as to support the updating of international recommendations, dissemination of experience, and education of the current and future generation of workers.IFE has been involved in research and development into the application of 3D computer simulation and virtual reality (VR) technology to support work in radiological environments in the nuclear sector since the mid 1990s. During this process, two significant software tools have been developed, the VRdose system and the Halden Planner, and a number of publications have been produced to contribute to improving the safety culture in the nuclear industry.This paper describes the radiation risk assessment techniques applied in earlier versions of the VRdose system and the Halden Planner, for visualising radiation fields and calculating dose, and presents new developments towards implementing a flexible and up-to-date dosimetric package in these 3D software tools, based on new developments in the field of radiation protection. The latest versions of these 3D tools are capable of more accurate risk estimation, permit more flexibility via a range of user choices, and are applicable to a wider range of irradiation situations than their predecessors.

  1. The Emergence of the Nuclear Industry and Associated Crime

    DTIC Science & Technology

    1991-08-01

    was Martin Sobell, who was convicted and sentenced to thirty years in prison. He was confined for five years at Alcatraz and was later transferred to...Washington: GPO, 1973): 111-1. 11 Dan O’Niel, "Project Chariot: How Alaska Escaped Nuclear Excavation," The Bulletin of thg Atomic Scientists 45, no...Chariot: How Alaska Escaped Nuclear Excavation." The Bulletin of the Atomic Scientists 45, no. 10 (1989): 28-37. Otway, Harry J., Dagmar Maurer, and

  2. Understanding the Challenges in the Transition from Film Radiography in the Nuclear Power Industry

    SciTech Connect

    Meyer, Ryan M.; Ramuhalli, Pradeep; Moran, Traci L.; Nove, Carol A.; Pardini, Allan F.

    2012-09-01

    Nondestructive examination (NDE) applications in the nuclear power industry using film radiography are shrinking due to the advent of modern digital imaging technologies and advances in alternative inspection methods that do not present an ionizing radiation hazard. Technologies that are used routinely in the medical industry for patient diagnosis are being adapted to industrial NDE applications including the detection and characterization of defects in welds. From the user perspective, non-film inspection techniques provide several advantages over film techniques. It is anticipated that the shift away from the application of film radiography in the nuclear power industry represents an irreversible trend. The U.S. Nuclear Regulatory Commission (NRC) has noted this trend in the U.S. nuclear power industry and will be working to ensure that the effectiveness and reliability of component inspections is not compromised by this transition. Currently, specific concerns are associated with 1) obtaining a fundamental understanding of how inspection effectiveness and reliability may be impacted by this transition and 2) ensuring training standards and qualifications remain compatible with modern industrial radiographic practice. This paper discusses recent trends in industrial radiography and assesses their advantages and disadvantages from the perspective of nuclear power plant component inspections.

  3. Nuclear Forensics: Scientific Analysis Supporting Law Enforcement and Nuclear Security Investigations.

    PubMed

    Keegan, Elizabeth; Kristo, Michael J; Toole, Kaitlyn; Kips, Ruth; Young, Emma

    2016-02-02

    Nuclear forensic science, or "nuclear forensic", aims to answer questions about nuclear material found outside of regulatory control. In this Feature, we provide a general overview of nuclear forensics, selecting examples of key "nuclear forensic signatures" which have allowed investigators to determine the identity of unknown nuclear material in real investigations.

  4. Pipe support for use in a nuclear system

    DOEpatents

    Pollono, Louis P.; Mello, Raymond M.

    1977-01-01

    A pipe support for high temperature, thin-walled vertical piping runs used in a nuclear system. A cylindrical pipe transition member, having the same inside diameter as the thin-walled piping, replaces a portion of the piping where support is desired. The outside diameter of the pipe transition member varies axially along its vertical dimension. For a section of the axial length adjacent the upper and lower terminations of the pipe transition member, the outside diameter is the same as the outside diameter of the thin-walled piping to which it is affixed. Intermediate of the termination sections, the outside diameter increases from the top of the member to the bottom. Adjacent the lower termination section, the diameter abruptly becomes the same as the piping. Thus, the cylindrical transition member is formed to have a generally triangular shaped cross-section along the axial dimension. Load-bearing insulation is installed next to the periphery of the member and is kept in place by an outer ring clamp. The outer ring clamp is connected to pipe hangers, which provide the desired support for the vertical thin-walled piping runs.

  5. Development program to support industrial coal gasification. Quarterly report 1

    SciTech Connect

    1982-01-15

    The Development Program to Support Industrial Coal Gasification is on schedule. The efforts have centered on collecting background information and data, planning, and getting the experimental program underway. The three principal objectives in Task I-A were accomplished. The technical literature was reviewed, the coals and binders to be employed were selected, and tests and testing equipment to be used in evaluating agglomerates were developed. The entire Erie Mining facility design was reviewed and a large portion of the fluidized-bed coal gasification plant design was completed. Much of the work in Task I will be experimental. Wafer-briquette and roll-briquette screening tests will be performed. In Task II, work on the fluidized-bed gasification plant design will be completed and work on a plant design involving entrained-flow gasifiers will be initiated.

  6. Preloading of bolted connections in nuclear reactor component supports

    SciTech Connect

    Yahr, G T

    1984-10-01

    A number of failures of threaded fasteners in nuclear reactor component supports have been reported. Many of those failures were attributed to stress corrosion cracking. This report discusses how stress corrosion cracking can be avoided in bolting by controlling the maximum bolt preloads so that the sustained stresses in the bolts are below the level required to cause stress corrosion cracking. This is a basic departure from ordinary bolted joint design where the only limits on preload are on the minimum preload. Emphasis is placed on the importance of detailed analysis to determine the acceptable range of preload and the selection of a method for measuring the preload that is sufficiently accurate to ensure that the preload is actually within the acceptable range. Procedures for determining acceptable preload range are given, and the accuracy of various methods of measuring preload is discussed.

  7. Matching Grant to Support Nuclear Engineering Education at Georgia Tech, September 1, 1999 - September 30, 2001

    SciTech Connect

    Valentine, John

    2002-05-10

    During the 2001 Fiscal year, funds from the DOE Matching Grant Program, along with matching funds from the industrial sponsors have been used to support both research (in the area of thermal-hydraulics) and educational missions. Experimental research has been performed in the area of axial offset anomaly in pressurized water reactors. Numerical research has also been performed in the area of multi-fluid modeling of two-phase flow. Details of activities in these two areas are given below. As for the educational component, funds were used to support the Georgia Tech Nuclear and Radiological Engineering (NRE) Scholarship Program. This Scholarship Program has allowed Georgia Tech to substantially increase the freshman class size and to populate it with outstanding students.

  8. [Occupational medicine in nuclear industry and power engineering].

    PubMed

    Gus'kova, A K

    2004-01-01

    The author analysed results of medical service in atomic industry and power engineering over 50 years. Those results are beneficial for management in occupational medicine for any new complicated and potentially dangerous technology and activity.

  9. The approach to risk analysis in three industries - Nuclear power, space systems, and chemical process

    NASA Astrophysics Data System (ADS)

    Garrick, B. J.

    A review is presented of how safety and risk analysis is conducted in the three major industries of space flight, nuclear power, and chemical and petroleum processes. This review is presented in the belief that safety enhancements and efficiencies may result from a greater exchange of risk assessment technology between these industries. The focus of this review relates to the engineered systems involved in the three industries.

  10. Supported Molecular Iridium Catalysts: Resolving Effects of Metal Nuclearity and Supports as Ligands

    SciTech Connect

    Lu, Jing; Serna, Pedro; Aydin, Cerem; Browning, Nigel D.; Gates, Bruce C.

    2012-02-07

    The performance of a supported catalyst is influenced by the size and structure of the metal species, the ligands bonded to the metal, and the support. Resolution of these effects has been lacking because of the lack of investigations of catalysts with uniform and systematically varied catalytic sites. We now demonstrate that the performance for ethene hydrogenation of isostructural iridium species on supports with contrasting properties as ligands (electron-donating MgO and electron-withdrawing HY zeolite) can be elucidated on the basis of molecular concepts. Spectra of the working catalysts show that the catalytic reaction rate is determined by the dissociation of H{sub 2} when the iridium, either as mono- or tetra-nuclear species, is supported on MgO and is not when the support is the zeolite. The neighboring iridium sites in clusters are crucial for activation of both H{sub 2} and C{sub 2}H{sub 4} when the support is MgO but not when it is the zeolite, because the electron-withdrawing properties of the zeolite support enable even single site-isolated Ir atoms to bond to both C{sub 2}H{sub 4} and H{sub 2} and facilitate the catalysis.

  11. A comparison of commercial/industry and nuclear weapons safety concepts

    SciTech Connect

    Bennett, R.R.; Summers, D.A.

    1996-07-01

    In this paper the authors identify factors which influence the safety philosophy used in the US commercial/industrial sector and compare them against those factors which influence nuclear weapons safety. Commercial/industrial safety is guided by private and public safety standards. Generally, private safety standards tend to emphasize product reliability issues while public (i.e., government) safety standards tend to emphasize human factors issues. Safety in the nuclear weapons arena is driven by federal requirements and memoranda of understanding (MOUs) between the Departments of Defense and Energy. Safety is achieved through passive design features integrated into the nuclear weapon. Though the common strand between commercial/industrial and nuclear weapons safety is the minimization of risk posed to the general population (i.e., public safety), the authors found that each sector tends to employ a different safety approach to view and resolve high-consequence safety issues.

  12. Reagan's energy war: can deregulation and the Pentagon save the nuclear industry

    SciTech Connect

    Feeney, A.

    1981-11-01

    Mr. Feeney feels that Administration energy policies claiming to protect democracy and reduce government interference will transfer money and political control from the people to the energy corporations and the Pentagon. Critics deplore the hard-path approach of downgrading conservation and solar energy in favor of nuclear energy, which some see as setting the stage for a nuclear war in this decade. They see the plan to abolish DOE as providing an opportunity to bail out the nuclear industry, bury environmental and alternative energy research, and block regulations. Critics question why Reagan's devotion to the free market is not applied to the nuclear industry, although they disagree on the linkage with nuclear weapons of new fuel cycle proposals and the use of national security to solve the waste disposal problem by nationalizing and militarizing the fuel cycle. (DCK)

  13. A Lesson from the Nuclear Industry: Professionalism and Technology.

    ERIC Educational Resources Information Center

    Roth, Gene L.; Widen, W. C.

    1991-01-01

    Focuses on an innovative approach to instill professionalism in workers such as reactor operators and other nuclear power workers. It may be used by technology instructors to send a message to their students: regardless of the advanced state of technology, the human element provides the key to desirable outcomes. (Author/JOW)

  14. A Study of Reasons for Participation in Continuing Professional Education in the U.S. Nuclear Power Industry

    ERIC Educational Resources Information Center

    McCamey, Randy B.

    2003-01-01

    The need for workers in the U.S. nuclear power industry to continually update their knowledge, skills, and abilities is critical to the safe and reliable operation of the country's nuclear power facilities. To improve their skills, knowledge, and abilities, many professionals in the nuclear power industry participate in continuing professional…

  15. Nuclear reactor construction with bottom supported reactor vessel

    DOEpatents

    Sharbaugh, John E.

    1987-01-01

    An improved liquid metal nuclear reactor construction has a reactor core and a generally cylindrical reactor vessel for holding a large pool of low pressure liquid metal coolant and housing the core within the pool. The reactor vessel has an open top end, a closed flat bottom end wall and a continuous cylindrical closed side wall interconnecting the top end and bottom end wall. The reactor also has a generally cylindrical concrete containment structure surrounding the reactor vessel and being formed by a cylindrical side wall spaced outwardly from the reactor vessel side wall and a flat base mat spaced below the reactor vessel bottom end wall. A central support pedestal is anchored to the containment structure base mat and extends upwardly therefrom to the reactor vessel and upwardly therefrom to the reactor core so as to support the bottom end wall of the reactor vessel and the lower end of the reactor core in spaced apart relationship above the containment structure base mat. Also, an annular reinforced support structure is disposed in the reactor vessel on the bottom end wall thereof and extends about the lower end of the core so as to support the periphery thereof. In addition, an annular support ring having a plurality of inward radially extending linear members is disposed between the containment structure base mat and the bottom end of the reactor vessel wall and is connected to and supports the reactor vessel at its bottom end on the containment structure base mat so as to allow the reactor vessel to expand radially but substantially prevent any lateral motions that might be imposed by the occurrence of a seismic event. The reactor construction also includes a bed of insulating material in sand-like granular form, preferably being high density magnesium oxide particles, disposed between the containment structure base mat and the bottom end wall of the reactor vessel and uniformly supporting the reactor vessel at its bottom end wall on the containment

  16. An evolution of technologies and applications of gamma imagers in the nuclear cycle industry

    SciTech Connect

    Khalil, R. A.; Menaa, N.; De Toro, D.; Varet, T.

    2011-07-01

    The tracking of radiation contamination and distribution has become a high priority in the nuclear cycle industry in order to respect the ALARA principle which is a main challenge during decontamination and dismantling activities. To support this need, AREVA/CANBERRA and CEA LIST have been actively carrying out research and development on a gamma-radiation imager. In this paper we will present the new generation of gamma camera, called GAMPIX. This system is based on the Timepix chip, hybridized with a CdTe substrate. A coded mask could be used in order to increase the sensitivity of the camera. Moreover, due to the USB connection with a standard computer, this gamma camera is immediately operational and user-friendly. The final system is a very compact gamma camera (global weight is less than 1 kg without any shielding) which could be used as a hand-held device for radioprotection purposes. In this article, we present the main characteristics of this new generation of gamma camera and we expose experimental results obtained during in situ measurements. Even though we present preliminary results the final product is under industrialization phase to address various applications specifications. (authors)

  17. Applications of nuclear physics to interdisciplinary research and to industry

    NASA Astrophysics Data System (ADS)

    Schweitzer, Jeffrey

    2000-04-01

    Techniques that have been developed to understand nuclear structure can be used for interdisciplinary research and to determine useful properties. Both microscopic and macroscopic techniques can be used. The introduction discusses the diversity of fields that can benefit from applying nuclear physics techniques. Three current areas of research are used as illustrations. The use of gamma-ray spectroscopy following thermal neutron capture to better understand the formation and evolution of planetary bodies. Such measurements can be performed from orbit, on landers or on rovers, but each type of measurement puts different constraints on the instrument design. Nuclear resonant reaction analysis has recently been used to better understand the chemical kinetics in the curing of cement. Elemental concentrations of hydrogen have been measured with a spatial resolution of a few nanometers at the grain surface and about 20 nanometers at a depth of about two microns as a function of time during the reaction. Finally, x-ray techniques are being developed to provide an x-ray fluorescence instrument that can be used safely and reliably at a crime scene for investigative purposes. Unique problems of applying laboratory techniques to random, human-occupied locations and the requirements for providing a technically viable analysis that will be accepted by our legal system will be discussed.

  18. Analysis of Government Policies to Support Sustainable Domestic Defense Industries

    DTIC Science & Technology

    2015-06-01

    the defense industry , is costly. To obtain capital, a company needs access to financial markets . Unfortunately, high risks and unstable defense...i. Market Environment In the defense industry , government policy sometimes involves the preservation of certain companies to guarantee (excess...Globalization in defense technology and the industrial base affects the global arms market overall and raises concerns about security issues, including arms

  19. Technical Support Section Instrument Support Program for nuclear and nonnuclear facilities with safety requirements

    SciTech Connect

    Adkisson, B.P.; Allison, K.L.

    1995-01-01

    This document describes requirements, procedures, and supervisory responsibilities of the Oak Ridge National Laboratory (ORNL) Instrumentation and Controls (I&C) Division`s Technical Support Section (TSS) for instrument surveillance and maintenance in nonreactor nuclear facilities having identified Operational Safety Requirements (OSRs) or Limiting Conditions Document (LCDs). Implementation of requirements comply with the requirements of U.S. Department of Energy (DOE) Orders 5480.5, 5480.22, and 5481.1B; Martin Marietta Energy Systems, Inc. (Energy Systems), Policy Procedure ESS-FS-201; and ORNL SPP X-ESH-15. OSRs and LCDs constitute an agreement or contract between DOE and the facility operating management regarding the safe operation of the facility. One basic difference between OSRs and LCDs is that violation of an OSR is considered a Category II occurrence, whereas violation of an LCD requirement is considered a Category III occurrence (see Energy Systems Standard ESS-OP-301 and ORNL SPP X-GP-13). OSRs are required for high- and moderate-hazard nuclear facilities, whereas the less-rigorous LCDs are required for low-hazard nuclear facilities and selected {open_quotes}generally accepted{close_quotes} operations. Hazard classifications are determined through a hazard screening process, which each division conducts for its facilities.

  20. A survey of doses to worker groups in the nuclear industry

    SciTech Connect

    Khan, T.A.; Baum, J.W.

    1991-01-01

    The the US National Council on Radiation Protection and Measurements (NCRP) has suggested ...as guidance for radiation programs that cumulative exposure not exceed the age of the individual in years {times} 10 mSv (years {times} 1 rem).'' The International Commission on Radiological Protection (ICRP) has recommended a dose limit of 10 rem averaged over 5 years. With these developments in mind, the US Nuclear Regulatory Commission (NRC) requested the ALARA Center of the Brookhaven National Laboratory to undertake two parallel studies. One study, which is still ongoing, is to examine the impact of the newly recommended dose limits on the nuclear industry as a whole; the other study was intended to assist in this larger project by looking more closely at the nuclear power industry. Preliminary data had indicated that the critical industry as far as the impact of new regulatory limits were concerned would be the nuclear power industry, because, it was conjectured, there existed a core of highly skilled workers in some groups which routinely get higher than average exposures. The objectives of the second study were to get a better understanding of the situation vis {grave a} vis the nuclear power industry, by identifying the high-dose worker groups, quantifying the annual and lifetime doses to these groups to see the extent of the problem if there was one, and finally to determine if there were any dose-reduction techniques which were particularly suited to reducing doses to these groups. In this presentation we describe some of the things learned during our work on the two projects. For more detailed information on the project on dose-reduction techniques for high-dose worker groups in the nuclear power industry, see NUREG/CR-5139. An industry/advisory committee has been set up which is in the process of evaluating the data from the larger project on the impact of new dose limits and will shortly produce its report. 7 refs., 5 figs., 6 tabs.

  1. Autonomic Intelligent Cyber Sensor to Support Industrial Control Network Awareness

    DOE PAGES

    Vollmer, Todd; Manic, Milos; Linda, Ondrej

    2013-06-01

    The proliferation of digital devices in a networked industrial ecosystem, along with an exponential growth in complexity and scope, has resulted in elevated security concerns and management complexity issues. This paper describes a novel architecture utilizing concepts of Autonomic computing and a SOAP based IF-MAP external communication layer to create a network security sensor. This approach simplifies integration of legacy software and supports a secure, scalable, self-managed framework. The contribution of this paper is two-fold: 1) A flexible two level communication layer based on Autonomic computing and Service Oriented Architecture is detailed and 2) Three complementary modules that dynamically reconfiguremore » in response to a changing environment are presented. One module utilizes clustering and fuzzy logic to monitor traffic for abnormal behavior. Another module passively monitors network traffic and deploys deceptive virtual network hosts. These components of the sensor system were implemented in C++ and PERL and utilize a common internal D-Bus communication mechanism. A proof of concept prototype was deployed on a mixed-use test network showing the possible real world applicability. In testing, 45 of the 46 network attached devices were recognized and 10 of the 12 emulated devices were created with specific Operating System and port configurations. Additionally the anomaly detection algorithm achieved a 99.9% recognition rate. All output from the modules were correctly distributed using the common communication structure.« less

  2. Autonomic Intelligent Cyber Sensor to Support Industrial Control Network Awareness

    SciTech Connect

    Vollmer, Todd; Manic, Milos; Linda, Ondrej

    2013-06-01

    The proliferation of digital devices in a networked industrial ecosystem, along with an exponential growth in complexity and scope, has resulted in elevated security concerns and management complexity issues. This paper describes a novel architecture utilizing concepts of Autonomic computing and a SOAP based IF-MAP external communication layer to create a network security sensor. This approach simplifies integration of legacy software and supports a secure, scalable, self-managed framework. The contribution of this paper is two-fold: 1) A flexible two level communication layer based on Autonomic computing and Service Oriented Architecture is detailed and 2) Three complementary modules that dynamically reconfigure in response to a changing environment are presented. One module utilizes clustering and fuzzy logic to monitor traffic for abnormal behavior. Another module passively monitors network traffic and deploys deceptive virtual network hosts. These components of the sensor system were implemented in C++ and PERL and utilize a common internal D-Bus communication mechanism. A proof of concept prototype was deployed on a mixed-use test network showing the possible real world applicability. In testing, 45 of the 46 network attached devices were recognized and 10 of the 12 emulated devices were created with specific Operating System and port configurations. Additionally the anomaly detection algorithm achieved a 99.9% recognition rate. All output from the modules were correctly distributed using the common communication structure.

  3. The Use of Thorium within the Nuclear Power Industry - 13472

    SciTech Connect

    Miller, Keith

    2013-07-01

    Thorium is 3 to 4 times more abundant than uranium and is widely distributed in nature as an easily exploitable resource in many countries. Unlike natural uranium, which contains ∼0.7% fissile {sup 235}U isotope, natural thorium does not contain any fissile material and is made up of the fertile {sup 232}Th isotope only. Therefore thorium and thorium-based fuel as metal, oxide or carbide, has been utilized in combination with fissile {sup 235}U or {sup 239}Pu in nuclear research and power reactors for conversion to fissile {sup 233}U, thereby enlarging fissile material resources. During the pioneering years of nuclear energy, from the mid 1950's to mid 1970's, there was considerable interest worldwide to develop thorium fuels and fuel cycles in order to supplement uranium reserves. Thorium fuels and fuel cycles are particularly relevant to countries having large thorium deposits but very limited uranium reserves for their long term nuclear power programme. The feasibility of thorium utilization in high temperature gas cooled reactors (HTGR), light water reactors (LWR), pressurized heavy water reactors (PHWRs), liquid metal cooled fast breeder reactors (LMFBR) and molten salt breeder reactors (MSBR) were demonstrated. The initial enthusiasm for thorium fuels and fuel cycles was not sustained among the developing countries later, due to new discovery of uranium deposits and their improved availability. However, in recent times, the need for proliferation-resistance, longer fuel cycles, higher burnup, and improved waste form characteristics, reduction of plutonium inventories and in situ use of bred-in fissile material has led to renewed interest in thorium-based fuels and fuel cycles. (authors)

  4. Drug and alcohol abuse: the bases for employee assistance programs in the nuclear-utility industry

    SciTech Connect

    Radford, L.R.; Rankin, W.L.; Barnes, V.; McGuire, M.V.; Hope, A.M.

    1983-07-01

    This report describes the nature, prevalence, and trends of drug and alcohol abuse among members of the US adult population and among personnel in non-nuclear industries. Analogous data specific to the nuclear utility industry are not available, so these data were gathered in order to provide a basis for regulatory planning. The nature, prevalence, and trend inforamtion was gathered using a computerized literature, telephone discussions with experts, and interviews with employee assistance program representatives from the Seattle area. This report also evaluates the possible impacts that drugs and alcohol might have on nuclear-related job performance, based on currently available nuclear utility job descriptions and on the scientific literature regarding the impairing effects of drugs and alcohol on human performance. Employee assistance programs, which can be used to minimize or eliminate job performance decrements resulting from drug or alcohol abuse, are also discussed.

  5. Multidisciplinary Graduate Curriculum in Support of the Biobased Products Industry

    SciTech Connect

    John R. Dorgan

    2005-09-30

    The project had a dominant education component. The project involved revising curriculum to educate traditional engineering students in the emerging field of industrial biotechnology. New classes were developed and offered. As a result, the curriculum of the Colorado School of Mines was expanded to include new content. Roughly 100 undergraduates and about 10 graduate students each year benefit from this curricular expansion. The research associated with this project consisted of developing new materials and energy sources from renewable resources. Several significant advances were made, most importantly the heat distortion temperature of polylactide (PLA) was increased through the addition of cellulosic nanowhiskers. The resulting ecobionanocomposites have superior properties which enable the use of renewable resource based plastics in a variety of new applications. Significant amounts of petroleum are thereby saved and considerable environmental benefits also result. The original project objectives had to be modified as a result of DOE funding cuts, the Biomass Program did not receive adequate funding to fully fund its selected projects. Nonetheless, effectiveness and economic feasibility of the project proved excellent. The educational activities are continuing in a sustainable fashion, now being supported by tuition revenues and the normal budgeting of the University. PI Dorgan taught one of the newly developed classes will in the Fall 2006, after the close of the DOE grant, and again repeatedly into the future. Now established, the curriculum in biobased products and energy will grow and evolve through regular teaching and revisions. On the research side, the new plastic materials appear economically feasible and a new collaboration between the PI’s group and Sealed Air, a major food-packaging manufacturer, has been established to bring the new green plastics to market. Public benefits of the project are noteworthy in many respects. These include the

  6. Multidisciplinary Graduate Curriculum in Support of the Biobased Products Industry

    SciTech Connect

    John R. Dorgan

    2005-07-31

    The project had a dominant education component. The project involved revising curriculum to educate traditional engineering students in the emerging field of industrial biotechnology. New classes were developed and offered. As a result, the curriculum of the Colorado School of Mines was expanded to include new content. Roughly 100 undergraduates and about 10 graduate students each year benefit from this curricular expansion. The research associated with this project consisted of developing new materials and energy sources from renewable resources. Several significant advances were made, most importantly the heat distortion temperature of polylactide (PLA) was increased through the addition of cellulosic nanowhiskers. The resulting ecobionanocomposites have superior properties which enable the use of renewable resource based plastics in a variety of new applications. Significant amounts of petroleum are thereby saved and considerable environmental benefits also result. Effectiveness and economic feasibility of the project proved excellent. The educational activities are continuing in a sustainable fashion, now being supported by tuition revenues and the normal budgeting of the University. The PI will be teaching one of the newly developed classes will next Fall (Fall 2006), after the close of the DOE grant, and again repeatedly into the future. Now established, the curriculum in biobased products and energy will grow and evolve through regular teaching and revision. On the research side, the new plastic materials appear economically feasible and a new collaboration between the PI’s group and Sealed Air, a major food-packaging manufacturer, has been established to bring the new green plastics to market. Public benefits of the project are noteworthy in many respects. These include the development of a better educated workforce and citizenry capable of providing technological innovation as a means of growing the economy and providing jobs. In particular, the

  7. Tissue specificity in the nuclear envelope supports its functional complexity.

    PubMed

    de Las Heras, Jose I; Meinke, Peter; Batrakou, Dzmitry G; Srsen, Vlastimil; Zuleger, Nikolaj; Kerr, Alastair Rw; Schirmer, Eric C

    2013-01-01

    Nuclear envelope links to inherited disease gave the conundrum of how mutations in near-ubiquitous proteins can yield many distinct pathologies, each focused in different tissues. One conundrum-resolving hypothesis is that tissue-specific partner proteins mediate these pathologies. Such partner proteins may have now been identified with recent proteome studies determining nuclear envelope composition in different tissues. These studies revealed that the majority of the total nuclear envelope proteins are tissue restricted in their expression. Moreover, functions have been found for a number these tissue-restricted nuclear envelope proteins that fit with mechanisms proposed to explain how the nuclear envelope could mediate disease, including defects in mechanical stability, cell cycle regulation, signaling, genome organization, gene expression, nucleocytoplasmic transport, and differentiation. The wide range of functions to which these proteins contribute is consistent with not only their involvement in tissue-specific nuclear envelope disease pathologies, but also tissue evolution.

  8. Tissue specificity in the nuclear envelope supports its functional complexity

    PubMed Central

    de las Heras, Jose I; Meinke, Peter; Batrakou, Dzmitry G; Srsen, Vlastimil; Zuleger, Nikolaj; Kerr, Alastair RW; Schirmer, Eric C

    2013-01-01

    Nuclear envelope links to inherited disease gave the conundrum of how mutations in near-ubiquitous proteins can yield many distinct pathologies, each focused in different tissues. One conundrum-resolving hypothesis is that tissue-specific partner proteins mediate these pathologies. Such partner proteins may have now been identified with recent proteome studies determining nuclear envelope composition in different tissues. These studies revealed that the majority of the total nuclear envelope proteins are tissue restricted in their expression. Moreover, functions have been found for a number these tissue-restricted nuclear envelope proteins that fit with mechanisms proposed to explain how the nuclear envelope could mediate disease, including defects in mechanical stability, cell cycle regulation, signaling, genome organization, gene expression, nucleocytoplasmic transport, and differentiation. The wide range of functions to which these proteins contribute is consistent with not only their involvement in tissue-specific nuclear envelope disease pathologies, but also tissue evolution. PMID:24213376

  9. Methods and practices used in incident analysis in the Finnish nuclear power industry.

    PubMed

    Suksi, Seija

    2004-07-26

    Finnish nuclear power plant operators Teollisuuden Voima Oy (TVO) and Fortum Power and Heat Oy (Fortum) was carried out by the Technical Research Centre (VTT) on request of STUK at the end of 1990s. The study aimed at providing a broad overview and suggestions for improvement of the whole organisational framework to support event investigation practices at the regulatory body and at the utilities. The main objective of the research was to evaluate the adequacy and reliability of event investigation analysis methods and practices in the Finnish nuclear power industry and based on the results to further develop them. The results and suggestions of the research are reviewed in the paper and the corrective actions implemented in event investigation and operating experience procedures both at STUK and at utilities are discussed as well. STUK has developed its own procedure for the risk-informed analysis of nuclear power plant events. The PSA based event analysis method is used to assess the safety significance and importance measures associated with the unavailability of components and systems subject to Technical Specifications. The insights from recently performed PSA based analyses are also briefly discussed in the paper.

  10. Fitness for duty in the nuclear power industry

    SciTech Connect

    Durbin, N.; Moore, C.; Grant, T.; Fleming, T.; Hunt, P.; Martin, R.; Murphy, S.; Hauth, J.; Wilson, R.; Bittner, A.; Bramwell, A.; Macaulay, J.; Olson, J.; Terrill, E.; Toquam, J. )

    1991-09-01

    This report presents an overview of the NRC licensees' implementation of the FFD program during the first full year of the program's operation and provides new information on a variety of FFD technical issues. The purpose of this document is to contribute to appropriate changes to the rule, to the inspection process, and to other NRC activities. It describes the characteristics of licensee programs, discusses the results of NRC inspections, updates technical information covered in previous reports, and identifies lessons learned during the first year. Overall, the experience of the first full year of licensees' FFD program operations indicates that licensees have functioning fitness for duty programs devoted to the NRC rule's performance objectives of achieving drug-free workplaces in which nuclear power plant personnel are not impaired as they perform their duties. 96 refs., 14 tabs.

  11. The Healthy Worker Effect and Nuclear Industry Workers

    PubMed Central

    Fornalski, Krzysztof W.; Dobrzyński, Ludwik

    2010-01-01

    The linear no-threshold (LNT) dose-effect relationship has been consistently used by most radiation epidemiologists to estimate cancer mortality risk. The large scattering of data by International Agency for Research on Cancer, IARC (Vrijheid et al. 2007; Therry-Chef et al. 2007; Cardis et al. 2007), interpreted in accordance with LNT, has been previously demonstrated (Fornalski and Dobrzyński 2009). Using conventional and Bayesian methods the present paper demonstrates that the standard mortality ratios (SMRs), lower in the IARC cohort of exposed nuclear workers than in the non exposed group, should be considered as a hormetic effect, rather than a healthy worker effect (HWE) as claimed by the IARC group. PMID:20585442

  12. REVIEW OF INDUSTRIES AND GOVERNMENT AGENCIES FOR TECHNOLOGIES APPLICABLE TO DEACTIVATION AND DECOMMISSIONING OF NUCLEAR WEAPONS FACILITIES

    SciTech Connect

    Reilkoff, T. E.; Hetland, M. D.; O'Leary, E. M.

    2002-02-25

    The Deactivation and Decommissioning Focus Area's (DDFA's) mission is to develop, demonstrate, and deploy improved deactivation and decommissioning (D&D) technologies. This mission requires that emphasis be continually placed on identifying technologies currently employed or under development in other nuclear as well as nonnuclear industries and government agencies. In support of DDFA efforts to clean up the U.S. Department of Energy's (DOE's) radiologically contaminated surplus facilities using technologies that improve worker safety, reduce costs, and accelerate cleanup schedules, a study was conducted to identify innovative technologies developed for use in nonnuclear arenas that are appropriate for D&D applications.

  13. Supporting rural wood industry through timber utilization research. Research paper

    SciTech Connect

    Skog, K.

    1991-10-01

    The report evaluates the potential impact of USDA Forest Service wood utilization and wood energy research on rural employment and income. Recent projections suggest employment will decrease in many forest products industries, such as softwood sawmilling, but will eventually increase in softwood plywood and reconstituated panel mills. Forest products industries expected to provide wages exceeding the average manufacturing production wage include logging, softwood sawmills, millwork, softwood plywood--veneer, structural wood members, particle-board, wood partitions, pulp mills, paper mills, and paperboard mills. Industries expected to pay 90 percent of the average manufacturing production wage include wood kitchen cabinets, mobile homes, prefabricated wood buildings, and wood preservatives.

  14. Rapid Radiochemical Analyses in Support of Fukushima Nuclear Accident - 13196

    SciTech Connect

    Maxwell, Sherrod L.; Culligan, Brian K.; Hutchison, Jay B.

    2013-07-01

    discussed. Air filter samples were reported within twenty-four (24) hours of receipt using rapid techniques published previously. [11] The rapid reporting of high quality analytical data arranged through the U.S. Department of Energy Consequence Management Home Team was critical to allow the government of Japan to readily evaluate radiological impacts from the nuclear reactor incident to both personnel and the environment. SRNL employed unique rapid methods capability for radionuclides to support Japan that can also be applied to environmental, bioassay and waste management samples. New rapid radiochemical techniques for radionuclides in soil and other environmental matrices as well as some of the unique challenges associated with this work will be presented that can be used for application to environmental monitoring, environmental remediation, decommissioning and decontamination activities. (authors)

  15. RAPID RADIOCHEMICAL ANALYSES IN SUPPORT OF FUKUSHIMA NUCLEAR ACCIDENT

    SciTech Connect

    Maxwell, S.

    2012-11-07

    reported within twenty-four (24) hours of receipt using rapid techniques published previously. The rapid reporting of high quality analytical data arranged through the U.S. Department of Energy Consequence Management Home Team was critical to allow the government of Japan to readily evaluate radiological impacts from the nuclear reactor incident to both personnel and the environment. SRNL employed unique rapid methods capability for radionuclides to support Japan that can also be applied to environmental, bioassay and waste management samples. New rapid radiochemical techniques for radionuclides in soil and other environmental matrices as well as some of the unique challenges associated with this work will be presented that can be used for application to environmental monitoring, environmental remediation, decommissioning and decontamination activities.

  16. A survey of fatigue monitoring in the nuclear power industry

    SciTech Connect

    Ware, A.G.

    1991-12-31

    The original design of nuclear power plants addressed fatigue concerns by including calculations of projected fatigue usage for specific components; the calculations were based on estimates of the number and severity of expected transients over the 40-year design life of the plants. In some cases, the transients occurring in the plants are not as severe as was anticipated in the original design analyses, while in other cases events have occurred that were not anticipated in the design basis documents. Field failures caused by fatigue have identified some of those cases. In response, several organizations in the United States and overseas have developed fatigue monitoring programs to more accurately estimate the fatigue usage. One basic approach consists of reconstructing the fatigue usage to date based on the transients recorded in the operating history instead of those projected in the design documents. Another approach includes monitoring the plant instrumentation to determine actual values for parameters such as temperature and pressure and using the measured values in the fatigue usage calculations instead of the values projected in the design documents. The use of existing plant instrumentation to measure temperature, pressure, flow rate, etc., along with the incorporation of conservative assumptions, had generally proven adequate for estimating fatigue usage; however, in some cases additional instrumentation installed for local monitoring can provide a more accurate estimate, especially where thermal stratification is known to occur. Fatigue monitoring can aid in identifying fatigue concerns not anticipated in the original design and for reducing the excessive conservatism in some of the original design calculations so that the fatigue lives of these components can be justified as they age. Fatigue monitoring can also assist efforts to reduce ongoing fatigue usage through design modifications and operating procedure changes.

  17. A survey of fatigue monitoring in the nuclear power industry

    SciTech Connect

    Ware, A.G.

    1991-01-01

    The original design of nuclear power plants addressed fatigue concerns by including calculations of projected fatigue usage for specific components; the calculations were based on estimates of the number and severity of expected transients over the 40-year design life of the plants. In some cases, the transients occurring in the plants are not as severe as was anticipated in the original design analyses, while in other cases events have occurred that were not anticipated in the design basis documents. Field failures caused by fatigue have identified some of those cases. In response, several organizations in the United States and overseas have developed fatigue monitoring programs to more accurately estimate the fatigue usage. One basic approach consists of reconstructing the fatigue usage to date based on the transients recorded in the operating history instead of those projected in the design documents. Another approach includes monitoring the plant instrumentation to determine actual values for parameters such as temperature and pressure and using the measured values in the fatigue usage calculations instead of the values projected in the design documents. The use of existing plant instrumentation to measure temperature, pressure, flow rate, etc., along with the incorporation of conservative assumptions, had generally proven adequate for estimating fatigue usage; however, in some cases additional instrumentation installed for local monitoring can provide a more accurate estimate, especially where thermal stratification is known to occur. Fatigue monitoring can aid in identifying fatigue concerns not anticipated in the original design and for reducing the excessive conservatism in some of the original design calculations so that the fatigue lives of these components can be justified as they age. Fatigue monitoring can also assist efforts to reduce ongoing fatigue usage through design modifications and operating procedure changes.

  18. Fuel supply of nuclear power industry with the introduction of fast reactors

    NASA Astrophysics Data System (ADS)

    Muraviev, E. V.

    2014-12-01

    The results of studies conducted for the validation of the updated development strategy for nuclear power industry in Russia in the 21st century are presented. Scenarios with different options for the reprocessing of spent fuel of thermal reactors and large-scale growth of nuclear power industry based on fast reactors of inherent safety with a breeding ratio of ˜1 in a closed nuclear fuel cycle are considered. The possibility of enhanced fuel breeding in fast reactors is also taken into account in the analysis. The potential to establish a large-scale nuclear power industry that covers 100% of the increase in electric power requirements in Russia is demonstrated. This power industry may be built by the end of the century through the introduction of fast reactors (replacing thermal ones) with a gross uranium consumption of up to ˜1 million t and the termination of uranium mining even if the reprocessing of spent fuel of thermal reactors is stopped or suffers a long-term delay.

  19. Economical Mars Exploration Supported by a Nuclear Thermal Rocket

    NASA Astrophysics Data System (ADS)

    Howe, S. D.; O'Brien, R. C.

    2012-06-01

    A nuclear thermal rocket (NTR) developed for human Mars missions could act as a "mother ship" and carry multiple unmanned platforms to Mars for independent deployment. Use of the NTR could increase the science per dollar for each Earth launch.

  20. Reuse of nuclear byproducts, NaF and HF in metal glass industries

    SciTech Connect

    Park, J.W.; Lee, H.W.; Yoo, S.H.; Moon, H.S.; Cho, N.C.

    1997-02-01

    A study has been performed to evaluate the radiological safety and feasibility associated with reuse of NaF(Sodium Fluoride) and HF(Hydrofluoric Acid) which are generated as byproducts from the nuclear fuel fabrication process. The investigation of oversea`s experience reveals that the byproduct materials are most often used in the metal and glass industries. For the radiological safety evaluation, the uranium radioactivities in the byproduct materials were examined and shown to be less than radioactivities in natural materials. The radiation doses to plant personnel and the general public were assessed to be very small and could be ignored. The Korea nuclear regulatory body permits the reuse of NaF in the metal industry on the basis of associated radioactivity being {open_quote}below regulatory concern{close_quote}. HF is now under review for reuse acceptability in the steel and glass industries.

  1. Industry Support of Medical Research: Important Opportunity or Treacherous Pitfall?

    PubMed

    Tierney, William M; Meslin, Eric M; Kroenke, Kurt

    2016-02-01

    Pharmaceutical and device manufacturers fund more than half of the medical research in the U.S. Research funding by for-profit companies has increased over the past 20 years, while federal funding has declined. Research funding from for-profit medical companies is seen as tainted by many academicians because of potential biases and prior misbehavior by both investigators and companies. Yet NIH is encouraging partnerships between the public and private sectors to enhance scientific discovery. There are instances, such as methods for improving drug adherence and post-marketing drug surveillance, where the interests of academician researchers and industry could be aligned. We provide examples of ethically performed industry-funded research and a set of principles and benchmarks for ethically credible academic-industry partnerships that could allow academic researchers, for-profit companies, and the public to benefit.

  2. Nukes II: the nuclear power industry wants another chance. This time, it promises to do things right

    SciTech Connect

    De Young, H.G.

    1985-03-01

    Anticipating a comback for nuclear power, the nuclear industry points to the need for reliable supplies of electricity to provide over 35% of US energy requirements. The industry faces both technical and institutional problems, in contrast to the mature industry of other countries, and promises to improve its performance in safety design and efficiency. Pointing to design advances, robotics, computerized simulation and other techniques, the industry feels that regulation will be more reasonable and costs will be reduced. Economic solutions include building smaller plants and using modular construction. The biggest uncertainty, however, is whether the public will buy either the need for additional capacity or nuclear power to fill that need.

  3. Instructional Support System--Occupational Education. Building Industries Occupations.

    ERIC Educational Resources Information Center

    Abramson, Theodore; And Others

    The modules which make up the bulk of this report are the result of a two-week workshop at which thirteen building industries occupations teachers worked toward the development of a student outcome oriented curriculum. These modules are divided into the following occupational units: (1) carpentry (containing hand tools; portable power tools;…

  4. Improving healthcare quality through organisational peer-to-peer assessment: lessons from the nuclear power industry

    PubMed Central

    Pronovost, Peter J; Hudson, Daniel W

    2012-01-01

    Healthcare has made great efforts to reduce preventable patient harm, from externally driven regulations to internally driven professionalism. Regulation has driven the majority of efforts to date, and has a necessary place in establishing accountability and minimum standards. Yet they need to be coupled with internally driven efforts. Among professional groups, internally-driven efforts that function as communities of learning and change social norms are highly effective tools to improve performance, yet these approaches are underdeveloped in healthcare. Healthcare can learn much from the nuclear power industry. The nuclear power industry formed the Institute of Nuclear Power Operators following the Three Mile Island accident to improve safety. That organization established a peer-to-peer assessment program to cross-share best practices, safety hazards, problems and actions that improved safety and operational performance. This commentary explores how a similar program could be expanded into healthcare. Healthcare needs a structured, clinician-led, industry-wide process to openly review, identify and mitigate hazards, and share best practices that ultimately improve patient safety. A healthcare version of the nuclear power program could supplement regulatory and other strategies currently used to improve quality and patient safety. PMID:22562877

  5. Improving healthcare quality through organisational peer-to-peer assessment: lessons from the nuclear power industry.

    PubMed

    Pronovost, Peter J; Hudson, Daniel W

    2012-10-01

    Healthcare has made great efforts to reduce preventable patient harm, from externally driven regulations to internally driven professionalism. Regulation has driven the majority of efforts to date, and has a necessary place in establishing accountability and minimum standards. Yet they need to be coupled with internally driven efforts. Among professional groups, internally-driven efforts that function as communities of learning and change social norms are highly effective tools to improve performance, yet these approaches are underdeveloped in healthcare. Healthcare can learn much from the nuclear power industry. The nuclear power industry formed the Institute of Nuclear Power Operators following the Three Mile Island accident to improve safety. That organization established a peer-to-peer assessment program to cross-share best practices, safety hazards, problems and actions that improved safety and operational performance. This commentary explores how a similar program could be expanded into healthcare. Healthcare needs a structured, clinician-led, industry-wide process to openly review, identify and mitigate hazards, and share best practices that ultimately improve patient safety. A healthcare version of the nuclear power program could supplement regulatory and other strategies currently used to improve quality and patient safety.

  6. Support of the Iraq nuclear facility dismantlement and disposal program

    SciTech Connect

    Coates, Roger; Cochran, John; Danneels, Jeff; Chesser, Ronald; Phillips, Carlton; Rogers, Brenda

    2007-07-01

    Available in abstract form only. Full text of publication follows: Iraq's former nuclear facilities contain large quantities of radioactive materials and radioactive waste. The Iraq Nuclear Facility Dismantlement and Disposal Program (the Iraq NDs Program) is a new program to decontaminate and permanently dispose of radioactive wastes in Iraq. The NDs Program is led by the Government of Iraq, under International Atomic Energy Agency (IAEA) auspices, with guidance and assistance from a number of countries. The U.S. participants include Texas Tech University and Sandia National Laboratories. A number of activities are ongoing under the broad umbrella of the Iraq NDs Program: drafting a new nuclear law that will provide the legal basis for the cleanup and disposal activities; assembly and analysis of existing data; characterization of soil contamination; bringing Iraqi scientists to the world's largest symposium on radioactive waste management; touring U.S. government and private sector operating radwaste disposal facilities in the U.S., and hosting a planning workshop on the characterization and cleanup of the Al-Tuwaitha Nuclear Facility. (authors)

  7. The tethering of chromatin to the nuclear envelope supports nuclear mechanics

    PubMed Central

    Schreiner, Sarah M.; Koo, Peter K.; Zhao, Yao; Mochrie, Simon G. J.; King, Megan C.

    2015-01-01

    The nuclear lamina is thought to be the primary mechanical defence of the nucleus. However, the lamina is integrated within a network of lipids, proteins and chromatin; the interdependence of this network poses a challenge to defining the individual mechanical contributions of these components. Here, we isolate the role of chromatin in nuclear mechanics by using a system lacking lamins. Using novel imaging analyses, we observe that untethering chromatin from the inner nuclear membrane results in highly deformable nuclei in vivo, particularly in response to cytoskeletal forces. Using optical tweezers, we find that isolated nuclei lacking inner nuclear membrane tethers are less stiff than wild-type nuclei and exhibit increased chromatin flow, particularly in frequency ranges that recapitulate the kinetics of cytoskeletal dynamics. We suggest that modulating chromatin flow can define both transient and long-lived changes in nuclear shape that are biologically important and may be altered in disease. PMID:26074052

  8. Laser-fluorescence monitoring of {sup 129}I in industrial reprocessing of nuclear fuel

    SciTech Connect

    Kireev, S.V.; Protsenko, E.D.; Shnyrev, L.S.; Veselov, V.K.; Isupov, V.K.

    1995-01-01

    A laser-fluorescence system is developed that uses a He-Ne (633 nm) laser for continuous monitoring of {sup 129}I during HNO{sub 3} dissolution of irradiated nuclear fuel. Tests at Khlopin Radium Institute indicated that the sensitivity of the {sup 129}I detection (at worst 8{center_dot}10{sup {minus}5} g/m{sup 3}) ensures reliable monitoring of this isotope both directly in the working gas during industrial reprocessing of irradiated nuclear fuel and following gas-purification systems at radiochemical plants.

  9. USCEA/NIST measurement assurance programs for the radiopharmaceutical and nuclear power industries

    SciTech Connect

    Golas, D.B.

    1993-12-31

    In cooperation with the U.S. Council for Energy Awareness (USCEA), the National Institute of Standards and Technology (NIST) supervises and administers two measurement assurance programs for radioactivity measurement traceability. One, in existence since the mid 1970s, provides traceability to suppliers of radiochemicals and radiopharmaceuticals, dose calibrators, and nuclear pharmacy services. The second program, begun in 1987, provides traceability to the nuclear power industry for utilities, source suppliers, and service laboratories. Each program is described, and the results of measurements of samples of known, but undisclosed activity, prepared at NIST and measured by the participants are presented.

  10. Precursor nuclearity effects in supported vanadium oxides prepared by organometallic grafting.

    SciTech Connect

    Wegener, S. L.; Kim, H.; Marks, T. J.; Stair, P. C.

    2011-01-01

    Despite widespread importance in catalysis, the active and selective sites of supported vanadium oxide (VO{sub x}) catalysts are not well understood. Such catalysts are of great current interest because of their industrial significance and potential for selective oxidation processes. However, the fact that the nature of the active and selective sites is ambiguous hinders molecular level understanding of catalytic reactions and the development of new catalysts. Furthermore, complete structural elucidation requires isolation and characterization of specific vanadium oxide surface species, the preparation of which presents a significant synthetic challenge. In this study, we utilize the structural uniformity inherent in organometallic precursors for the preparation of supported vanadium oxide catalysts. The resulting catalysts are characterized by UV-visible diffuse reflectance spectroscopy (UV-vis DRS), X-ray absorption spectroscopy (XAS), UV-Raman spectroscopy, and H{sub 2}-temperature programmed reduction (H{sub 2}-TPR). Significant structural and reactivity differences are observed in catalysts prepared from different organometallic precursors, indicating that the chemical nature of surface vanadia can be influenced by the nuclearity of the precursor used for grafting.

  11. Means for supporting fuel elements in a nuclear reactor

    DOEpatents

    Andrews, Harry N.; Keller, Herbert W.

    1980-01-01

    A grid structure for a nuclear reactor fuel assembly comprising a plurality of connecting members forming at least one longitudinally extending opening peripheral and inner fuel element openings through each of which openings at least one nuclear fuel element extends, said connecting members forming wall means surrounding said each peripheral and inner fuel element opening, a pair of rigid projections longitudinally spaced from one another extending from a portion of said wall means into said each peripheral and inner opening for rigidly engaging said each fuel element, respectively, yet permit individual longitudinal slippage thereof, and resilient means formed integrally on and from said wall means and positioned in said each peripheral and inner opening in opposed relationship with said projections and located to engage said fuel element to bias the latter into engagement with said rigid projections, respectively

  12. PSF Analysis Support System for Nuclear Power Plants

    SciTech Connect

    Satoko Sakajo; Takashi Nakagawa; Naotaka Terashita

    2002-07-01

    Research during recent years has revealed that human errors tend to reflect the quality of performance shaping factors (PSFs). Therefore, from the viewpoint of reducing human error, PSFs, which include error-likely equipment design, written procedures, and other factors, must be analyzed and improved. This paper provides methodologies to identify and qualify the potential PSFs included in tasks at a nuclear power plant (NPP). The methodologies were applied to actual plants. (authors)

  13. 59 FR- Noncompetitive Award of Financial Assistance to Support Nuclear Applications of Robotics

    Federal Register 2010, 2011, 2012, 2013, 2014

    1994-05-18

    ... Noncompetitive Award of Financial Assistance to Support Nuclear Applications of Robotics agency: Department of... Nuclear Energy in 1986 for energy applications of robotics. DOE has previously renewed these awards...-integrated teams which are capable of completing the advanced robotics systems required. These teams would...

  14. Industrial hygiene support of underground operations at the Nevada Test Site

    SciTech Connect

    Porter, P.F.

    1992-07-23

    The Industrial Hygiene Section of the Health Protection Department provides industrial hygiene support of underground operations at the Nevada Test Site. This report describes support operations and summarizes the industrial hygiene data collected from July 31, 1989 through June 30, 1991. Air quality data were collected by means of personnel sampling by active and passive techniques using various kinds of industrial hygiene instrumentation and through localized and general area monitoring. The data collected were used to evaluate underground air quality and quantity requirements; evaluate worker exposures to a variety of air contaminants; determine the applicability and effectiveness of personal protective equipment.

  15. Industrial Base Analysis for Support Equipment. Phase 1.

    DTIC Science & Technology

    1986-10-01

    Continue on reverse if necessary and identify by block number) The ability of the aerospace industry to provide fieldable weapon systems depends to a large...systems; and establish a corporate memory within the Air Force and the Department of Defense. 1 , Building and demonstrating a prototype Gr/DSS are...Defense (DoD). 7 1.3 PRIE’ SCOPE Building and demonstrating a prototype Gr/DSS are crucial, but the thrust of Phase I of the project has been limited

  16. Handbook of software quality assurance techniques applicable to the nuclear industry

    SciTech Connect

    Bryant, J.L.; Wilburn, N.P.

    1987-08-01

    Pacific Northwest Laboratory is conducting a research project to recommend good engineering practices in the application of 10 CFR 50, Appendix B requirements to assure quality in the development and use of computer software for the design and operation of nuclear power plants for NRC and industry. This handbook defines the content of a software quality assurance program by enumerating the techniques applicable. Definitions, descriptions, and references where further information may be obtained are provided for each topic.

  17. The NUCLARR databank: Human reliability and hardware failure data for the nuclear power industry

    SciTech Connect

    Reece, W.J.

    1993-05-01

    Under the sponsorship of the US Nuclear Regulatory Commission (NRC), the Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) was developed to provide human reliability and hardware failure data to analysts in the nuclear power industry. This IBM-compatible databank is contained on a set of floppy diskettes which include data files and a menu-driven system for locating, reviewing, sorting, and retrieving the data. NUCLARR contains over 2500 individual data records, drawn from more, than 60 sources. The system is upgraded annually, to include additional human error and hardware component failure data and programming enhancements (i.e., increased user-friendliness). NUCLARR is available from the NRC through project staff at the INEL.

  18. Nautical Education for Offshore Extractive Industries. Support Operations & Seamanship.

    ERIC Educational Resources Information Center

    Hoffmann, G. L.

    This training manual is intended for persons who will be employed on supply vessels or towboats which support ocean-based oil extraction operations. The text deals with the basic skills of marine towing procedures, boat handling, deck maintenance, cargo operations, and rope and wire handling. Additional sections treat the proper attitude of a…

  19. (Technical and engineering support for the Office of Industrial Programs)

    SciTech Connect

    Not Available

    1991-01-01

    As of April 19, 1991, technical, operational and analytic support and assistance to the offices and divisions of the Office of Renewable Energy, under contract DE-AC01-86CE30844 was completed. The overall work effort, initiated February 20, 1986, was characterized by timely, comprehensive, high quality, professional responsiveness to a broad range of renewable energy program operational support requirements. These are no instances of failure to respond, nor unacceptable response, during the five-year period. The technology program areas covered are Solar Buildings Technology, Wind Energy Technology, Photovoltaic Energy Technology, Geothermal Energy Technology, Biofuels and Municipal Waste Technology, Solar Thermal Technology, Hydropower Energy Technology, Ocean Energy Technology, and Electric Energy Systems and Energy Storage. The analytical and managerial support provided to the office and staff of the Deputy Assistant Secretary for Renewable Energy enabled a comprehensive evaluation of program and policy alternatives, and the selection and execution of appropriate courses of action from amongst those alternatives. Largely through these means the Office has been able to maintain continuity and a meaningful program thrust through the vacillations of policies and budgets that it has experienced over that it has experienced over the past five years. Appended are summaries of support activities within each of the individual technology program areas, as well as a complete listing of all project deliverables and due-dates for each submittal under the contract.

  20. Overview of implementing a project control system in the nuclear utility industry

    SciTech Connect

    Cooprider, D.H. )

    1994-03-01

    During the late 1980s, a metamorphosis began at Florida Power and Light Company (FPL). A strategic step in nuclear engineering's efforts to become more cost effective began in January 1990. A project control department was formed. The initial mission was to provide support for nuclear engineering design activities associated with FPL's two twin-unit nuclear power generation facilities - Turkey Point and St. Lucie. Later, the goal expanded to include the division's materials management, nuclear licensing, and information management departments. The project control group was organized along the lines of the organizations served. Separate dedicated groups were established for each plant. Since most engineering activity was based at the Juno Beach headquarters, the project control staff also was based there.

  1. Industry support for molten carbonate fuel cell commercialization

    SciTech Connect

    Nimmons, J.T.

    1996-12-31

    The Alliance to Commercialize Carbonate Technology (ACCT) is a working alliance of utilities and industry, created to help bring molten carbonate fuel cell (MCFC) technology into commercial markets by the year 2000. Its principal focus is the IMHEX{reg_sign} MCFC power plant under development by the team of M-C Power Corporation, the Institute of Gas Technology, The Bechtel Corporation, and Stewart & Stevenson Services, Inc. (the {open_quotes}Development Team{close_quotes}), although many ACCT members are also interested in other fuel cell technologies. This paper will describe ACCT`s background, mission, approach and activities, as well as opportunities for those interested to join in ACCT`s ongoing work toward MCFC commercialization.

  2. Neutronic data in support of space nuclear propulsion

    SciTech Connect

    Mughabghab, S.; Schmidt, E.; Ludewig, H.

    1997-07-01

    The thermophysical properties of lithium hydride ({sup 7}LiH), particularly small density (0.775 gm/cc), high melting point (688 C) and relatively high hydrogen atomic number density makes it an attractive material for use as a neutron moderator and shield (for LiH) in space nuclear thermal propulsion. However, the unavailability of neutronic cross section data in the thermal energy range for {sup 7}LiH in the ENDF/B library necessitated the generation of the relevant data which is required in criticality studies and for the determination of temperature-dependent feedback coefficients in the moderator and fuel regions. Here, the scattering kernel data for {sup 7}LiH have been generated for the first time in the temperature range 50--1,000 K. This is based on a phonon distribution function derived from both experimental data and theoretical calculations. A detailed study of the variation of the moderator temperature coefficient {alpha}{sub m}(T) with temperature, T, is carried out for a typical space nuclear reactor of the particle bed type. It is established that the moderator temperature coefficient is proportional to T{sup {minus}1.65} where T is the moderator temperature in Kelvin units.

  3. TACOM LCMC Industrial Base Engineering Support - Commanders’ Conference

    DTIC Science & Technology

    2011-07-01

    SSTS), and plan corrective actions and material change efforts. UNCLASSIFIED 17 Data Sources PMR P-coded NSNs FEDLOG MATCAT & WSC to ID specific...vehicle families OSMIS PMR NSNs with order History LIW / Other Initial Unique NSN list DATA INTEGRITY CHECKS •Canceled NSNs identified•Replacement...List ILAP Maintenance Records Equip. Support Strategy PMR 60 plus data elements UNCLASSIFIED 18 Process Define Target System for Evaluation

  4. Supporting U.S. Response to the Japanese Nuclear Crisis | ORAU

    SciTech Connect

    Crapo, John; Jakubowski, Ted

    2012-03-08

    When an earthquake and tsunami hit off the coast of Japan on March 11, 2011, and triggered a nuclear crisis, the U.S. immediately offered support. Among those tapped to assist was ORAU's National Security and Emergency Management team, which provided NNSA with technical and analytical nuclear incident support. Within 48 hours of the earthquake, ORAU emergency management experts accompanied the DOE Office of Emergency Response in deploying to Japan to support the U.S. Air Force Base in Yokota and the U.S. Embassy. A separate team from ORAU supported the NNSA Nuclear Incident Team, which served as the point of coordination for all support activities both in Japan and in the U.S.

  5. Supporting U.S. Response to the Japanese Nuclear Crisis | ORAU

    ScienceCinema

    Crapo, John; Jakubowski, Ted

    2016-07-12

    When an earthquake and tsunami hit off the coast of Japan on March 11, 2011, and triggered a nuclear crisis, the U.S. immediately offered support. Among those tapped to assist was ORAU's National Security and Emergency Management team, which provided NNSA with technical and analytical nuclear incident support. Within 48 hours of the earthquake, ORAU emergency management experts accompanied the DOE Office of Emergency Response in deploying to Japan to support the U.S. Air Force Base in Yokota and the U.S. Embassy. A separate team from ORAU supported the NNSA Nuclear Incident Team, which served as the point of coordination for all support activities both in Japan and in the U.S.

  6. Is there a need for hydrological modelling in decision support systems for nuclear emergencies.

    PubMed

    Raskob, W; Heling, R; Zheleznyak, M

    2004-01-01

    This paper discusses the role of hydrological modelling in decision support systems for nuclear emergencies. In particular, most recent developments such as, the radionuclide transport models integrated in to the decision support system RODOS will be explored. Recent progress in the implementation of physically-based distributed hydrological models for operational forecasting in national and supranational centres, may support a closer cooperation between national hydrological services and therefore, strengthen the use of hydrological and radiological models implemented in decision support systems.

  7. Hanging core support system for a nuclear reactor. [LMFBR

    DOEpatents

    Burelbach, J.P.; Kann, W.J.; Pan, Y.C.; Saiveau, J.G.; Seidensticker, R.W.

    1984-04-26

    For holding the reactor core in the confining reactor vessel, a support is disclosed that is structurally independent of the vessel, that is dimensionally accurate and stable, and that comprises tandem tension linkages that act redundantly of one another to maintain stabilized core support even in the unlikely event of the complete failure of one of the linkages. The core support has a mounting platform for the reactor core, and unitary structure including a flange overlying the top edge of the reactor vessels, and a skirt and box beams between the flange and platform for establishing one of the linkages. A plurality of tension rods connect between the deck closing the reactor vessel and the platform for establishing the redundant linkage. Loaded Belleville springs flexibly hold the tension rods at the deck and separable bayonet-type connections hold the tension rods at the platform.

  8. A project to transfer technology from NASA centers in support of industrial innovation in the midwest

    NASA Technical Reports Server (NTRS)

    Barr, B. G.

    1986-01-01

    A technology transfer program utilizing graduate students in mechanical engineering at the University of Kansas was initiated in early 1981. The objective of the program was to encourage industrial innovation in the Midwest through improved industry/university cooperation and the utilization of NASA technology. A related and important aspect of the program was the improvement of graduate engineering education through the involvement of students in the identification and accomplishment of technological objectives in cooperation with scientists at NASA centers and engineers in industry. The pilot NASA/University Industrial Innovation Program was an outstanding success based on its ability to: attract top graduate students; secure industry support; and stimulate industry/university cooperation leading to enhanced university capability and utilization of advanced technology by industry.

  9. Technology Roadmap Instrumentation, Control, and Human-Machine Interface to Support DOE Advanced Nuclear Energy Programs

    SciTech Connect

    Donald D Dudenhoeffer; Burce P Hallbert

    2007-03-01

    Instrumentation, Controls, and Human-Machine Interface (ICHMI) technologies are essential to ensuring delivery and effective operation of optimized advanced Generation IV (Gen IV) nuclear energy systems. In 1996, the Watts Bar I nuclear power plant in Tennessee was the last U.S. nuclear power plant to go on line. It was, in fact, built based on pre-1990 technology. Since this last U.S. nuclear power plant was designed, there have been major advances in the field of ICHMI systems. Computer technology employed in other industries has advanced dramatically, and computing systems are now replaced every few years as they become functionally obsolete. Functional obsolescence occurs when newer, more functional technology replaces or supersedes an existing technology, even though an existing technology may well be in working order.Although ICHMI architectures are comprised of much of the same technology, they have not been updated nearly as often in the nuclear power industry. For example, some newer Personal Digital Assistants (PDAs) or handheld computers may, in fact, have more functionality than the 1996 computer control system at the Watts Bar I plant. This illustrates the need to transition and upgrade current nuclear power plant ICHMI technologies.

  10. Nuclear reactor heat transport system component low friction support system

    DOEpatents

    Wade, Elman E.

    1980-01-01

    A support column for a heavy component of a liquid metal fast breeder reactor heat transport system which will deflect when the pipes leading coolant to and from the heavy component expand or contract due to temperature changes includes a vertically disposed pipe, the pipe being connected to the heavy component by two longitudinally spaced cycloidal dovetail joints wherein the distal end of each of the dovetails constitutes a part of the surface of a large diameter cylinder and the centerlines of these large diameter cylinders intersect at right angles and the pipe being supported through two longitudinally spaced cycloidal dovetail joints wherein the distal end of each of the dovetails constitutes a part of the surface of a large diameter cylinder and the centerlines of these large diameter cylinders intersect at right angles, each of the cylindrical surfaces bearing on a flat and horizontal surface.

  11. Hanging core support system for a nuclear reactor

    DOEpatents

    Burelbach, James P.; Kann, William J.; Pan, Yen-Cheng; Saiveau, James G.; Seidensticker, Ralph W.

    1987-01-01

    For holding the reactor core in the confining reactor vessel, a support is disclosed that is structurally independent of the vessel, that is dimensionally accurate and stable, and that comprises tandem tension linkages that act redundantly of one another to maintain stabilized core support even in the unlikely event of the complete failure of one of the linkages. The core support has a mounting platform for the reactor core, and unitary structure including a flange overlying the top edge of the reactor vessels, and a skirt and box beams between the flange and platform for establishing one of the linkages. A plurality of tension rods connect between the deck closing the reactor vessel and the platform for establishing the redundant linkage. Loaded Belleville springs flexibly hold the tension rods at the deck and separable bayonet-type connections hold the tension rods at the platform. Motion or radiation sensing detectors can be provide at the lower ends of the tension rods for obtaining pertinent readings proximate the core.

  12. Dependable Hydrogen and Industrial Heat Generation from the Next Generation Nuclear Plant

    SciTech Connect

    Charles V. Park; Michael W. Patterson; Vincent C. Maio; Piyush Sabharwall

    2009-03-01

    The Department of Energy is working with industry to develop a next generation, high-temperature gas-cooled nuclear reactor (HTGR) as a part of the effort to supply the US with abundant, clean and secure energy. The Next Generation Nuclear Plant (NGNP) project, led by the Idaho National Laboratory, will demonstrate the ability of the HTGR to generate hydrogen, electricity, and high-quality process heat for a wide range of industrial applications. Substituting HTGR power for traditional fossil fuel resources reduces the cost and supply vulnerability of natural gas and oil, and reduces or eliminates greenhouse gas emissions. As authorized by the Energy Policy Act of 2005, industry leaders are developing designs for the construction of a commercial prototype producing up to 600 MWt of power by 2021. This paper describes a variety of critical applications that are appropriate for the HTGR with an emphasis placed on applications requiring a clean and reliable source of hydrogen. An overview of the NGNP project status and its significant technology development efforts are also presented.

  13. Definitional Hegemony as a Public Relations Strategy: The Rhetoric of the Nuclear Power Industry after Three Mile Island.

    ERIC Educational Resources Information Center

    Dionisopoulos, George N.; Crable, Richard E.

    1988-01-01

    Examines (1) definitional hegemony as one of several rhetorical options available to issue managers; (2) the post-accident rhetorical context of the Three Mile Island nuclear crisis; and (3) the specific strategies utilized to deal with this crisis. Assesses the nuclear industry's public relations efforts. (MS)

  14. INDUSTRIAL CONTROL SYSTEM CYBER SECURITY: QUESTIONS AND ANSWERS RELEVANT TO NUCLEAR FACILITIES, SAFEGUARDS AND SECURITY

    SciTech Connect

    Robert S. Anderson; Mark Schanfein; Trond Bjornard; Paul Moskowitz

    2011-07-01

    Typical questions surrounding industrial control system (ICS) cyber security always lead back to: What could a cyber attack do to my system(s) and; how much should I worry about it? These two leading questions represent only a fraction of questions asked when discussing cyber security as it applies to any program, company, business, or organization. The intent of this paper is to open a dialog of important pertinent questions and answers that managers of nuclear facilities engaged in nuclear facility security and safeguards should examine, i.e., what questions should be asked; and how do the answers affect an organization's ability to effectively safeguard and secure nuclear material. When a cyber intrusion is reported, what does that mean? Can an intrusion be detected or go un-noticed? Are nuclear security or safeguards systems potentially vulnerable? What about the digital systems employed in process monitoring, and international safeguards? Organizations expend considerable efforts to ensure that their facilities can maintain continuity of operations against physical threats. However, cyber threats particularly on ICSs may not be well known or understood, and often do not receive adequate attention. With the disclosure of the Stuxnet virus that has recently attacked nuclear infrastructure, many organizations have recognized the need for an urgent interest in cyber attacks and defenses against them. Several questions arise including discussions about the insider threat, adequate cyber protections, program readiness, encryption, and many more. These questions, among others, are discussed so as to raise the awareness and shed light on ways to protect nuclear facilities and materials against such attacks.

  15. Radiation exposure control from the application of nuclear gauges in the mining industry in Ghana.

    PubMed

    Faanu, A; Darko, E O; Awudu, A R; Schandorf, C; Emi-Reynolds, G; Yeboah, J; Glover, E T; Kattah, V K

    2010-05-01

    The use of nuclear gauges for process control and elemental analysis in the mining industry in Ghana, West Africa, is wide spread and on the increase in recent times. The Ghana Radiation Protection Board regulates nuclear gauges through a system of notification and authorization by registration or licensing, inspection, and enforcement. Safety assessments for authorization and enforcement have been established to ensure the safety and security of radiation sources as well as protection of workers and the general public. Appropriate training of mine staff is part of the efforts to develop the necessary awareness about the safety and security of radiation sources. The knowledge and skills acquired will ensure the required protection and safety at the workplaces. Doses received by workers monitored over a period between 1998 and 2007 are well below the annual dose limit of 20 mSv recommended by the International Commission on Radiological Protection.

  16. Approach to modify the properties of titanium alloys for use in nuclear industry

    NASA Astrophysics Data System (ADS)

    Bilobrov, Iurii; Trachevsky, Vladimir

    2011-08-01

    This article discusses the metallurgical aspects of the modification of titanium alloys for use in the nuclear industry in the future. Irradiation leads to hardening, plastic instability and reduction in fracture toughness in Ti alloys. Sintered compositions Ti-6Al-4V, Ti-6Al-4V/LaB 6 have shown methods to reduce embrittlement. Residual porosity may serve as a temporary storage of products of nuclear decay H and He. High uniformity of the element distribution reduces the number of places predisposed to defect cluster formation. The plasticity reserve of Ti-6Al-4V/LaB 6 in comparison with international standards is ≈10%. The boron compounds to the partial absorption of neutrons fill the volume of residual pores in the material without degrading the properties of the matrix Ti-6Al-4V/LaB 6 alloy.

  17. The Economic Potential of Three Nuclear-Renewable Hybrid Energy Systems Providing Thermal Energy to Industry

    SciTech Connect

    Ruth, Mark; Cutler, Dylan; Flores-Espino, Francisco; Stark, Greg; Jenkin, Thomas

    2016-12-01

    This report is one of a series of reports that Idaho National Laboratory and National Renewable Energy Laboratory are producing to investigate the technical and economic aspects of nuclear-renewable hybrid energy systems (N-R HESs). Previous reports provided results of an analysis of two N-R HES scenarios. This report builds that analysis with a Texas-synthetic gasoline scenario providing the basis in which the N-R HES sells heat directly to an industrial customer. Subsystems were included that convert electricity to heat thus allowing the renewable energy subsystem to generate heat and benefit from that revenue stream. Nuclear and renewable energy sources are important to consider in the energy sector's evolution because both are considered to be clean and non-carbon emitting energy sources.

  18. Current practices for risk zoning around nuclear power plants in comparison to other industry sectors.

    PubMed

    Kirchsteiger, Christian

    2006-08-25

    This paper analyses the background and current status of the information basis leading to the definition of risk and emergency zones around nuclear power plants (NPPs) in different countries in Europe and beyond. Although dependable plant-specific probabilistic safety assessment (PSA) of level 2 and/or level 3 could in principle provide sufficiently detailed input to define the geographical dimension of a NPP's risk and emergency zones, the analysis of the status in some European and other countries shows that other, "deterministic" approaches using a reference accident are actually used in practice. Regarding use of level 2 PSA for emergency planning, the approach so far has been to use the level 2 PSA information retrospectively to provide the justification for the choice of reference accident(s) used to define the emergency plans and emergency planning zones (EPZs). There are significant differences in the EPZs that are defined in different countries, ranging from a few up to 80km. There is a striking contrast in the extent of using probabilistic information to define emergency zones between the nuclear and other high risk industry sectors, such as the chemical process industry, and the reasons for these differences are not entirely clear, since the risk of chemical industry is similar as that of the nuclear sector. The differences seem to be more related to risk perception than to the actual risk potential. Therefore, there is a strong need to be able to communicate risk information to the Public both before and following an accident. In addition, there is a need to educate the Public so that they can understand risk information in a comparative sense. Finally, based on the consensus discussions at a recent JRC/OECD International Seminar on Risk and Emergency Zoning around NPPs, a set of recommendations is given in the areas of: -a more comprehensive use of the available risk information for risk zoning purposes, -risk communication; -comparative (energy) risk

  19. Nuclear Power for Catalonia: The Role of the Official Chamber of Industry of Barcelona, 1953-1962

    ERIC Educational Resources Information Center

    Salom, Francesc X. Barca

    2005-01-01

    Between 1939 and 1959, the regime led by General Franco pursued a policy of economic self-sufficiency. This policy inflicted great injury on Spanish science and industry, not least in Catalonia, and in its capital, Barcelona. In response, Catalan industry looked to a future made more promising by the advent of nuclear power. This paper describes…

  20. Applying radiological emergency planning experience to hazardous materials emergency planning within the nuclear industry

    SciTech Connect

    Foltman, A.; Newsom, D.; Lerner, K.

    1988-01-01

    The nuclear industry has extensive radiological emergency planning (REP) experience that is directly applicable to hazardous materials emergency planning. Recently, the Feed Materials Production Center near Cincinnati, Ohio, successfully demonstrated such application. The REP experience includes conceptual bases and standards for developing plans that have been tested in hundreds of full-scale exercises. The exercise program itself is also well developed. Systematic consideration of the differences between chemical and radiological hazards shows that relatively minor changes to the REP bases and standards are necessary. Conduct of full-scale, REP-type exercises serves to test the plans, provide training, and engender confidence and credibility.

  1. NASA safety program activities in support of the Space Exploration Initiatives Nuclear Propulsion program

    NASA Technical Reports Server (NTRS)

    Sawyer, J. C., Jr.

    1993-01-01

    The activities of the joint NASA/DOE/DOD Nuclear Propulsion Program Technical Panels have been used as the basis for the current development of safety policies and requirements for the Space Exploration Initiatives (SEI) Nuclear Propulsion Technology development program. The Safety Division of the NASA Office of Safety and Mission Quality has initiated efforts to develop policies for the safe use of nuclear propulsion in space through involvement in the joint agency Nuclear Safety Policy Working Group (NSPWG), encouraged expansion of the initial policy development into proposed programmatic requirements, and suggested further expansion into the overall risk assessment and risk management process for the NASA Exploration Program. Similar efforts are underway within the Department of Energy to ensure the safe development and testing of nuclear propulsion systems on Earth. This paper describes the NASA safety policy related to requirements for the design of systems that may operate where Earth re-entry is a possibility. The expected plan of action is to support and oversee activities related to the technology development of nuclear propulsion in space, and support the overall safety and risk management program being developed for the NASA Exploration Program.

  2. Prioritization of engineering support requests and advanced technology projects using decision support and industrial engineering models

    NASA Technical Reports Server (NTRS)

    Tavana, Madjid

    1995-01-01

    The evaluation and prioritization of Engineering Support Requests (ESR's) is a particularly difficult task at the Kennedy Space Center (KSC) -- Shuttle Project Engineering Office. This difficulty is due to the complexities inherent in the evaluation process and the lack of structured information. The evaluation process must consider a multitude of relevant pieces of information concerning Safety, Supportability, O&M Cost Savings, Process Enhancement, Reliability, and Implementation. Various analytical and normative models developed over the past have helped decision makers at KSC utilize large volumes of information in the evaluation of ESR's. The purpose of this project is to build on the existing methodologies and develop a multiple criteria decision support system that captures the decision maker's beliefs through a series of sequential, rational, and analytical processes. The model utilizes the Analytic Hierarchy Process (AHP), subjective probabilities, the entropy concept, and Maximize Agreement Heuristic (MAH) to enhance the decision maker's intuition in evaluating a set of ESR's.

  3. Bayesian Model Development for Analysis of Open Source Information to Support the Assessment of Nuclear Programs

    SciTech Connect

    Gastelum, Zoe N.; Whitney, Paul D.; White, Amanda M.

    2013-07-15

    Pacific Northwest National Laboratory has spent several years researching, developing, and validating large Bayesian network models to support integration of open source data sets for nuclear proliferation research. Our current work focuses on generating a set of interrelated models for multi-source assessment of nuclear programs, as opposed to a single comprehensive model. By using this approach, we can break down the models to cover logical sub-problems that can utilize different expertise and data sources. This approach allows researchers to utilize the models individually or in combination to detect and characterize a nuclear program and identify data gaps. The models operate at various levels of granularity, covering a combination of state-level assessments with more detailed models of site or facility characteristics. This paper will describe the current open source-driven, nuclear nonproliferation models under development, the pros and cons of the analytical approach, and areas for additional research.

  4. Parametric instabilities of rotor-support systems with application to industrial ventilators

    NASA Technical Reports Server (NTRS)

    Parszewski, Z.; Krodkiemski, T.; Marynowski, K.

    1980-01-01

    Rotor support systems interaction with parametric excitation is considered for both unequal principal shaft stiffness (generators) and offset disc rotors (ventilators). Instability regions and types of instability are computed in the first case, and parametric resonances in the second case. Computed and experimental results are compared for laboratory machine models. A field case study of parametric vibrations in industrial ventilators is reported. Computed parametric resonances are confirmed in field measurements, and some industrial failures are explained. Also the dynamic influence and gyroscopic effect of supporting structures are shown and computed.

  5. Digital Full-Scope Simulation of a Conventional Nuclear Power Plant Control Room, Phase 2: Installation of a Reconfigurable Simulator to Support Nuclear Plant Sustainability

    SciTech Connect

    Ronald L. Boring; Vivek Agarwal; Kirk Fitzgerald; Jacques Hugo; Bruce Hallbert

    2013-03-01

    The U.S. Department of Energy’s Light Water Reactor Sustainability program has developed a control room simulator in support of control room modernization at nuclear power plants in the U.S. This report highlights the recent completion of this reconfigurable, full-scale, full-scope control room simulator buildout at the Idaho National Laboratory. The simulator is fully reconfigurable, meaning it supports multiple plant models developed by different simulator vendors. The simulator is full-scale, using glasstop virtual panels to display the analog control boards found at current plants. The present installation features 15 glasstop panels, uniquely achieving a complete control room representation. The simulator is also full-scope, meaning it uses the same plant models used for training simulators at actual plants. Unlike in the plant training simulators, the deployment on glasstop panels allows a high degree of customization of the panels, allowing the simulator to be used for research on the design of new digital control systems for control room modernization. This report includes separate sections discussing the glasstop panels, their layout to mimic control rooms at actual plants, technical details on creating a multi-plant and multi-vendor reconfigurable simulator, and current efforts to support control room modernization at U.S. utilities. The glasstop simulator provides an ideal testbed for prototyping and validating new control room concepts. Equally importantly, it is helping create a standardized and vetted human factors engineering process that can be used across the nuclear industry to ensure control room upgrades maintain and even improve current reliability and safety.

  6. Tritium activities in Canada supporting CANDU{sup R} nuclear power reactors

    SciTech Connect

    Miller, J. M.

    2008-07-15

    An overview of the various Canadian tritium research and operational activities supporting the development, refurbishment and operation of CANDU{sup R} nuclear power reactors is presented. These activities encompass tritium health and safety, tritium in the environment, tritium interaction with materials, and tritium processing, and relate to both supporting R and D advances as well as operational best practices. The collective results of these activities contribute to our goals of improving worker and public safety, and operational efficiency. (authors)

  7. In vitro dissolution of respirable aerosols of industrial uranium and plutonium mixed-oxide nuclear fuels.

    PubMed

    Eidson, A F; Mewhinney, J A

    1983-12-01

    Dissolution characteristics of mixed-oxide nuclear fuels are important considerations for prediction of biological behavior of inhaled particles. Four representative industrial mixed-oxide powders were obtained from fuel fabrication enclosures. Studies of the dissolution of Pu, Am and U from aerosol particles of these materials in a serum simulant solution and in 0.1M HCl showed: (1) dissolution occurred at a rapid rate initially and slowed at longer times, (2) greater percentages of U dissolved than Pu or Am: with the dissolution rates of U and Pu generally reflecting the physical nature of the UO2-PuO2 matrix, (3) the temperature history of industrial mixed-oxides could not be reliably related to Pu dissolution except for a 3-5% increase when incorporated into a solid solution by sintering at 1750 degrees C, and (4) dissolution in the serum simulant agreed with the in vivo UO2 dissolution rate and suggested the dominant role of mechanical processes in PuO2 clearance from the lung. The rapid initial dissolution rate was shown to be related, in part, to an altered surface layer. The advantages and uses of in vitro solubility data for estimation of biological behavior of inhaled industrial mixed oxides, such as assessing the use of chelation therapy and interpretation of urinary excretion data, are discussed. It was concluded that in vitro solubility tests were useful, simple and easily applied to individual materials potentially inhaled by humans.

  8. Fitness for duty in the nuclear industry: Update of the technical issues 1996

    SciTech Connect

    Durbin, N.; Grant, T.

    1996-05-01

    The purpose of this report is to provide an update of information on the technical issues surrounding the creation, implementation, and maintenance of fitness-for-duty (FFD) policies and programs. It has been prepared as a resource for Nuclear Regulatory Commission (NRC) and nuclear power plant personnel who deal with FFD programs. It contains a general overview and update on the technical issues that the NRC considered prior to the publication of its original FFD rule and the revisions to that rule (presented in earlier NUREG/CRs). It also includes chapters that address issues about which there is growing concern and/or about which there have been substantial changes since NUREG/CR-5784 was published. Although this report is intended to support the NRC`s rule making on fitness for duty, the conclusions of the authors of this report are their own and do not necessarily represent the opinions of the NRC.

  9. Global nuclear industry views: challenges arising from the evolution of the optimisation principle in radiological protection.

    PubMed

    Saint-Pierre, S

    2012-01-01

    further improvements in the international RP system, it should be clearly borne in mind that the system is generally based on protection against the risk of cancer and hereditary diseases. The system also protects against deterministic non-cancer effects on tissues and organs. In seeking refinements of such protective notions, ICRP is invited to pay increased attention to the fact that a continued balance must be struck between beneficial activities that cause exposures and protection. The global nuclear industry is committed to help overcome these key RP issues as part of the RP community's upcoming international deliberations towards a more efficient international RP system.

  10. Perception of Aquaculture Education to Support Further Growth of Aquaculture Industry in Victoria, Australia

    ERIC Educational Resources Information Center

    Awal, Sadiqul; Christie, Andrew; Watson, Matthew; Hannadige, Asanka G. T.

    2012-01-01

    Purpose: The central aim of this study was to determine the perception of aquaculture educational provisions in the state of Victoria, and whether they are sufficient to ultimately support further growth of the industry. Design/methodology/approach: Questionnaires were formulated and distributed to participants in a variety of ways, including via…

  11. Trends to 1982 in Industrial Support of Basic Research. Special Report.

    ERIC Educational Resources Information Center

    National Science Foundation, Washington, DC. Div. of Science Resources Studies.

    This report analyzes recent trends in company-funded basic research support and incorporates findings from a special mail survey and personal interviews with research and development (R&D) officials of 54 firms. The report also provides insight into industry/university cooperative basic research efforts. Following an introduction, the report…

  12. Industry Review and Validation of Model Curriculum for Programmer/Analyst, Network Administration, and Technical Support.

    ERIC Educational Resources Information Center

    Schwager, Mahna; Lee, June

    Industry representatives reviewed the curricula for computer programmer-analyst, network administrator, and technical support courses at 10 community colleges in California. Thirty-eight reviewers participated in the focus groups, and several other reviewers participated via e-mail. The focus groups discussed each of the three degree programs…

  13. Engineering, Support, and Management Services: Construction Industry Series: Preparation Level: Student Manual and Instructor's Guide.

    ERIC Educational Resources Information Center

    Texas Education Agency, Austin. Dept. of Occupational Education and Technology.

    The guide is an outline of training experiences designed to lead a student to at least entry-level proficiency in engineering, support, and management service jobs within the construction industry. Teaching units cover construction drafting, architectural drawing, engineering drafting, estimating, expediting and scheduling, surveying, testing and…

  14. A Project-Based Laboratory for Learning Embedded System Design with Industry Support

    ERIC Educational Resources Information Center

    Lee, Chyi-Shyong; Su, Juing-Huei; Lin, Kuo-En; Chang, Jia-Hao; Lin, Gu-Hong

    2010-01-01

    A project-based laboratory for learning embedded system design with support from industry is presented in this paper. The aim of this laboratory is to motivate students to learn the building blocks of embedded systems and practical control algorithms by constructing a line-following robot using the quadratic interpolation technique to predict the…

  15. Industrial Complex for Solid Radwaste Management at Chernobyle Nuclear Power Plant

    SciTech Connect

    Ahner, S.; Fomin, V. V.

    2002-02-26

    In the framework of the preparation for the decommissioning of the Chernobyl Nuclear Power Plant (ChNPP) an Industrial Complex for Solid Radwaste Management (ICSRM) will be built under the EC TACIS Program in the vicinity of ChNPP. The paper will present the proposed concepts and their integration into existing buildings and installations. Further, the paper will consider the safety cases, as well as the integration of Western and Ukrainian Organizations into a cohesive project team and the requirement to guarantee the fulfillment of both Western standards and Ukrainian regulations and licensing requirements. The paper will provide information on the status of the interim design and the effects of value engineering on the output of basic design phase. The paper therefor summarizes the design results of the involved design engineers of the Design and Process Providers BNFL (LOT 1), RWE NUKEM GmbH (LOT 2 and General) and INITEC (LOT 3).

  16. Consideration of an industry-wide occupational health study of nuclear utility workers

    SciTech Connect

    1991-12-31

    This report assesses the advisability and feasibility of conducting an epidemiologic study of workers at commercial nuclear power plants in the United States. Such a study`s purpose would be to improve knowledge of the health implications of workplace exposure to fractional low-dose ionizing radiation. This issue is of considerable societal concern and can be addressed in human populations only by epidemiologic follow-up of large worker cohorts over extended periods of time. The report recommends that an industry-wide retrospective cohort health study of nuclear power workers is highly advisable. It would provide valuable information regarding the presence of observable health risks related to workplace exposures to ionizing radiation, especially the upper bounds of such risk. The study`s value will be enhanced if it continues as ongoing worker surveillance and if its analysis can eventually be merged with similar worker cohort studies elsewhere. Additional recommendations are made as to epidemiologic design, standardization, data assembly and analytic methods.

  17. MetroFission: New high-temperature references and sensors for the nuclear industry

    NASA Astrophysics Data System (ADS)

    Sadli, M.; del Campo, D.; de Podesta, M.; Deuzé, T.; Failleau, G.; Elliott, C. J.; Fourrez, S.; García, C.; Pearce, J. V.

    2013-09-01

    The European metrology research programme (EMRP) allows funding for metrology-oriented projects in the frame of targeted calls aimed at improving metrology for important contemporary and future needs in different fields such as energy, environment and industry. A joint research project (JRP), called "MetroFission", was selected for funding in the "Energy" call of 2010. This JRP, led by NPL (UK), aims to anticipate and to start addressing the metrological needs of the next generation of nuclear power plants. The need for improving the accuracy and reliability of temperature measurements at temperatures higher than those currently measured in nuclear power plants is dealt with in the first workpackage of the project. This project started in September 2010 and will last for three years. This paper summarizes the activities of the first half of the project and the expected final achievements, which will be essentially oriented towards new temperature references and new devices, adapted to the high temperature range as well as the particularly harsh working conditions.

  18. Attitude towards personal protective equipment in the French nuclear fuel industry.

    PubMed

    Guseva Canu, Irina; Faust, Ségolène; Canioni, Pierre; Collomb, Philippe; Samson, Eric; Laurier, Dominique

    2013-06-01

    This descriptive cross-sectional study examines the compliance of workers from the European Gaseous Diffusion Uranium Enrichment Consortium (EURODIF) with personal protection equipment (PPE) in view of the various hazards in the nuclear fuel industry. The PPE inventory was drawn up by an industrial hygienist in charge of the PPE at EURODIF. Two hundred and twenty seven (10%) randomly selected, active and retired, EURODIF workers filled in a questionnaire on their attitudes towards PPE. Exposure data from the EURODIF job exposure matrix were used to examine whether PPE usage varies according to exposure level. The study suggests a PPE usage profile that varies depending on the hazards present and PPE available. Anti-uranium PPE and gloves were among the best rated, while anti-spray goggles were the least used. We found that, for most hazards known to cause cancer or irreversible health damage, PPE usage varied according to exposure (homogeneity test, p<0.05; trend test, p<0.05). The continuous use of PPE among workers should be encouraged through improvements to the PPE management system. A precise model of individual exposure can only be designed if the use and efficiency of PPE are taken into consideration.

  19. Nuclear accumulation of seven in absentia homologue-2 supports motility and proliferation of liver cancer cells.

    PubMed

    Malz, Mona; Aulmann, Antje; Samarin, Jana; Bissinger, Michaela; Longerich, Thomas; Schmitt, Sabrina; Schirmacher, Peter; Breuhahn, Kai

    2012-11-01

    Stability of many tumor-relevant proteins is partly mediated by E3 ligases, which determine substrate specificity within the ubiquitin system. Recent data demonstrated that increased nuclear expression of the E3 ligase seven in absentia homologue (SIAH)-1 in human hepatocarcinogenesis supports tumor cell proliferation and migration. To define whether closely related SIAH-2 synergizes with protumorigenic SIAH-1, we systematically analyzed expression, localization and functional relevance of SIAH-2 in human hepatocellular carcinoma (HCC). Nuclear accumulation of SIAH-2 is detectable in more than 60% of all HCCs and correlates with tumor progression, cell proliferation and distant metastasis. An inverse correlation between nuclear SIAH-1 and SIAH-2 was detected, suggesting independent mechanisms for nuclear enrichment. Inhibition of nuclear SIAH-2 by RNAi in HCC cell lines reduced proliferation as well as lateral tumor cell motility and transmigration; however, combined knock down of both SIAH-1 and SIAH-2 did not further amplify biological effects compared to single gene inhibition. Reduction of SIAH-2 expression sensitizes HCC cells to the treatment with different cytostatic drugs, demonstrating that SIAH-2-targeting approaches may increase the response of HCC cells to conventional chemotherapy. Together, these data show that SIAH-2--as described for SIAH-1--accumulates in nuclei of HCC cells where it supports tumor growth and tumor cell dissemination. Because the nuclear pattern of SIAH-2 differs in HCC tissues from the SIAH-1 pattern and because the inactivation of SIAH-2 is not compensated by SIAH-1, the specific inhibition of SIAH-2 (especially in combination with other drugs) represents a promising therapeutic strategy for HCC.

  20. Technical Steps to Support Nuclear Arsenal Downsizing: A Report by the APS Panel on Public Affairs

    DTIC Science & Technology

    2010-02-01

    CONTRACT NUMBER 5b. GRANT NUMBER 5c. PROGRAM ELEMENT NUMBER 6. AUTHOR(S) 5d. PROJECT NUMBER 5e. TASK NUMBER 5f. WORK UNIT NUMBER 7. PERFORMING...validate fissile materials declarations. To support the goal of sustaining the capability and expertise: • Refurbish elements of the US nuclear... elements as infrared and video cameras, radiation portal moni- tors, motion detectors, encrypted RF communications, advanced intrusion detection, innovative

  1. A decision-support system for off-site nuclear emergencies.

    PubMed

    Yihua, X; Lin, G; Su, P; Tiefu, L; Honghui, X; Yongxing, Z; Xinzeng, S

    1998-03-01

    In the case of a nuclear emergency, quick, well-founded decisions must be made about the type of protective action, its region of application, and initiation time. These typically are tasks for computer-based systems. Even with emergency-preparedness, exercises, and training, the decision-support system is one of great importance. This paper describes a decision-support system recently developed by the China Institute of Atomic Energy; it can optimally rank actions during the early phase of an accident using multiattribute utility analysis, and for the intermediate and later phases by cost-benefit analysis. This system runs both on MICRO VAX II and PC systems.

  2. Efficiency of Nuclear and Mitochondrial Markers Recovering and Supporting Known Amniote Groups

    PubMed Central

    Lambret-Frotté, Julia; Perini, Fernando Araújo; de Moraes Russo, Claudia Augusta

    2012-01-01

    We have analysed the efficiency of all mitochondrial protein coding genes and six nuclear markers (Adora3, Adrb2, Bdnf, Irbp, Rag2 and Vwf) in reconstructing and statistically supporting known amniote groups (murines, rodents, primates, eutherians, metatherians, therians). The efficiencies of maximum likelihood, Bayesian inference, maximum parsimony, neighbor-joining and UPGMA were also evaluated, by assessing the number of correct and incorrect recovered groupings. In addition, we have compared support values using the conservative bootstrap test and the Bayesian posterior probabilities. First, no correlation was observed between gene size and marker efficiency in recovering or supporting correct nodes. As expected, tree-building methods performed similarly, even UPGMA that, in some cases, outperformed other most extensively used methods. Bayesian posterior probabilities tend to show much higher support values than the conservative bootstrap test, for correct and incorrect nodes. Our results also suggest that nuclear markers do not necessarily show a better performance than mitochondrial genes. The so-called dependency among mitochondrial markers was not observed comparing genome performances. Finally, the amniote groups with lowest recovery rates were therians and rodents, despite the morphological support for their monophyletic status. We suggest that, regardless of the tree-building method, a few carefully selected genes are able to unfold a detailed and robust scenario of phylogenetic hypotheses, particularly if taxon sampling is increased. PMID:23032608

  3. Geopressure industrial forums, newsletter and lease support. Final report, April 7, 1981-December 31, 1983

    SciTech Connect

    Knutson, C.F.

    1983-12-01

    In the course of this contract C. K. GeoEnergy: (1) planned, organized, conducted, and reported on six DOE/Industry Forum meetings where the progress of DOE's resource development program was outlined and discussed (these six forum meetings included three meetings of the Drilling and Testing Subgroup and three meetings of the Overview Group), (2) prepared and distributed 15 newsletters, and (3) prepared three reports for DOE lease support. This final report includes summaries of each of the forum meetings as well as the three lease support meetings and the newsletter program.

  4. Cancer mortality in relation to monitoring for radionuclide exposure in three UK nuclear industry workforces.

    PubMed Central

    Carpenter, L. M.; Higgins, C. D.; Douglas, A. J.; Maconochie, N. E.; Omar, R. Z.; Fraser, P.; Beral, V.; Smith, P. G.

    1998-01-01

    Cancer mortality in 40,761 employees of three UK nuclear industry facilities who had been monitored for external radiation exposure was examined according to whether they had also been monitored for possible internal exposure to tritium, plutonium or other radionuclides (uranium, polonium, actinium or other unspecified). Death rates from cancer were compared both with national rates and with rates in radiation workers not monitored for exposure to any radionuclides. Among workers monitored for tritium exposure, overall cancer mortality was significantly below national rates [standardized mortality ratio (SMR) = 83, 165 deaths; 2P = 0.02] and none of the cancer-specific death rates was significantly above either the national average or rates in non-monitored workers. Although the overall death rate from cancer in workers monitored for plutonium exposure was also significantly low relative to national rates (SMR = 89, 581 deaths; 2P = 0.005), mortality from pleural cancer was significantly raised (SMR = 357, nine deaths; 2P = 0.002); none of the rates differed significantly from those of non-monitored workers. Workers monitored for radionuclides other than tritium or plutonium also had a death rate from all cancers combined that was below the national average (SMR = 86, 418 deaths; 2P = 0.002) but prostatic cancer mortality was raised both in relation to death rates in the general population (SMR = 153, 37 deaths; 2P = 0.02) and to death rates in radiation workers who had not been monitored for exposure to any radionuclide [rate ratio (RR) = 1.65; 2P = 0.03]. Mortality from cancer of the lung was also significantly increased in workers monitored for other radionuclides compared with those of radiation workers not monitored for exposure to radionuclides (RR = 1.31, 164 deaths; 2P = 0.01). For cancers of the lung, prostate and all cancers combined, death rates in monitored workers were examined according to the timing and duration of monitoring for radionuclide

  5. First principles surface thermodynamics of industrial supported catalysts in working conditions

    NASA Astrophysics Data System (ADS)

    Raybaud, P.; Costa, D.; Corral Valero, M.; Arrouvel, C.; Digne, M.; Sautet, P.; Toulhoat, H.

    2008-02-01

    Ever stronger environmental concerns prompt the research in the area of heterogeneous catalysis to play an ever more crucial role to produce ever cleaner fuel from the refining of petroleum effluents. The catalytic active phase is often used in a dispersed state over a porous oxide material. This paper is a review of recent progress brought by periodic density functional theory (DFT) calculations in the area of two relevant industrial supported catalysts. We focus on two important supports used in the refining industry: anatase-TiO2 and γ-alumina. According to the various reaction conditions, the presence of H2O, H2 and H2S may change the surface states of the support. In particular, it is crucial to know and control the hydroxylation state depending on temperature and partial pressure of reactants (H2O, H2, H2S). The support effects on the catalytic active phases are presented for MoS2 particles, used in hydrodesulfurization catalysis, and for Pd particles, used in hydrogenation catalysis. It is shown how the wetting property and equilibrium morphology of the active phase depend on the support. A discussion on the impact for catalytic activities is provided.

  6. Professional societies and industry support: what is the quid pro quo?

    PubMed

    Kassirer, Jerome P

    2007-01-01

    Professional medical societies have become increasingly dependent on pharmaceutical, device, and biotechnology companies for ongoing support of their programs, but the internal influence of this financial largesse on medical societies' practices is well hidden. Many examples exist in which societies' educational products, including clinical practice guidelines and professional publications, have been tainted by involvement by industry-paid individuals. These examples show that professional judgments of organizations can be affected in ways that are not in the best interests of our patients. Society leaders should develop policies that leave critical decisions, especially those that affect patient care, in the hands of members without financial ties to industry. Society leaders should not accept funds designated for specific industry-recommended projects unless such programs are already part of their planned agenda. These leaders, who typically serve for only a year or two, should delve into arrangements that salaried society executives make with industry, and insure that no promises are made that compromise an organization's professional goals. Professional societies should also find ways of reducing the vast, embarrassing industry involvement at their national meetings, especially the vulgar circus-like displays and the drug company-sponsored symposia. We must reduce commercialism and restore professionalism to our medical meetings.

  7. Technical support for the Ukrainian State Committee for Nuclear Radiation Safety on specific waste issues

    SciTech Connect

    Little, C.A.

    1995-07-01

    The government of Ukraine, a now-independent former member of the Soviet Union, has asked the United States to assist its State Committee for Nuclear and Radiation Safety (SCNRS) in improving its regulatory control in technical fields for which it has responsibility. The US Nuclear Regulatory Commission (NRC) is providing this assistance in several areas, including management of radioactive waste and spent fuel. Radioactive wastes resulting from nuclear power plant operation, maintenance, and decommissioning must be stored and ultimately disposed of appropriately. In addition, radioactive residue from radioisotopes used in various industrial and medical applications must be managed. The objective of this program is to provide the Ukrainian SCNRS with the information it needs to establish regulatory control over uranium mining and milling activities in the Zheltye Vody (Yellow Waters) area and radioactive waste disposal in the Pripyat (Chernobyl) area among others. The author of this report, head of the Environmental Technology Section, Health Sciences Research Division of Oak Ridge National Laboratory, accompanied NRC staff to Ukraine to meet with SCNRS staff and visit sites in question. The report highlights problems at the sites visited and recommends license conditions that SCNRS can require to enhance safety of handling mining and milling wastes. The author`s responsibility was specifically for the visit to Zheltye Vody and the mining and milling waste sites associated with that facility. An itinerary for the Zheltye Vody portion of the trip is included as Appendix A.

  8. Applications of high resolution ICP-AES in the nuclear industry

    SciTech Connect

    Johnson, S.G.; Giglio, J.J.; Goodall, P.S.; Cummings, D.G.

    1998-07-01

    Application of high resolution ICP-AES to selected problems of importance in the nuclear industry is a growing field. The advantages in sample preparation time, waste minimization and equipment cost are considerable. Two examples of these advantages are presented in this paper, burnup analysis of spent fuel and analysis of major uranium isotopes. The determination of burnup, an indicator of fuel cycle efficiency, has been accomplished by the determination of {sup 139}La by high resolution inductively coupled plasma atomic emission spectroscopy (HR-ICP-AES). Solutions of digested samples of reactor fuel rods were introduced into a shielded glovebox housing an inductively coupled plasma (ICP) and the resulting atomic emission transmitted to a high resolution spectrometer by a 31 meter fiber optic bundle. Total and isotopic U determination by thermal ionization mass spectrometry (TIMS) is presented to allow for the calculation of burnup for the samples. This method of burnup determination reduces the time, material, sample handling and waste generated associated with typical burnup determinations which require separation of lanthanum from the other fission products with high specific activities. Work concerning an alternative burnup indicator, {sup 236}U, is also presented for comparison. The determination of {sup 235}U:{sup 238}U isotope ratios in U-Zr fuel alloys is also presented to demonstrate the versatility of HR-ICP-AES.

  9. A Review of Human Reliability Needs in the U.S. Nuclear Industry

    SciTech Connect

    Boring, Ronald Laurids

    2015-08-01

    In this survey, 34 subject matter experts from the U.S. nuclear industry were interviewed to determine specific needs for human reliability analysis (HRA). Conclusions from the interviews are detailed in this article. A summary of the findings includes: (1) The need for improved guidance on the use of HRA methods generally and for specific applications. (2) The need for additional training in HRA to provide more hands-on experience in the application of HRA methods. (3) Thedevelopment of HRA approaches suitable for advanced reactors, severe accident situations, and low-power and shutdown applications. (4) The refinement of HRA methods to account forfactors such as crew variability, latent errors, more sophisticated dependency modeling, and errors of commission. (5) The continued need for simplified HRA methods appropriate for field applications. (6) The need for tighter coupling of HRA and human factors. (7) The need for improvements in the quantitative basis of HRA methods. These findings suggest the field of HRA is mature but still benefits from refinements.

  10. Radiochemistry Student, Postdoc and Invited Speaker Support for New Directions in Isotope Production, Nuclear Forensics and Radiochemistry Supported by the DOE

    SciTech Connect

    Jurisson, Silvia, S.

    2011-04-11

    The Division of Nuclear Chemistry and Technology (NUCL) of the American Chemistry Society (ACS) is sponsoring a symposium entitled "New Directions in Isotope Production, Nuclear Forensics and Radiochemistry Supported by the DOE" at the 240th ACS National Meeting in Boston, MA 22-26 August 2010. Radiochemistry and nuclear science is a critical area of research and funding for which the DOE has provided support over the years. Radiochemistry is undergoing a renaissance in interdisciplinary areas including medicine, materials, nanotechnology, nuclear forensics and energy. For example, interest in nuclear energy is growing in response to global warming. The field of nuclear forensics has grown significantly since 9/11 in response to potential terror threats and homeland security. Radioactive molecular imaging agents and targeted radiotherapy are revolutionizing molecular medicine. The need for radiochemists is growing, critical, and global. The NUCL Division of the ACS has been involved in various areas of radiochemistry and nuclear chemistry for many years, and is the host of the DOE supported Nuclear Chemistry Summer Schools. This Symposium is dedicated to three of the critical areas of nuclear science, namely isotope production, nuclear forensics and radiochemistry. An important facet of this meeting is to provide support for young radiochemistry students/postdoctoral fellows to attend this Symposium as participants and contributors. The funding requested from DOE in this application will be used to provide bursaries for U.S. students/postdoctoral fellows to enable them to participate in this symposium at the 240th ACS National Meeting, and for invited scientists to speak on the important issues in these areas.

  11. The hydrological impact assessment in the decision support of nuclear emergency response.

    PubMed

    Vamanu, Dan V; Slavnicu, Dan S; Gheorghiu, Dorina; Acasandrei, Valentin T; Slavnicu, Elena

    2010-07-01

    The paper presents several aspects believed to be relevant for the integration in the decision support systems for the management of radiological emergencies, of assessment tools addressing surface water contamination. Three exemplary cases are discussed in the context-the CONVEX 2005 international alert exercise, AXIOPOLIS 09, a national drill targeting a CANDU reactor at Cernavoda nuclear power plant in Romania, and Oltenia 07-a nation-wide drill around a scenario, involving trans-border effects of a virtual accident at a VVER reactor at Kozloduy, Bulgaria. The capability of different analytic tools were tested, including public deliverables like real-time, online decision support system's HDM module and model-based computerised system for management support to identify optimal remedial strategies for restoring radionuclide-contaminated aquatic ecosystems and drainage areas, as well as research-grade, home-made facilities, in order to identify and sort out merits and issues of interest in steering their effective utilisation.

  12. DOE/DHS INDUSTRIAL CONTROL SYSTEM CYBER SECURITY PROGRAMS: A MODEL FOR USE IN NUCLEAR FACILITY SAFEGUARDS AND SECURITY

    SciTech Connect

    Robert S. Anderson; Mark Schanfein; Trond Bjornard; Paul Moskowitz

    2011-07-01

    Many critical infrastructure sectors have been investigating cyber security issues for several years especially with the help of two primary government programs. The U.S. Department of Energy (DOE) National SCADA Test Bed and the U.S. Department of Homeland Security (DHS) Control Systems Security Program have both implemented activities aimed at securing the industrial control systems that operate the North American electric grid along with several other critical infrastructure sectors (ICS). These programs have spent the last seven years working with industry including asset owners, educational institutions, standards and regulating bodies, and control system vendors. The programs common mission is to provide outreach, identification of cyber vulnerabilities to ICS and mitigation strategies to enhance security postures. The success of these programs indicates that a similar approach can be successfully translated into other sectors including nuclear operations, safeguards, and security. The industry regulating bodies have included cyber security requirements and in some cases, have incorporated sets of standards with penalties for non-compliance such as the North American Electric Reliability Corporation Critical Infrastructure Protection standards. These DOE and DHS programs that address security improvements by both suppliers and end users provide an excellent model for nuclear facility personnel concerned with safeguards and security cyber vulnerabilities and countermeasures. It is not a stretch to imagine complete surreptitious collapse of protection against the removal of nuclear material or even initiation of a criticality event as witnessed at Three Mile Island or Chernobyl in a nuclear ICS inadequately protected against the cyber threat.

  13. The role of research in nuclear regulation: A US industry perspective

    SciTech Connect

    Simard, R.L.

    1997-01-01

    The author reviews the focus of research efforts within the NRC following the development of nuclear energy. Initial work focused on research in support of rulemaking and generic-issue resolution largely to support the licensing of U.S. plants that was going on at the time, including study of design basis accidents. Going into the 1980`s there was a need for information on accidents beyond the design basis, following the TMI accident. Aging research became relevant with the plants accumulating years of operation. More recently effort has gone into work on more advanced reactor designs. Looking ahead the author argues there may be few unresolved safety issues, and analytic tools are presently very well developed. So the question of what to do in the future is relevant, especially when coupled with changing responsibilities, changing legislation, changing budgets, changing market forces, and changing expectations from consumers. So the author poses questions which should be addressed as one looks at planning for the role of research in the NRC in the future.

  14. Industrial hygiene support of underground operations at the Nevada Test Site. Progress report, July 1, 1989--June 30, 1991

    SciTech Connect

    Porter, P.F.

    1992-07-23

    The Industrial Hygiene Section of the Health Protection Department provides industrial hygiene support of underground operations at the Nevada Test Site. This report describes support operations and summarizes the industrial hygiene data collected from July 31, 1989 through June 30, 1991. Air quality data were collected by means of personnel sampling by active and passive techniques using various kinds of industrial hygiene instrumentation and through localized and general area monitoring. The data collected were used to evaluate underground air quality and quantity requirements; evaluate worker exposures to a variety of air contaminants; determine the applicability and effectiveness of personal protective equipment.

  15. Supporting the President's Arms Control and Nonproliferation Agenda: Transparency and Verification for Nuclear Arms Reductions

    SciTech Connect

    Doyle, James E; Meek, Elizabeth

    2009-01-01

    The President's arms control and nonproliferation agenda is still evolving and the details of initiatives supporting it remain undefined. This means that DOE, NNSA, NA-20, NA-24 and the national laboratories can help define the agenda, and the policies and the initiatives to support it. This will require effective internal and interagency coordination. The arms control and nonproliferation agenda is broad and includes the path-breaking goal of creating conditions for the elimination of nuclear weapons. Responsibility for various elements of the agenda will be widely scattered across the interagency. Therefore an interagency mapping exercise should be performed to identify the key points of engagement within NNSA and other agencies for creating effective policy coordination mechanisms. These can include informal networks, working groups, coordinating committees, interagency task forces, etc. It will be important for NA-20 and NA-24 to get a seat at the table and a functional role in many of these coordinating bodies. The arms control and nonproliferation agenda comprises both mature and developing policy initiatives. The more mature elements such as CTBT ratification and a follow-on strategic nuclear arms treaty with Russia have defined milestones. However, recent press reports indicate that even the START follow-on strategic arms pact that is planned to be complete by the end of 2009 may take significantly longer and be more expansive in scope. The Russians called for proposals to count non-deployed as well as deployed warheads. Other elements of the agenda such as FMCT, future bilateral nuclear arms reductions following a START follow-on treaty, nuclear posture changes, preparations for an international nuclear security summit, strengthened international safeguards and multilateral verification are in much earlier stages of development. For this reason any survey of arms control capabilities within the USG should be structured to address potential needs across the

  16. A mortality study of employees of the nuclear industry in Oak Ridge, Tennessee.

    PubMed

    Frome, E L; Cragle, D L; Watkins, J P; Wing, S; Shy, C M; Tankersley, W G; West, C M

    1997-07-01

    An analysis was conducted of 27,982 deaths among 106,020 persons employed at four Federal nuclear plants in Oak Ridge, Tennessee, between 1943 and 1985. The main objectives were to extend the evaluation of the health effects of employment in the nuclear industry in Oak Ridge to include most workers who were omitted from earlier studies, to compare the mortality experience of workers among the facilities, to address methodological problems that occur when individuals employed at more than one facility are included in the analysis, and to conduct dose-response analyses for those individuals with potential exposure to external radiation. All-cause mortality and all-cancer mortality were in close agreement with national rates. The only notable excesses occurred for white males for lung cancer [standardized mortality ratio (SMR) = 1.18, 1,849 deaths] and non-malignant respiratory disease (SMR = 1.12, 1,568 deaths). A more detailed analysis revealed substantial differences in death rates among workers at the Oak Ridge plants. Evaluation of internally adjusted log SMRs using Poisson regression showed that workers employed only at Tennessee Eastman Corporation or K-25 and at multiple facilities had higher death rates than similar workers employed only at X-10 or Y-12, and that the differences were primarily due to non-cancer causes. Analysis of selected cancer causes for white males indicated large differences among the workers at the different facilities for lung cancer, leukemia and other lymphatic cancer. Dose-response analyses for external penetrating radiation were limited to a subcohort of 28,347 white males employed at X-10 or Y-12. Their collective recorded dose equivalent was 376 Sv. There was a strong "healthy worker effect" in this subcohort-all-cause SMR = 0.80 (4,786 deaths) and all-cancer SMR = 0.87 (1,134 deaths). Variables included in the analyses were age, birth cohort, a measure of socioeconomic status, length of employment, internal radiation exposure

  17. Section 2: Corrosion and failure analysis studies in support of the pulp and paper industry

    SciTech Connect

    Keiser, J.R.; Pawel, S.J.; Swindeman, R.W.; Longmire, H.F.

    1997-04-01

    Technical support is being provided to various pulp and paper companies and related industries to help determine the cause of material degradation problems and to identify alternate materials to prevent such degradation. During the past year, examinations have included parts from several sootblowers, two failed economizer tubes, and inspection of a continuous digester. The results of the analyses and inspections were communicated to the plant operators, and, in some cases, recommendations were made. This article discusses examination of sootblower nozzles, which evidenced intergranular cracking. Analysis indicated the presence of chromium carbide precipitates along the grain boundaries, which can cause the sample to be sensitized to grain boundary attack.

  18. Summary of technical information and agreements from Nuclear Management and Resources Council industry reports addressing license renewal

    SciTech Connect

    Regan, C.; Lee, S.; Chopra, O.K.; Ma, D.C.; Shack, W.J.

    1996-10-01

    In about 1990, the Nuclear Management and Resources Council (NUMARC) submitted for NRC review ten industry reports (IRs) addressing aging issues associated with specific structures and components of nuclear power plants ad one IR addressing the screening methodology for integrated plant assessment. The NRC staff had been reviewing the ten NUMARC IRs; their comments on each IR and NUMARC responses to the comments have been compiled as public documents. This report provides a brief summary of the technical information and NUMARC/NRC agreements from the ten IRs, except for the Cable License Renewal IR. The technical information and agreements documented herein represent the status of the NRC staffs review when the NRC staff and industry resources were redirected to address rule implementation issues. The NRC staff plans to incorporate appropriate technical information and agreements into the draft standard review plan for license renewal.

  19. Preparation and characterization of (10)B boric acid with high purity for nuclear industry.

    PubMed

    Zhang, Weijiang; Liu, Tianyu; Xu, Jiao

    2016-01-01

    Boric acid is often added into coolant as neutron capture agent for pressurized water reactor, whose amount is influenced by its abundance and purity. Therefore, the preparation of enriched (10)B boric acid with high purity is beneficial to nuclear industry. (10)B is also used in developing tumor-specific boronated drugs in boron neutron capture therapy. The boronated drug can be administered to patient intravenously, intratumorally, or deposited at tumor site in surgical excision. Thus, enriched (10)B boric acid is of practical significance in the field of medicine. Self-made boron trifluoride-methanol-complex solution was selected as one of the experimental reagents, and the preparation of (10)B acid was realized by one-step reaction for the complexes with water and calcium chloride. The determination of electrical conductivity in reaction process proves that the optimum reaction time was 16-20 h. Furthermore, the effect of reaction time, ratio of calcium chloride to complex as well as the amount of water on the purity and yield of boric acid was investigated. Finally, the optimum reaction time was 20 h, the optimal solid-liquid ratio (molar ratio) was 3:1, and the amount of water was 1 L of deionized water for each mol of the complex. H2O2 was added in the reaction process to remove Fe(2+). After recrystallization, IR spectra of (10)B boric acid was measured and compared with standard to verify the product of boric acid. The feasibility of the preparation method was determined by the detection of XRD of boric acid. To observe the morphology by polarizing microscope, crystal structure was obtained. The purity of the final product is 99.95 %, and the yield is 96.47 %. The ion concentration of boric acid accords with the national standard of high purity, which was determined by ICP.

  20. Modeling of Some Physical Properties of Zirconium Alloys for Nuclear Applications in Support of UFD Campaign

    SciTech Connect

    Michael V. Glazoff

    2013-08-01

    Zirconium-based alloys Zircaloy-2 and Zircaloy-4 are widely used in the nuclear industry as cladding materials for light water reactor (LWR) fuels. These materials display a very good combination of properties such as low neutron absorption, creep behavior, stress-corrosion cracking resistance, reduced hydrogen uptake, corrosion and/or oxidation, especially in the case of Zircaloy-4. However, over the last couple of years, in the post-Fukushima Daiichi world, energetic efforts have been undertaken to improve fuel clad oxidation resistance during off-normal temperature excursions. Efforts have also been made to improve upon the already achieved levels of mechanical behavior and reduce hydrogen uptake. In order to facilitate the development of such novel materials, it is very important to achieve not only engineering control, but also a scientific understanding of the underlying material degradation mechanisms, both in working conditions and in storage of used nuclear fuel. This report strives to contribute to these efforts by constructing the thermodynamic models of both alloys; constructing of the respective phase diagrams, and oxidation mechanisms. A special emphasis was placed upon the role of zirconium suboxides in hydrogen uptake reduction and the atomic mechanisms of oxidation. To that end, computational thermodynamics calculations were conducted concurrently with first-principles atomistic modeling.

  1. Structural dynamic and thermal stress analysis of nuclear reactor vessel support system

    NASA Technical Reports Server (NTRS)

    Chi-Diango, J.

    1972-01-01

    A nuclear reactor vessel is supported by a Z-ring and a box ring girder. The two proposed structural configurations to transmit the loads from the Z-ring and the box ring girder to the foundation are shown. The cantilever concrete ledge transmitting the load from the Z-ring and the box girder via the cavity wall to the foundation is shown, along with the loads being transmitted through one of the six steel columns. Both of these two supporting systems were analyzed by using rigid format 9 of NASTRAN for dynamic loads, and the thermal stresses were analyzed by AXISOL. The six column configuration was modeled by a combination of plate and bar elements, and the concrete cantilever ledge configuration was modeled by plate elements. Both configurations were found structurally satisfactory; however, nonstructural considerations favored the concrete cantilever ledge.

  2. Online Condition Monitoring of Bearings to Support Total Productive Maintenance in the Packaging Materials Industry

    PubMed Central

    Gligorijevic, Jovan; Gajic, Dragoljub; Brkovic, Aleksandar; Savic-Gajic, Ivana; Georgieva, Olga; Di Gennaro, Stefano

    2016-01-01

    The packaging materials industry has already recognized the importance of Total Productive Maintenance as a system of proactive techniques for improving equipment reliability. Bearing faults, which often occur gradually, represent one of the foremost causes of failures in the industry. Therefore, detection of their faults in an early stage is quite important to assure reliable and efficient operation. We present a new automated technique for early fault detection and diagnosis in rolling-element bearings based on vibration signal analysis. Following the wavelet decomposition of vibration signals into a few sub-bands of interest, the standard deviation of obtained wavelet coefficients is extracted as a representative feature. Then, the feature space dimension is optimally reduced to two using scatter matrices. In the reduced two-dimensional feature space the fault detection and diagnosis is carried out by quadratic classifiers. Accuracy of the technique has been tested on four classes of the recorded vibrations signals, i.e., normal, with the fault of inner race, outer race, and ball operation. The overall accuracy of 98.9% has been achieved. The new technique can be used to support maintenance decision-making processes and, thus, to increase reliability and efficiency in the industry by preventing unexpected faulty operation of bearings. PMID:26938541

  3. Online Condition Monitoring of Bearings to Support Total Productive Maintenance in the Packaging Materials Industry.

    PubMed

    Gligorijevic, Jovan; Gajic, Dragoljub; Brkovic, Aleksandar; Savic-Gajic, Ivana; Georgieva, Olga; Di Gennaro, Stefano

    2016-03-01

    The packaging materials industry has already recognized the importance of Total Productive Maintenance as a system of proactive techniques for improving equipment reliability. Bearing faults, which often occur gradually, represent one of the foremost causes of failures in the industry. Therefore, detection of their faults in an early stage is quite important to assure reliable and efficient operation. We present a new automated technique for early fault detection and diagnosis in rolling-element bearings based on vibration signal analysis. Following the wavelet decomposition of vibration signals into a few sub-bands of interest, the standard deviation of obtained wavelet coefficients is extracted as a representative feature. Then, the feature space dimension is optimally reduced to two using scatter matrices. In the reduced two-dimensional feature space the fault detection and diagnosis is carried out by quadratic classifiers. Accuracy of the technique has been tested on four classes of the recorded vibrations signals, i.e., normal, with the fault of inner race, outer race, and ball operation. The overall accuracy of 98.9% has been achieved. The new technique can be used to support maintenance decision-making processes and, thus, to increase reliability and efficiency in the industry by preventing unexpected faulty operation of bearings.

  4. Creating an educational consortium to support the recruitment and retention of expertise for the nuclear weapons complex

    SciTech Connect

    Harmon, Frank; Wells, Douglas P.; Hunt, Alan; Beller, Denis

    2006-12-13

    From FY 02-05 IAC has been a part of the DOE Advanced Fuel Cycle Initiative and its predecessor organization Advanced Accelerator Applications. In the IAC program effort has been divided into three parts; Student Research, Accelerator Driven Nuclear Research and Materials Science. Within the three parts specific research and development activities have been undertaken in Student Research, which supported undergraduate and graduate students, post-docs, engineering staff, program administration, project infrastructure, visiting and summer faculty appointments, visiting scientists, and support of students and faculty at the University of Michigan, Texas A&M University, University of Texas and UNLV; Accelerator Driven Nuclear Research included the use of electron accelerators to study driven sub-critical nuclear systems (ADS) and to provide practical methods of monitoring and assaying nuclear materials for accountancy in non proliferation applications (Materials Accountability and Control, MA&C); and Materials Science research at IAC supported all AFC national technical areas.

  5. RE: Request for Correction, Technical Support Document, Greenhouse Gas Emissions Reporting from the Petroleum and Natural Gas Industry

    EPA Pesticide Factsheets

    The Industrial Energy Consumers of America (IECA) joins the U.S. Chamber of Commerce in its request for correction of information developed by the Environmental Protection Agency (EPA) in a background technical support document titled Greenhouse Gas Emissions Reporting from the Petroleum and Natural Gas Industry

  6. Assessment of DOD and industry networks for Computer-Aided Logistics Support (CALS) telecommunications. Final report

    SciTech Connect

    DeLaura, F.L.; Sharp, S.J.; Clark, R.

    1987-06-01

    The Department of Defense is committed to applying the best in modern technology toward improving the transfer of design, engineering, and manufacturing technical information among weapon-system contractors and DoD organizations. The Military Services, the Defense Logistics Agency (DLA), the Defense Communications Agency (DCA), and industry are undertaking or planning telecommunications support for such transfer. In view of these many and diverse efforts, the Computer Aided Logistics Support (CALS) Steering Group through the CALS Communications Working Group has recognized the need for evaluating them. The report presents an evaluation of CALS-related telecommunications requirements in DoD, the major efforts for automating engineering drawing and technical data repositories, and various intelligent-gateway efforts in each of the Services. The overall direction within each Service for telecommunication support and transitioning to the OSI (Open Systems Interconnection) standards is presented, as well as the status of commercial efforts for defining and implementing the OSI standards and improving long-haul telecommunications support.

  7. ADRIANA project: Identification of research infrastructures for the SFR, within the frame of European industrial initiative for sustainable nuclear fission

    SciTech Connect

    Latge, C.; Gastaldi, O.; Vala, L.; Gerbeth, G.; Homann, C.; Benoit, P.; Papin, J.; Girault, N.; Roelofs, F.; Bucenieks, I.; Paffumi, E.; Ciampichetti, A.

    2012-07-01

    Fast neutron reactors have a large potential as sustainable energy source. In particular, Sodium Fast Reactors (SFR) with a closed fuel cycle and potential for minor actinide burning may allow minimization of volume and heat load of high level waste and provide improved use of natural resources (as compared to only 1% energy recovery in the current once-through fuel cycle, with Thermal Reactors, such as EPR). The coordinating action ADRIANA (Advanced Reactor Initiative And Network Arrangement) has been initiated to set up a network dedicated to the construction and operation of research infrastructures in support of developments for the European Industrial Initiative for sustainable nuclear fission. The Project sets these objectives for the following reactor systems and related technologies: Sodium Fast Reactor (SFR), Lead Fast Reactor (LFR), Gas Fast Reactor (GFR, including very high temperature technologies), Instrumentation, diagnostics and experimental devices, Irradiation facilities and hot laboratories, Zero power reactors. Among the fast reactor systems, the sodium cooled reactor has the most comprehensive technological basis as result of the experience gained from worldwide operation of several experimental, prototype and commercial size reactors, since the forties (see Appendix I). This concept is currently considered as the reference, within the European strategy. Innovations are needed to further enhance safety, reduce capital cost and improve efficiency reliability and operability, making the Generation IV SFR an attractive option for electricity production. Currently, in France, a moderate (500 to 600 MWe) power demonstrator named ASTRID (Advanced Sodium Test Reactor for Industrial Demonstration) has been proposed and endorsed by EU. Presently, the reference configuration is a pool concept. General R and D needs have been identified and experimental facilities required to satisfy these needs have been listed for the following domains: material and

  8. DOE/Industry Matching Grant Program

    SciTech Connect

    John C. Lee

    2003-09-30

    For the academic year 2001-2002, the Department of Nuclear Engineering and Radiological Sciences received $50,000 of industrial contributions, matched by a DOE grant of $35,000. We used the combined DOE/Industry Matching Grant of $85,000 toward (a) undergraduate merit scholarships and research support, (b) graduate student support, and (c) partial support of a research scientist.

  9. Editorial input for the right price: tobacco industry support for a sheet metal indoor air quality manual.

    PubMed

    Campbell, Richard; Balbach, Edith

    2013-01-01

    Following legal action in the 1990s, internal tobacco industry documents became public, allowing unprecedented insight into the industry's relationships with outside organizations. During the 1980s and 1990s, the National Energy Management Institute (NEMI), established by the Sheet Metal Workers International Association and the Sheet Metal and Air Conditioning Contractors' National Association, (SMACNA) received tobacco industry funding to establish an indoor air quality services program. But the arrangement also required NEMI to serve as an advocate for industry efforts to defeat indoor smoking bans by arguing that ventilation was a more appropriate solution to environmental tobacco smoke. Drawing on tobacco industry documents, this paper describes a striking example of the ethical compromises that accompanied NEMI's collaboration with the tobacco industry, highlighting the solicitation of tobacco industry financial support for a SMACNA indoor air quality manual in exchange for sanitizing references to the health impact of environmental tobacco smoke prior to publication.

  10. Modular assembly for supporting, straining, and directing flow to a core in a nuclear reactor

    DOEpatents

    Pennell, William E.

    1977-01-01

    A reactor core support arrangement for supporting, straining, and providing fluid flow to the core and periphery of a nuclear reactor during normal operation. A plurality of removable inlet modular units are contained within permanent liners in the lower supporting plate of the reactor vessel lower internals. During normal operation (1) each inlet modular unit directs main coolant flow to a plurality of core assemblies, the latter being removably supported in receptacles in the upper portion of the modular unit and (2) each inlet modular unit may direct bypass flow to a low pressure annular region of the reactor vessel. Each inlet modular unit may include special fluid seals interposed between mating surfaces of the inlet modular units and the core assemblies and between the inlet modular units and the liners, to minimize leakage and achieve an hydraulic balance. Utilizing the hydraulic balance, the modular units are held in the liners and the assemblies are held in the modular unit receptacles by their own respective weight. Included as part of the permanent liners below the horizontal support plate are generally hexagonal axial debris barriers. The axial debris barriers collectively form a bottom boundary of a secondary high pressure plenum, the upper boundary of which is the bottom surface of the horizontal support plate. Peripheral liners include radial debris barriers which collectively form a barrier against debris entry radially. During normal operation primary coolant inlet openings in the liner, below the axial debris barriers, pass a large amount of coolant into the inlet modular units, and secondary coolant inlet openings in the portion of the liners within the secondary plenum pass a small amount of coolant into the inlet modular units. The secondary coolant inlet openings also provide alternative coolant inlet flow paths in the unlikely event of blockage of the primary inlet openings. The primary inlet openings have characteristics which limit the

  11. The Bavarian Model? Modernization, Environment, and Landscape Planning in the Bavarian Nuclear Power Industry, 1950--1980

    NASA Astrophysics Data System (ADS)

    Miller, Russell Lowell

    Perhaps no state in the Federal Republic of Germany witnessed a more pronounced state sponsored modernization effort than Bavaria, 1950-1980. This vast transformation, particularly in the field of nuclear energy, required a continuous negotiation of landscape planning between state officials, scientists, and ordinary citizens. While ordinary Bavarians had little input in the technical or scientific aspects of the nuclear industry, they could shape the landscape policy, by offering environmental and cultural criticism on specific locations for reactors. Using material from the Bavarian State Archives (some, from the 1970s, only recently declassified), this dissertation compares the Bavarian landscape disputes over nuclear facilities in the nineteen-fifties with those featured in the widespread anti-nuclear demonstrations of the nineteen-seventies. As one of the few English language studies on the topic, this dissertation suggests considerably more continuity in landscape disputes than previous scholarship and offers a fresh look into the migration of skepticism towards the landscape use of nuclear power from political right to left over the course of thirty years.

  12. Final Technical Report; NUCLEAR ENGINEERING RECRUITMENT EFFORT

    SciTech Connect

    Kerrick, Sharon S.; Vincent, Charles D.

    2007-07-02

    This report provides the summary of a project whose purpose was to support the costs of developing a nuclear engineering awareness program, an instruction program for teachers to integrate lessons on nuclear science and technology into their existing curricula, and web sites for the exchange of nuclear engineering career information and classroom materials. The specific objectives of the program were as follows: OBJECTIVE 1: INCREASE AWARENESS AND INTEREST OF NUCLEAR ENGINEERING; OBJECTIVE 2: INSTRUCT TEACHERS ON NUCLEAR TOPICS; OBJECTIVE 3: NUCLEAR EDUCATION PROGRAMS WEB-SITE; OBJECTIVE 4: SUPPORT TO UNIVERSITY/INDUSTRY MATCHING GRANTS AND REACTOR SHARING; OBJECTIVE 5: PILOT PROJECT; OBJECTIVE 6: NUCLEAR ENGINEERING ENROLLMENT SURVEY AT UNIVERSITIES

  13. The nuclear power industry in the United States: status and projections.

    PubMed

    Connolly, T J

    1988-01-01

    One sixth of the electricity in the United States is now being generated in nuclear power plants, a remarkable achievement for a technology whose basic nuclear reaction was not even known 50 years ago. On the other hand, many of the nation's electric utilities are experiencing great difficulties completing the construction of their nuclear plants; 41 partially constructed plants have been abandoned. Those abandoned plants plus about 110 in operation and 15 still to be completed comprise the first generation of nuclear power plants in the United States. When, and even if, there will be a second generation is much in doubt. Data are presented to show that the absence of a second generation of nuclear plants will place large demands on the fossil fuels, with attendant high energy prices and high environmental costs the expected outcome. It appears that the future will bring large economic forces to start new orders for nuclear plants. On the other hand, the opposing institutional forces appear equally strong. Among the problems creating these institutional forces are the difficulty the United States is having in finding a politically acceptable approach to nuclear waste disposal and the vulnerability of power plant builders and operators to litigation and high financial risk. At present, the issue of a second generation of nuclear plants is stalemated.

  14. Sandia National Laboratories support of the Iraq Nuclear Facility Dismantlement and Disposal Program.

    SciTech Connect

    Cochran, John Russell; Danneels, Jeffrey John

    2009-03-01

    Because of past military operations, lack of upkeep and looting there are now enormous radioactive waste problems in Iraq. These waste problems include destroyed nuclear facilities, uncharacterized radioactive wastes, liquid radioactive waste in underground tanks, wastes related to the production of yellow cake, sealed radioactive sources, activated metals and contaminated metals that must be constantly guarded. Iraq currently lacks the trained personnel, regulatory and physical infrastructure to safely and securely manage these facilities and wastes. In 2005 the International Atomic Energy Agency (IAEA) agreed to organize an international cooperative program to assist Iraq with these issues. Soon after, the Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) was initiated by the U.S. Department of State (DOS) to support the IAEA and assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials. The Iraq NDs Program is providing support for the IAEA plus training, consultation and limited equipment to the GOI. The GOI owns the problems and will be responsible for implementation of the Iraq NDs Program. Sandia National Laboratories (Sandia) is a part of the DOS's team implementing the Iraq NDs Program. This report documents Sandia's support of the Iraq NDs Program, which has developed into three principal work streams: (1) training and technical consultation; (2) introducing Iraqis to modern decommissioning and waste management practices; and (3) supporting the IAEA, as they assist the GOI. Examples of each of these work streams include: (1) presentation of a three-day training workshop on 'Practical Concepts for Safe Disposal of Low-Level Radioactive Waste in Arid Settings;' (2) leading GOI representatives on a tour of two operating low level radioactive waste disposal facilities in the U.S.; and (3) supporting the IAEA's Technical Meeting with the GOI from April 21-25, 2008. As noted in the

  15. The Impacts of Military, Industrial, and Private Support on Modern Astronomy

    NASA Astrophysics Data System (ADS)

    Harwit, Martin

    2015-01-01

    In contrast to the period following WW I, governmental support for astronomy grew enormously after WWII and during the Cold War. In spite of reservations expressed by leading astronomers like Harlow Shapley at Harvard and Otto Struve at Yerkes, tools provided by the military took astronomy into directions neither Shapley nor Struve could possibly have imagined — radio, X-ray, gamma-ray and infrared astronomy. It was a great ride that lasted half a century. Had it been up to Shapley and Struve, they would have opted for a return to where pre-war optical astronomy had left off — themes over which they could exert personal control.The problem today, however, as I will show, is that the directions the military supported, while still fruitful, may be keeping us from vigorously pursuing new problems astrophysics needs to consider, the nature of dark energy and dark matter, or the pursuit of intelligent life elsewhere in the universe, none of which appear of interest to the military or industry. Topics of this kind could be supported by the very rich, like Yerkes and Hooker in the past, the Keck Foundation and Paul Allen more recently, or by less affluent but highly skilled volunteers. Support by the wealthy has occasionally been questioned, as in a front page article by William Broad in the International New York Times on March 17, 2014, in which he worried that the ultrarich would likely be idiosyncratic and know too little. Whether this fear is justified can be debated. However, failing this kind of philanthropic support, astronomy might opt for aid through the recently developed "economy of the commons,' pioneered by Elinor Ostrom, which tends to succeed by world-wide support on smaller scales coordinated largely through the internet. This movement is sometimes referred to as crowd sourcing. It tends to attract thoughtful, like-minded individuals from across the globe who wish to contribute their skills and have the required talents.I will review both the great

  16. Gap Analysis to Support Modeling the Long-Term Degradation of Used Nuclear Fuel Canisters

    SciTech Connect

    Jensen, Philip J.; Sunderland, Dion J.; Ross, Steven B.; Montgomery, Robert O.; Hanson, Brady D.; Devanathan, Ram

    2015-04-01

    Welded stainless steel canisters are being used worldwide for dry storage of used nuclear fuel (UNF) assemblies, and the number of canisters in use is steadily increasing. In support of work currently being pursued at Pacific Northwest National Laboratory to understand the atmospheric corrosion behavior of spent fuel dry storage systems, a gap analysis is underway to assess the state of knowledge for modeling of the long-term degradation of a UNF canister. The fundamental aim of this work is to inform research and development (R&D) efforts to establish a sound technical basis to support the extended dry storage of UNF for 100+ years. The analysis is considering all major components of the atmosphere corrosion degradation processes, ranging from contaminant sources and climatic interactions to regional conditions of particle transport and deposition, to microscale effects leading to stress corrosion cracking. The results of this gap analysis will be used to define the R&D pathway to develop an integrated multi-scale atmospheric corrosion modeling capability for UNF in dry storage canisters that can support the safe and reliable performance of these structures for more than 100 years.

  17. Calculating Relative Ionization Probabilities of Plutonium for Resonance Ionization Mass Spectrometry to Support Nuclear Forensic Investigations

    NASA Astrophysics Data System (ADS)

    Lensegrav, Craig; Smith, Craig; Isselhardt, Brett

    2015-03-01

    Ongoing work seeks to apply the technology of Resonance Ionization Mass Spectrometry (RIMS) to problems related to nuclear forensics and, in particular, to the analysis and quantification of debris from nuclear detonations. As part of this effort, modeling and simulation methods are being applied to analyze and predict the potential for ionization by laser excitation of isotopes of both uranium and plutonium. Early work focused on the ionization potential of isotopes of uranium, and the present effort has expanded and extended the previous work by identifying and integrating new data for plutonium isotopes. In addition to extending the effort to this important new element, we have implemented more accurate descriptions of the spatial distribution of the laser beams to improve the accuracy of model predictions compared with experiment results as well as an ability to readily incorporate new experimental data as they become available. The model is used to estimate ionization cross sections and to compare relative excitation on two isotopes as a function of wavelength. This allows the study of sensitivity of these measurements to fluctuations in laser wavelength, irradiance, and bandwidth. We also report on initial efforts to include predictions of americium ionization probabilities into our modeling package. I would like to thank my co-authors, Gamani Karunasiri and Fabio Alves. My success is a product of their support and guidance.

  18. Design of a professional development and support program for future photonics industry team leaders

    NASA Astrophysics Data System (ADS)

    Hall-Wallace, Michelle; Regens, Nancy L.; Pompea, Stephen M.

    2002-05-01

    The University of Arizona's Collaboration to Advance Teaching Technology and Science (CATTS) program sponsored by the National Science Foundation has found a successful way to unite public and charter school students and teachers, university science outreach programs, graduate and undergraduate students, and university faculty for the betterment of science education. A key aspect of this success has been the ability of the project to assist stakeholders in understanding the different cultural perspectives of all of the participants. The success of this program has led us to create a template for a professional development and support program emphasizing the degree of cross-cultural understanding appropriate for today's multinational photonics industry. This template is designed to give future photonics technical, managerial, and manufacturing leaders training in a variety of areas that can enhance their productivity and ability to lead teams. The design would be appropriate for photonics research and development teams, sales and marketing teams, teams with diverse members new college hires, and newly emplaced managers. This education template would also be appropriate for students in photonics industry technician and graduate- level programs. This type of program is not a substitute for other forms of professional managerial training, but rather augments such programs with material that can aid in a more global perspective.

  19. Cooperative measures to support the Indo-Pak Agreement Reducing Risk from Accidents Relating to Nuclear Weapons.

    SciTech Connect

    Mishra, Sitakanta; Ahmed, Mansoor

    2014-04-01

    In 2012, India and Pakistan reaffirmed the Agreement on Reducing the Risk from Accidents Relating to Nuclear Weapons. Despite a history of mutual animosity and persistent conflict between the two countries, this agreement derives strength from a few successful nuclear confidence building measures that have stood the test of time. It also rests on the hope that the region would be spared a nuclear holocaust from an accidental nuclear weapon detonation that might be misconstrued as a deliberate use of a weapon by the other side. This study brings together two emerging strategic analysts from South Asia to explore measures to support the Agreement and further develop cooperation around this critical issue. This study briefly dwells upon the strategic landscape of nuclear South Asia with the respective nuclear force management structures, doctrines, and postures of India and Pakistan. It outlines the measures in place for the physical protection and safety of nuclear warheads, nuclear materials, and command and control mechanisms in the two countries, and it goes on to identify the prominent, emerging challenges posed by the introduction of new weapon technologies and modernization of the respective strategic forces. This is followed by an analysis of the agreement itself leading up to a proposed framework for cooperative measures that might enhance the spirit and implementation of the agreement.

  20. Fire simulation in nuclear facilities: the FIRAC code and supporting experiments

    SciTech Connect

    Burkett, M.W.; Martin, R.A.; Fenton, D.L.; Gunaji, M.V.

    1984-01-01

    The fire accident analysis computer code FIRAC was designed to estimate radioactive and nonradioactive source terms and predict fire-induced flows and thermal and material transport within the ventilation systems of nuclear fuel cycle facilities. FIRAC maintains its basic structure and features and has been expanded and modified to include the capabilities of the zone-type compartment fire model computer code FIRIN developed by Battelle Pacific Northwest Laboratory. The two codes have been coupled to provide an improved simulation of a fire-induced transient within a facility. The basic material transport capability of FIRAC has been retained and includes estimates of entrainment, convection, deposition, and filtration of material. The interrelated effects of filter plugging, heat transfer, gas dynamics, material transport, and fire and radioactive source terms also can be simulated. Also, a sample calculation has been performed to illustrate some of the capabilities of the code and how a typical facility is modeled with FIRAC. In addition to the analytical work being performed at Los Alamos, experiments are being conducted at the New Mexico State University to support the FIRAC computer code development and verification. This paper summarizes two areas of the experimental work that support the material transport capabiities of the code: the plugging of high-efficiency particulate air (HEPA) filters by combustion aerosols and the transport and deposition of smoke in ventilation system ductwork.

  1. Maintenance approaches and practices in selected foreign nuclear power programs and other US industries: Review and lessons learned

    SciTech Connect

    Not Available

    1990-04-01

    The Commission published a Notice of Proposed Rule-making on Maintenance of Nuclear Power Plants on November 28, 1988, spelling out NRC's expectations in maintenance. In preparing the proposed rule, the NRC reviewed maintenance practices in other countries and considered maintenance approaches in other industries in this country. As a result of the review of maintenance practices, it was concluded that certain practices in the following areas have been found to contribute significantly to effective maintenance: (1) systems approach; (2) effectiveness monitoring; (3) technician qualifications and motivation; and (4) maintenance organization. 87 refs., 26 figs., 2 tabs.

  2. Industry

    SciTech Connect

    Bernstein, Lenny; Roy, Joyashree; Delhotal, K. Casey; Harnisch, Jochen; Matsuhashi, Ryuji; Price, Lynn; Tanaka, Kanako; Worrell, Ernst; Yamba, Francis; Fengqi, Zhou; de la Rue du Can, Stephane; Gielen, Dolf; Joosen, Suzanne; Konar, Manaswita; Matysek, Anna; Miner, Reid; Okazaki, Teruo; Sanders, Johan; Sheinbaum Parado, Claudia

    2007-12-01

    This chapter addresses past, ongoing, and short (to 2010) and medium-term (to 2030) future actions that can be taken to mitigate GHG emissions from the manufacturing and process industries. Globally, and in most countries, CO{sub 2} accounts for more than 90% of CO{sub 2}-eq GHG emissions from the industrial sector (Price et al., 2006; US EPA, 2006b). These CO{sub 2} emissions arise from three sources: (1) the use of fossil fuels for energy, either directly by industry for heat and power generation or indirectly in the generation of purchased electricity and steam; (2) non-energy uses of fossil fuels in chemical processing and metal smelting; and (3) non-fossil fuel sources, for example cement and lime manufacture. Industrial processes also emit other GHGs, e.g.: (1) Nitrous oxide (N{sub 2}O) is emitted as a byproduct of adipic acid, nitric acid and caprolactam production; (2) HFC-23 is emitted as a byproduct of HCFC-22 production, a refrigerant, and also used in fluoroplastics manufacture; (3) Perfluorocarbons (PFCs) are emitted as byproducts of aluminium smelting and in semiconductor manufacture; (4) Sulphur hexafluoride (SF{sub 6}) is emitted in the manufacture, use and, decommissioning of gas insulated electrical switchgear, during the production of flat screen panels and semiconductors, from magnesium die casting and other industrial applications; (5) Methane (CH{sub 4}) is emitted as a byproduct of some chemical processes; and (6) CH{sub 4} and N{sub 2}O can be emitted by food industry waste streams. Many GHG emission mitigation options have been developed for the industrial sector. They fall into three categories: operating procedures, sector-wide technologies and process-specific technologies. A sampling of these options is discussed in Sections 7.2-7.4. The short- and medium-term potential for and cost of all classes of options are discussed in Section 7.5, barriers to the application of these options are addressed in Section 7.6 and the implication of

  3. ENGINEERED NEAR SURFACE DISPOSAL FACILITY OF THE INDUSTRIAL COMPLEX FOR SOLID RADWASTE MANAGEMENT AT CHERNOBYL NUCLEAR POWER PLANT

    SciTech Connect

    Ziehm, Ronny; Pichurin, Sergey Grigorevich

    2003-02-27

    As a part of the turnkey project ''Industrial Complex for Solid Radwaste Management (ICSRM) at the Chernobyl Nuclear Power Plant (ChNPP)'' an Engineered Near Surface Disposal Facility (ENSDF, LOT 3) will be built on the VEKTOR site within the 30 km Exclusion Zone of the ChNPP. This will be performed by RWE NUKEM GmbH, Germany, and it governs the design, licensing support, fabrication, assembly, testing, inspection, delivery, erection, installation and commissioning of the ENSDF. The ENSDF will receive low to intermediate level, short lived, processed/conditioned wastes from the ICSRM Solid Waste Processing Facility (SWPF, LOT 2), the ChNPP Liquid Radwaste Treatment Plant (LRTP) and the ChNPP Interim Storage Facility for RBMK Fuel Assemblies (ISF). The ENSDF has a capacity of 55,000 m{sup 3}. The primary functions of the ENSDF are: to receive, monitor and record waste packages, to load the waste packages into concrete disposal units, to enable capping and closure of the disposal unit s, to allow monitoring following closure. The ENSDF comprises the turnkey installation of a near surface repository in the form of an engineered facility for the final disposal of LILW-SL conditioned in the ICSRM SWPF and other sources of Chernobyl waste. The project has to deal with the challenges of the Chernobyl environment, the fulfillment of both Western and Ukrainian standards, and the installation and coordination of an international project team. It will be shown that proven technologies and processes can be assembled into a unique Management Concept dealing with all the necessary demands and requirements of a turnkey project. The paper emphasizes the proposed concepts for the ENSDF and their integration into existing infrastructure and installations of the VEKTOR site. Further, the paper will consider the integration of Western and Ukrainian Organizations into a cohesive project team and the requirement to guarantee the fulfillment of both Western standards and Ukrainian

  4. DOE Spent Nuclear Fuel Information In Support of TSPA-VA

    SciTech Connect

    A. Brewer; D. Cresap; D. Fillmore; H. Loo; M. Ebner; R. McCormack

    1998-09-01

    RW has started the viability assessment (VA) effort to determine the feasibility of Yucca Mountain as the first geologic repository for spent nuclear fuel (SNF) and high-level waste. One component of the viability assessment will be a total system performance assessment (TSPA), based on the design concept and the scientific data and analysis available, describing the repository's probable behavior relative to the overall system performance standards. Thus, all the data collected from the Exploratory Studies Facility to-date have been incorporated into the latest TSPA model. In addition, the Repository Integration Program, an integrated probabilistic simulator, used in the TSPA has also been updated by Golder Associates Incorporated at December 1997. To ensure that the Department of Energy-owned (DOE-owned) SNF continues to be acceptable for disposal in the repository, it will be included in the TSPA-VA evaluation. A number of parameters are needed in the TSPA-VA models to predict the performance of the DOE-owned SNF materials placed into the potential repository. This report documents all of the basis and/or derivation for each of these parameters. A number of properties were not readily available at the time the TSPA-VA data was requested. Thus, expert judgement and opinion was utilized to determine a best property value. The performance of the DOE-owned SNF will be published as part of the TSPA-VA report. Each DOE site will be collecting better data as the DOE SNF program moves closer to repository license application. As required by the RW-0333P, the National Spent Nuclear Fuel Program will be assisting each site in qualifying the information used to support the performance assessment evaluations.

  5. Ethics for environmental health research: the case of the U.S. Nuclear weapons industry.

    PubMed

    Wing, Steve

    2010-01-01

    Exploitation of workers and communities based on class and race has profoundly influenced occupational and environmental health. During production and testing of nuclear weapons in the United States, class and race have affected exposures to radiation and other hazards as well as protection programs and monitoring of exposures. This situation has contributed to health disparities and has hindered advancement of research into the health effects of ionizing radiation and other exposures from nuclear weapons production. Organizing by workers and affected communities can bring about a better understanding of the health effects of ionizing radiation as well as more ethical research practices.

  6. The Nuclear Fuel Services, Inc. program to support disposition of enriched uranium-bearing materials

    SciTech Connect

    Schutt, Stephen M.; Jacob, Norman P.

    2007-07-01

    The disposition of surplus nuclear materials has become one of the most pressing issues of our time. Numerous agencies have invoked programs with the purpose of removing such materials from various international venues and disposing these materials in a manner that achieves non-proliferability. This paper describes the Nuclear Fuel Services, Inc (NFS) Nuclear Material Disposition Program, which to date has focused on a variety of Special Nuclear Material (SNM), in particular uranium of various enrichments. The major components of this program are discussed, with emphasis on recycle and return of material to the nuclear fuel cycle. (authors)

  7. The virtual digital nuclear power plant: A modern tool for supporting the lifecycle of VVER-based nuclear power units

    NASA Astrophysics Data System (ADS)

    Arkadov, G. V.; Zhukavin, A. P.; Kroshilin, A. E.; Parshikov, I. A.; Solov'ev, S. L.; Shishov, A. V.

    2014-10-01

    The article describes the "Virtual Digital VVER-Based Nuclear Power Plant" computerized system comprising a totality of verified initial data (sets of input data for a model intended for describing the behavior of nuclear power plant (NPP) systems in design and emergency modes of their operation) and a unified system of new-generation computation codes intended for carrying out coordinated computation of the variety of physical processes in the reactor core and NPP equipment. Experiments with the demonstration version of the "Virtual Digital VVER-Based NPP" computerized system has shown that it is in principle possible to set up a unified system of computation codes in a common software environment for carrying out interconnected calculations of various physical phenomena at NPPs constructed according to the standard AES-2006 project. With the full-scale version of the "Virtual Digital VVER-Based NPP" computerized system put in operation, the concerned engineering, design, construction, and operating organizations will have access to all necessary information relating to the NPP power unit project throughout its entire lifecycle. The domestically developed commercial-grade software product set to operate as an independently operating application to the project will bring about additional competitive advantages in the modern market of nuclear power technologies.

  8. Supported noble metal catalysts in the catalytic wet air oxidation of industrial wastewaters and sewage sludges.

    PubMed

    Besson, M; Descorme, C; Bernardi, M; Gallezot, P; di Gregorio, F; Grosjean, N; Minh, D Pham; Pintar, A

    2010-12-01

    This paper reviews some catalytic wet air oxidation (CWAO) investigations of industrial wastewaters over platinum and ruthenium catalysts supported on TiO2 and ZrO2 formulated to be active and resistant to leaching, with particular focus on the stability of the catalyst. Catalyst recycling experiments were performed in batch reactors and long-term stability tests were conducted in trickle-bed reactors. The catalyst did not leach upon treatment of Kraft bleaching plant and olive oil mill effluents, and could be either recycled or used for long periods of time in continuous reactors. Conversely, these catalysts were rapidly leached when used to treat effluents from the production of polymeric membranes containing N,N-dimethylformamide. The intermediate formation of amines, such as dimethylamine and methylamine with a high complexing capacity for the metal, was shown to be responsible for the metal leaching. These heterogeneous catalysts also deactivated upon CWAO of sewage sludges due to the adsorption of the solid organic matter. Pre-sonication of the sludge to disintegrate the flocs and improve solubility was inefficient.

  9. Industrial-hygiene survey report of Defense Fuel Support Point, Cincinnati, Ohio

    SciTech Connect

    Piacitelli, G.; Krishnan, R.

    1989-03-09

    As part of a study of worker exposure, personal protective equipment, and engineering controls in use in work areas where exposure to ethylene glycol ethers is possible, an industrial hygiene survey was conducted at the Defense Fuel Support Point, Cincinnati, Ohio. The activities include receiving, storing, and distributing of jet fuel for military use. At the site, 2-methoxyethanol (2-ME) was added as an icing inhibitor to one of the jet fuels. JP-4 contained 0.10 to 0.15 wt.% of 2-ME and JP-5 contained diethylene-glycol-monomethyl-ether (DEGME) at a concentration of 0.15 to 0.20 wt.% received at the location for shipment elsewhere. The potential existed for inhalation and dermal exposure to 2-ME. Exposure controls included the use of engineering controls at the truck-loading operation and quality control analysis divisions and the wearing of personal protective equipment. Monitoring indicated that full-shift inhalation exposures to 2-ME were low, less than 0.34 part per million (ppm). Short-term exposures occasionally reached 6.86 ppm. Due to the small number of workers with a potential of exposure to glygol ethers, the facility should not be included in additional health studies. Specific recommendations are made for work practices, ventilation and personal protective equipment.

  10. Resolution of Brassicaceae Phylogeny Using Nuclear Genes Uncovers Nested Radiations and Supports Convergent Morphological Evolution.

    PubMed

    Huang, Chien-Hsun; Sun, Renran; Hu, Yi; Zeng, Liping; Zhang, Ning; Cai, Liming; Zhang, Qiang; Koch, Marcus A; Al-Shehbaz, Ihsan; Edger, Patrick P; Pires, J Chris; Tan, Dun-Yan; Zhong, Yang; Ma, Hong

    2016-02-01

    Brassicaceae is one of the most diverse and economically valuable angiosperm families with widely cultivated vegetable crops and scientifically important model plants, such as Arabidopsis thaliana. The evolutionary history, ecological, morphological, and genetic diversity, and abundant resources and knowledge of Brassicaceae make it an excellent model family for evolutionary studies. Recent phylogenetic analyses of the family revealed three major lineages (I, II, and III), but relationships among and within these lineages remain largely unclear. Here, we present a highly supported phylogeny with six major clades using nuclear markers from newly sequenced transcriptomes of 32 Brassicaceae species and large data sets from additional taxa for a total of 55 species spanning 29 out of 51 tribes. Clade A consisting of Lineage I and Macropodium nivale is sister to combined Clade B (with Lineage II and others) and a new Clade C. The ABC clade is sister to Clade D with species previously weakly associated with Lineage II and Clade E (Lineage III) is sister to the ABCD clade. Clade F (the tribe Aethionemeae) is sister to the remainder of the entire family. Molecular clock estimation reveals an early radiation of major clades near or shortly after the Eocene-Oligocene boundary and subsequent nested divergences of several tribes of the previously polytomous Expanded Lineage II. Reconstruction of ancestral morphological states during the Brassicaceae evolution indicates prevalent parallel (convergent) evolution of several traits over deep times across the entire family. These results form a foundation for future evolutionary analyses of structures and functions across Brassicaceae.

  11. Resolution of Brassicaceae Phylogeny Using Nuclear Genes Uncovers Nested Radiations and Supports Convergent Morphological Evolution

    PubMed Central

    Huang, Chien-Hsun; Sun, Renran; Hu, Yi; Zeng, Liping; Zhang, Ning; Cai, Liming; Zhang, Qiang; Koch, Marcus A.; Al-Shehbaz, Ihsan; Edger, Patrick P.; Pires, J. Chris; Tan, Dun-Yan; Zhong, Yang; Ma, Hong

    2016-01-01

    Brassicaceae is one of the most diverse and economically valuable angiosperm families with widely cultivated vegetable crops and scientifically important model plants, such as Arabidopsis thaliana. The evolutionary history, ecological, morphological, and genetic diversity, and abundant resources and knowledge of Brassicaceae make it an excellent model family for evolutionary studies. Recent phylogenetic analyses of the family revealed three major lineages (I, II, and III), but relationships among and within these lineages remain largely unclear. Here, we present a highly supported phylogeny with six major clades using nuclear markers from newly sequenced transcriptomes of 32 Brassicaceae species and large data sets from additional taxa for a total of 55 species spanning 29 out of 51 tribes. Clade A consisting of Lineage I and Macropodium nivale is sister to combined Clade B (with Lineage II and others) and a new Clade C. The ABC clade is sister to Clade D with species previously weakly associated with Lineage II and Clade E (Lineage III) is sister to the ABCD clade. Clade F (the tribe Aethionemeae) is sister to the remainder of the entire family. Molecular clock estimation reveals an early radiation of major clades near or shortly after the Eocene–Oligocene boundary and subsequent nested divergences of several tribes of the previously polytomous Expanded Lineage II. Reconstruction of ancestral morphological states during the Brassicaceae evolution indicates prevalent parallel (convergent) evolution of several traits over deep times across the entire family. These results form a foundation for future evolutionary analyses of structures and functions across Brassicaceae. PMID:26516094

  12. Predictive based monitoring of nuclear plant component degradation using support vector regression

    SciTech Connect

    Agarwal, Vivek; Alamaniotis, Miltiadis; Tsoukalas, Lefteri H.

    2015-02-01

    Nuclear power plants (NPPs) are large installations comprised of many active and passive assets. Degradation monitoring of all these assets is expensive (labor cost) and highly demanding task. In this paper a framework based on Support Vector Regression (SVR) for online surveillance of critical parameter degradation of NPP components is proposed. In this case, on time replacement or maintenance of components will prevent potential plant malfunctions, and reduce the overall operational cost. In the current work, we apply SVR equipped with a Gaussian kernel function to monitor components. Monitoring includes the one-step-ahead prediction of the component’s respective operational quantity using the SVR model, while the SVR model is trained using a set of previous recorded degradation histories of similar components. Predictive capability of the model is evaluated upon arrival of a sensor measurement, which is compared to the component failure threshold. A maintenance decision is based on a fuzzy inference system that utilizes three parameters: (i) prediction evaluation in the previous steps, (ii) predicted value of the current step, (iii) and difference of current predicted value with components failure thresholds. The proposed framework will be tested on turbine blade degradation data.

  13. Nuclear Fabrication Consortium

    SciTech Connect

    Levesque, Stephen

    2013-04-05

    This report summarizes the activities undertaken by EWI while under contract from the Department of Energy (DOE) Office of Nuclear Energy (NE) for the management and operation of the Nuclear Fabrication Consortium (NFC). The NFC was established by EWI to independently develop, evaluate, and deploy fabrication approaches and data that support the re-establishment of the U.S. nuclear industry: ensuring that the supply chain will be competitive on a global stage, enabling more cost-effective and reliable nuclear power in a carbon constrained environment. The NFC provided a forum for member original equipment manufactures (OEM), fabricators, manufacturers, and materials suppliers to effectively engage with each other and rebuild the capacity of this supply chain by : Identifying and removing impediments to the implementation of new construction and fabrication techniques and approaches for nuclear equipment, including system components and nuclear plants. Providing and facilitating detailed scientific-based studies on new approaches and technologies that will have positive impacts on the cost of building of nuclear plants. Analyzing and disseminating information about future nuclear fabrication technologies and how they could impact the North American and the International Nuclear Marketplace. Facilitating dialog and initiate alignment among fabricators, owners, trade associations, and government agencies. Supporting industry in helping to create a larger qualified nuclear supplier network. Acting as an unbiased technology resource to evaluate, develop, and demonstrate new manufacturing technologies. Creating welder and inspector training programs to help enable the necessary workforce for the upcoming construction work. Serving as a focal point for technology, policy, and politically interested parties to share ideas and concepts associated with fabrication across the nuclear industry. The report the objectives and summaries of the Nuclear Fabrication Consortium

  14. 40 YEARS OF EXPERIENCE WITH LIQUID-LIQUID EXTRACTION EQUIPMENT IN THE NUCLEAR INDUSTRY

    SciTech Connect

    Drain, F.; Vinoche, R.; Duhamet, J.

    2003-02-27

    Three types of liquid-liquid extraction equipment are used in industrial reprocessing plants. Each is described below, with a special focus on pulsed columns and centrifugal extractors, which have been the subject of an extensive R&D program by the French Atomic Energy Commission (CEA). Various models have been developed to simulate equipment behavior and flowsheets. The excellent results obtained during industrial operation of the UP3 and UP2-800 plants in La Hague have confirmed the validity of the choices made during the design phases and pave the way for future improvement of the reprocessing process, from a technical and a financial standpoint.

  15. Nuclear Fuels.

    ERIC Educational Resources Information Center

    Nash, J. Thomas

    1983-01-01

    Trends in and factors related to the nuclear industry and nuclear fuel production are discussed. Topics addressed include nuclear reactors, survival of the U.S. uranium industry, production costs, budget cuts by the Department of Energy and U.S. Geological survey for resource studies, mining, and research/development activities. (JN)

  16. 78 FR 56719 - Draft Guidance for Industry on Arsenic in Apple Juice: Action Level; Supporting Document for...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-13

    ... HUMAN SERVICES Food and Drug Administration Draft Guidance for Industry on Arsenic in Apple Juice: Action Level; Supporting Document for Action Level for Arsenic in Apple Juice; A Quantitative Assessment of Inorganic Arsenic in Apple Juice; Extension of Comment Period AGENCY: Food and Drug...

  17. 78 FR 42086 - Draft Guidance for Industry on Arsenic in Apple Juice: Action Level; Supporting Document for...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-15

    ... HUMAN SERVICES Food and Drug Administration Draft Guidance for Industry on Arsenic in Apple Juice: Action Level; Supporting Document for Action Level for Arsenic in Apple Juice; A Quantitative Assessment of Inorganic Arsenic in Apple Juice; Availability AGENCY: Food and Drug Administration, HHS....

  18. Noble Gas Migration Experiment to Support the Detection of Underground Nuclear Explosions

    SciTech Connect

    Olsen, Khris B.; Kirkham, Randy R.; Woods, Vincent T.; Haas, Derek A.; Hayes, James C.; Bowyer, Ted W.; Mendoza, Donaldo P.; Lowrey, Justin D.; Lukins, Craig D.; Suarez, Reynold; Humble, Paul H.; Ellefson, Mark D.; Ripplinger, Mike D.; Zhong, Lirong; Mitroshkov, Alexandre V.; Aalseth, Craig E.; Prinke, Amanda M.; Mace, Emily K.; McIntyre, Justin I.; Stewart, Timothy L.; Mackley, Rob D.; Milbrath, Brian D.; Emer, Dudley; Biegalski, S.

    2016-03-01

    A Noble Gas Migration Experiment (NGME) funded by the National Center for Nuclear Security and conducted at the Nevada National Security Site (NNSS) in collaboration with Lawrence Livermore national Laboratory and National Security Technology provided critical on-site inspection (OSI) information related to the detection of an underground nuclear explosion (UNE) event using noble gas signatures.

  19. Watermelons Not War! A Support Book for Parenting in the Nuclear Age.

    ERIC Educational Resources Information Center

    Cloud, Kate; And Others

    The Nuclear Education Project (NEP), a group of five women concerned about parenting in a nuclear age, developed this guide to help parents and others develop a sense of hope and promote a greater involvement in the democratic political process. Chapter I, "The Heart of the Matter," presents sections on answering possible questions children might…

  20. Carbon-supported platinum alloy catalysts for phenol hydrogenation for making industrial chemicals

    SciTech Connect

    Srinivas, S.T.; Song, C.

    1999-07-01

    Phenol is available in large quantities in liquids derived from coal and biomass. Phenol hydrogenation is an industrially important reaction to produce cyclohexanone and cyclohexanol. Cyclohexane, cyclohexene and benzene are obtained as minor products in this reaction. Cyclohexanone is an important intermediate in the production of caprolactam for nylon 6 and cyclohexanol for adipic acid production. In USA, cyclohexanol and cyclohexanone are produced by benzene hydrogenation to cyclohexane over nickel or noble metal catalysts, followed by oxidation of cyclohexane to produce a mixture of cyclohexanol and cyclohexanone. Then cyclohexanol is dehydrogenated in the presence of Cu-Zn catalyst to cyclohexanone. Usually phenol hydrogenation is also carried out by using Ni catalyst in liquid phase. However, a direct single-step vapor phase hydrogenation of phenol to give cyclohexanone selectively is more advantageous in terms of energy savings and process economics, since processing is simplified and the endothermic step of cyclohexanol dehydrogenation can be avoided, as demonstrated by Montedipe and Johnson Matthey using promoted Pd/Al{sub 2}O{sub 3} catalyst. While it is not the purpose of this paper to dwell on the relative merits of these routes, it is necessary to mention that while using monometallic catalysts, generally the problem of catalyst deactivation of sintering as well as coking is frequently encountered. Addition and alloying of noble metal (e.g. Pt) with a second metal can result in a catalyst with better selectivity and activity in the reaction which is more resistant to deactivation. This paper presents the results on the single-step vapor phase hydrogenation of phenol over carbon-supported Pt-M (M=Cr, V, Zr) alloy catalysts to yield mainly cyclohexanone or cyclohexanol.

  1. Modeling and Simulation Approaches to Developing Human Performance Measures in Nuclear Industry

    SciTech Connect

    Bruce P. Hallbert; Jeffrey C. Joe; Molly J. Keefe; Julius J. Persensky

    2007-08-01

    Human performance is a key component to the safe operation of nuclear power plants. Further, human performance is quite variable, and while some variability may be random, much of it may be attributed to factors that are difficult to assess. There is a need to identify and assess aspects of human performance that relate to plant safety and to develop measures that can be used to successfully assess human performance for purposes of research that can lead to technical basis for developing human factors review criteria.

  2. Activities in support of continuing the service of nuclear power plant concrete structures

    SciTech Connect

    Naus, Dan J

    2012-01-01

    In general, nuclear power plant concrete structure s performance has been very good; however, aging of concrete structures occurs with the passage of time that can potentially result in degradation if is effects are not controlled. Safety-related nuclear power plant concrete structures are described. In-service inspection and testing requirements in the U.S. are summarized. The interaction of the license renewal process and concrete structures is noted. A summary of operating experience related to aging of nuclear power plant concrete structures is provided. Several candidate areas are identified where additional research would be beneficial for aging management of nuclear power plant concrete structures. Finally, an update on recent activities at Oak Ridge National Laboratory related to aging management of nuclear power plant concrete structures is provided.

  3. Support for the American Chemical Society's Summer Schools in Nuclear and Radiochemistry

    SciTech Connect

    Mantica, Paul F.

    2013-06-20

    The ACS Summer Schools in Nuclear and Radiochemistry were held at San Jose State University (SJSU) and Brookhaven National Laboratory (BNL). The Summer Schools offer undergraduate students with U.S. citizenship an opportunity to complete coursework through ACS accredited chemistry degree programs at SJSU or the State University of New York at Stony Brook (SBU). The courses include lecture and laboratory work on the fundamentals and applications of nuclear and radiochemistry. The number of students participating at each site is limited to 12, and the low student-to-instructor ratio is needed due to the intense nature of the six-week program. To broaden the students’ perspectives on nuclear science, prominent research scientists active in nuclear and/or radiochemical research participate in a Guest Lecture Series. Symposia emphasizing environmental chemistry, nuclear medicine, and career opportunities are conducted as a part of the program.

  4. The U.S. Department of Energy, National Nuclear Security Agency's Use of Geographic Information Systems for Nuclear Emergency Response Support

    SciTech Connect

    A. L. Guber

    2001-06-01

    The U.S, Department of Energy (DOE), National Nuclear Security Agency's (NNSA) Remote Sensing Laboratory (RSL) provides Geographic Information System (GIS) support during nuclear emergency response activities. As directed by the NNSA, the RSL GIS staff maintains databases and equipment for rapid field deployment during an emergency response. When on location, GIS operators provide information products to on-site emergency managers as well as to emergency managers at the DOE Headquarters (HQ) Emergency Operations Center (EOC) in Washington, D.C. Data products are derived from multiple information sources in the field including radiological prediction models, field measurements taken on the ground and from the air, and pertinent information researched on the Internet. The GIS functions as a central data hub where it supplies the information to response elements in the field, as well as to headquarters officials at HQ during emergency response activities.

  5. Sorption (Kd) measurements in support of dose assessments for Zion Nuclear Station Decommissioning

    SciTech Connect

    Yim S. P.; Sullivan T.; Milian, L.

    2012-12-12

    The Zion Nuclear Power Station is being decommissioned. ZionSolutions proposes to leave much of the below grade structures in place and to fill them with “clean” concrete demolition debris from the above grade parts of the facility. This study, commissioned by ZionSolutions and conducted by the Brookhaven National Laboratory (BNL) was performed to provide site-specific data for performance assessment calculations to support the request to terminate the NRC license and allow unrestricted use of the facility. Specifically, this study measured the distribution coefficient for five radionuclides of concern using site-specific soils and groundwater. The distributions coefficient is a measure of the amount of the radionuclide that will remain sorbed to the soil or concrete that is present relative to the amount that will remain in solution. A high distribution coefficient indicates most of the radionuclide will remain on the solid material and will not be available for transport by the groundwater. The radionuclides of concern are Fe-55, Co-60, Ni-63, Sr-90, and Cs-137. Tests were performed following ASTM C1733-10, Standard Test Methods for Distribution Coefficients of Inorganic Species by the Batch Method. Sr-85 was used in the testing as an analogue for Sr-90 because it behaves similarly with respect to sorption and has a gamma emission that is easier to detect than the beta emission from Sr-90. Site-specific soils included disturbed sand (sand removed during construction and used as backfill), native sand, silt/clay and silt. In addition, concrete cores from the Unit-1 Containment Building and the Crib House were broken into particles less than 2 mm in size and tested to obtain distribution coefficients for the five nuclides.

  6. Blending mining and nuclear industries at the Waste Isolation Pilot Plant

    SciTech Connect

    Walls, J.R.

    1990-01-01

    At the Waste Isolation Pilot Plant (WIPP) traditional procedures for underground mining activities have been significantly altered in order to assure underground safety and project adherence to numerous regulatory requirements. Innovative techniques have been developed for WIPP underground procedures, mining equipment, and operating environments. The mining emphasis at WIPP is upon the quality of the excavation, not (as in conventional mines) on the production of ore. The WIPP is a United States Department of Energy (DOE) project that is located 30 miles southeast of Carlsbad, New Mexico, where the nation's first underground engineered nuclear repository is being constructed. The WIPP site was selected because of its location amidst a 607 meter thick salt bed, which provides a remarkably stable rock formation for the permanent storage of nuclear waste. The underground facility is located 655 meters below the earth's surface, in the Salado formation, which comprises two-hundred million year old halites with minor amounts of clay and anhydrites. When completed, the WIPP underground facility will consist of two components: approximately 81 square kilometers of experimental areas, and approximately 405 square kilometers of repository. 3 figs.

  7. Volume Reduction of Solid Radioactive Waste From Research Reactor and Nuclear Laboratories - Industrial Experience

    SciTech Connect

    Singh, B.N.; Gandhi, K.G.; Chander, M.; Raj, K.

    2006-07-01

    Various research reactors and nuclear laboratories at Bhabha Atomic Research Centre, Mumbai, India generate approximately 600 m{sup 3} of radioactive solid waste annually. These wastes are categorized and segregated based on their radiation field, physical nature and radionuclides present. The low level waste is further segregated based on compactability criteria. The compactable wastes are packed in 200 litres carbon steel drums and pelletized to get a volume reduction factor of about five. The compaction system designed for Cat-I (Table-1) radioactive waste is having 200 Tons capacity hydraulic press, housed in a well-ventilated enclosure. Before pelletizing, the drum is assayed to estimate {beta},{gamma} activity. Further, the imaging of waste drum is also done so as to avoid any possibility of non-compactable material being taken for pelletizing. The pelletizing system comprises of conveying, pushing, indexing and compacting. All operations are controlled by programmable logic control (PLC) based control system. Apart from the drum palletising, the system is also equipped to compact the used Pre and HEPA filters, being generated from exhaust and supply air system of clean room, nuclear laboratories, research reactors, fuel reprocessing plants, high level waste management facility etc. The system is designed to handle about 5 drums or filters per hour. So far about 3000 number of each, HEPA filters and waste drums have been safely compacted and disposed. (authors)

  8. Human Reliability Analysis in the U.S. Nuclear Power Industry: A Comparison of Atomistic and Holistic Methods

    SciTech Connect

    Ronald L. Boring; David I. Gertman; Jeffrey C. Joe; Julie L. Marble

    2005-09-01

    A variety of methods have been developed to generate human error probabilities for use in the US nuclear power industry. When actual operations data are not available, it is necessary for an analyst to estimate these probabilities. Most approaches, including THERP, ASEP, SLIM-MAUD, and SPAR-H, feature an atomistic approach to characterizing and estimating error. The atomistic approach is based on the notion that events and their causes can be decomposed and individually quantified. In contrast, in the holistic approach, such as found in ATHEANA, the analysis centers on the entire event, which is typically quantified as an indivisible whole. The distinction between atomistic and holistic approaches is important in understanding the nature of human reliability analysis quantification and the utility and shortcomings associated with each approach.

  9. Radiation resistant concrete for applications in nuclear power and radioactive waste industries

    NASA Astrophysics Data System (ADS)

    Burnham, Steven Robert

    Elemental components of ordinary concrete contain a variety of metals and rare earth elements that are susceptible to neutron activation. This activation occurs by means of radiative capture, a neutron interaction that results in formation of radioisotopes such as Co-60, Eu-152, and Eu-154. Studies have shown that these three radioisotopes are responsible for the residual radioactivity found in nuclear power plant concrete reactor dome and shielding walls. Such concrete is classified as Low Level Radioactive Waste (LLRW) and Very Low Level Waste (VLLW) by International Atomic Energy Agency (IAEA) standards and requires disposal at appropriate disposal sites. There are only three such sites in the USA, and every nuclear power plant will produce at the time of decommissioning approximately 1,500 tonnes of activated concrete classified as LLRW and VLLW. NAVA ALIGA (ancient word for a new stone) is a new concrete mixture developed mainly by research as presented in this thesis. The purpose of NAVA ALIGA is to satisfy IAEA clearance levels if used as a material for reactor dome, spent fuel pool, or radioactive waste canisters. NAVA ALIGA will never be activated above the IAEA clearance level after long-term exposure to neutron radiation when used as a material for reactor dome, spent fuel pool, and radioactive waste canisters. Components of NAVA ALIGA were identified using Instrumental Neutron Activation Analysis (INAA) and Inductively Coupled Plasma Mass Spectrometry (ISP-MS) to determine trace element composition. In addition, it was tested for compressive strength and permeability, important for nuclear infrastructure. The studied mixture had a high water to cement ratio of 0.56, which likely resulted in the high measured permeability, yet the mixture also showed a compressive strength greater than 6 000 psi after 28 days. In addition to this experimental analysis, which goal was to develop a standard approach to define the concrete mixtures in satisfying the IAEA

  10. A perspective on large eddy simulation of problems in the nuclear industry

    SciTech Connect

    Hassan, Y.A.; Pruitt, J.M.; Steininger, D.A.

    1995-12-01

    Because of the complex nature of coolant flow in nuclear reactors, current subchannel methods for light water reactor analysis are insufficient. The large eddy simulation method has been proposed as a computational tool for subchannel analysis. In large eddy simulation, large flow structures are computed while small scales are modeled, thereby decreasing computational time as compared with direct numerical simulation methods. Large eddy simulation has been used in complex geometry calculations providing good results in tube bundle cross-flow situations in steam generators. It is proposed that the large eddy simulation method be extended from single- to two-phase flow calculations to help in the prediction of the thermal diffusion of energy between adjacent subchannels.

  11. Americium and plutonium association with magnesium hydroxide colloids in alkaline nuclear industry process environments

    NASA Astrophysics Data System (ADS)

    Maher, Zoe; Ivanov, Peter; O'Brien, Luke; Sims, Howard; Taylor, Robin J.; Heath, Sarah L.; Livens, Francis R.; Goddard, David; Kellet, Simon; Rand, Peter; Bryan, Nick D.

    2016-01-01

    The behaviours of Pu, Am and colloids in feed solutions to the Site Ion-exchange Effluent Plant (SIXEP) at the Sellafield nuclear reprocessing site in the U.K. have been studied. For both Pu and Am, fractions were found to be associated with material in the colloidal size range, with ˜50% of the Pu in the range 1-200 nm. The concentration of soluble Pu (<1 nm) was ˜1 nM, which is very similar to the solubility limit for Pu(V). The soluble Am concentration was of the order of 10-11 M, which was below the solubility limit of americium hydroxide. The size, morphology and elemental composition of the particulates and colloids in the feed solutions were investigated. Magnesium is homogeneously distributed throughout the particles, whereas U, Si, Fe, and Ca were present in localised areas only. Amongst some heterogeneous material, particles were identified that were consistent with hydrotalcite. The distribution of 241Am(III) on brucite (magnesium hydroxide) colloids of different sizes was studied under alkaline conditions representative of nuclear fuel storage pond and effluent feed solution conditions. The morphology of the brucite particles in the bulk material observed by ESEM was predominantly hexagonal, while that of the carbonated brucite consisted of hexagonal species mixed with platelets. The association of 241Am(III) with the brucite colloids was studied by ultrafiltration coupled with gamma ray-spectrometry. For carbonate concentrations up to 10-3 M, the 241Am(III) was mainly associated with larger colloids (>300 kDa), and there was a shift from the smaller size fractions to the larger over a period of 6 months. At higher carbonate concentrations (10-2 M), the Am was predominantly detected in the true solution fraction (<3 kDa) and in smaller size colloidal fractions, in the range 3-100 kDa.

  12. Effects of airborne particulates on remote spectrometry data collected for industrial accident response support

    NASA Astrophysics Data System (ADS)

    Lewis, Paul E.

    2003-12-01

    The Environmental Protection Agency (EPA) Region 7 maintains an operational passive midwave/longwave airborne spectrometer system. This system provides near-real-time information on hazardous chemical releases (e.g., chemical constituents, column density and direction) for emergency personnel responding to industrial accidents. Industrial accidents range from ruptured tank cars caused by train derailments to explosions at industrial facilities. Airborne particles may be present as well, especially in accidents involving explosions and fire. This paper investigates how the presence of airborne particles can affect the identification of airborne chemical species in these situations.

  13. Effects of airborne particulates on remote spectrometry data collected for industrial accident response support

    NASA Astrophysics Data System (ADS)

    Lewis, Paul E.

    2004-01-01

    The Environmental Protection Agency (EPA) Region 7 maintains an operational passive midwave/longwave airborne spectrometer system. This system provides near-real-time information on hazardous chemical releases (e.g., chemical constituents, column density and direction) for emergency personnel responding to industrial accidents. Industrial accidents range from ruptured tank cars caused by train derailments to explosions at industrial facilities. Airborne particles may be present as well, especially in accidents involving explosions and fire. This paper investigates how the presence of airborne particles can affect the identification of airborne chemical species in these situations.

  14. Public comments on the proposed 10 CFR Part 51 rule for renewal of nuclear power plant operating licenses and supporting documents: Review of concerns and NRC staff response. Volume 1

    SciTech Connect

    1996-05-01

    This report documents the Nuclear Regulatory Commission (NRC) staff review of public comments provided in response to the NRC`s proposed amendments to 10 Code of Federal Regulations (CFR) Part 51, which establish new requirements for the environmental review of applications for the renewal of operating licenses of nuclear power plants. The public comments include those submitted in writing, as well as those provided at public meetings that were held with other Federal agencies, State agencies, nuclear industry representatives, public interest groups, and the general public. This report also contains the NRC staff response to the various concerns raised, and highlights the changes made to the final rule and the supporting documents in response to these concerns.

  15. Data supporting the nuclear phylogenomics of the palm subfamily Arecoideae (Arecaceae).

    PubMed

    Comer, Jason R; Zomlefer, Wendy B; Barrett, Craig F; Stevenson, Dennis Wm; Heyduk, Karolina; Leebens-Mack, James H

    2016-06-01

    This data article provides data and supplemental materials referenced in "Nuclear phylogenomics of the palm subfamily Arecoideae (Arecaceae)" (Comer et al., 2016) [1]. Raw sequence reads generated for this study are available through the Sequence Read Archive (SRA Study Accession: SRP061467). An aligned supermatrix of 168 nuclear genes for 35 taxa (34 palms and one outgroup taxon) is provided. Also provided are individual maximum likelihood gene trees used for the coalescent based analyses, output from the maximum parsimony analyses, and two figures.

  16. An Overview of Facilities and Capabilities to Support the Development of Nuclear Thermal Propulsion

    SciTech Connect

    James Werner; Sam Bhattacharyya; Mike Houts

    2011-02-01

    Abstract. The future of American space exploration depends on the ability to rapidly and economically access locations of interest throughout the solar system. There is a large body of work (both in the US and the Former Soviet Union) that show that Nuclear Thermal Propulsion (NTP) is the most technically mature, advanced propulsion system that can enable this rapid and economical access by its ability to provide a step increase above what is a feasible using a traditional chemical rocket system. For an NTP system to be deployed, the earlier measurements and recent predictions of the performance of the fuel and the reactor system need to be confirmed experimentally prior to launch. Major fuel and reactor system issues to be addressed include fuel performance at temperature, hydrogen compatibility, fission product retention, and restart capability. The prime issue to be addressed for reactor system performance testing involves finding an affordable and environmentally acceptable method to test a range of engine sizes using a combination of nuclear and non-nuclear test facilities. This paper provides an assessment of some of the capabilities and facilities that are available or will be needed to develop and test the nuclear fuel, and reactor components. It will also address briefly options to take advantage of the greatly improvement in computation/simulation and materials processing capabilities that would contribute to making the development of an NTP system more affordable. Keywords: Nuclear Thermal Propulsion (NTP), Fuel fabrication, nuclear testing, test facilities.

  17. Hanford spent nuclear fuel project recommended path forward, volume III: Alternatives and path forward evaluation supporting documentation

    SciTech Connect

    Fulton, J.C.

    1994-10-01

    Volume I of the Hanford Spent Nuclear Fuel Project - Recommended Path Forward constitutes an aggressive series of projects to construct and operate systems and facilities to safely retrieve, package, transport, process, and store K Basins fuel and sludge. Volume II provided a comparative evaluation of four Alternatives for the Path Forward and an evaluation for the Recommended Path Forward. Although Volume II contained extensive appendices, six supporting documents have been compiled in Volume III to provide additional background for Volume II.

  18. HTR-100 industrial nuclear power plant for generation of heat and electricity

    SciTech Connect

    Brandes, S.; Kohl, W.

    1987-11-01

    Based on their proven high-temperature reactor (HTR) with pebble-bed core, Brown, Boveri and Cie/Hochtemperatur-Reaktorbau have developed an HTR-100 plant that combines favorable capital costs and high availability. Due to the high HTR-specific standards and passive safety features, this plant is especially well suited for siting near the end user. The safety concept permits further operation of the plant or decay heat removal via the operational heat sinks in the event of maloperation and design basis accidents having a higher probability of occurrence. In the event of hypothetical accidents, the decay heat is removed from the reactor pressure vessel by radiation, conduction, and convection to a concrete cooling system operating in natural convection. As an example of the new HTR-100 plant concept, a twin-block plant design for extraction of industrial steam is presented.

  19. Incorporating GIS data into an agent-based model to support planning policy making for the development of creative industries

    NASA Astrophysics Data System (ADS)

    Liu, Helin; Silva, Elisabete A.; Wang, Qian

    2016-07-01

    This paper presents an extension to the agent-based model "Creative Industries Development-Urban Spatial Structure Transformation" by incorporating GIS data. Three agent classes, creative firms, creative workers and urban government, are considered in the model, and the spatial environment represents a set of GIS data layers (i.e. road network, key housing areas, land use). With the goal to facilitate urban policy makers to draw up policies locally and optimise the land use assignment in order to support the development of creative industries, the improved model exhibited its capacity to assist the policy makers conducting experiments and simulating different policy scenarios to see the corresponding dynamics of the spatial distributions of creative firms and creative workers across time within a city/district. The spatiotemporal graphs and maps record the simulation results and can be used as a reference by the policy makers to adjust land use plans adaptively at different stages of the creative industries' development process.

  20. DOC/WSNSO (Department of Commerce/Weather Service Nuclear Support Office) operational support to Federal Radiological Monitoring and Assessment Center

    SciTech Connect

    Mueller, P.

    1989-01-01

    The National Weather Service (NWS) is an agency of the Department of Commerce. The NWS has hundreds of weather offices throughout the United States. The Weather Service Nuclear Support Office (WSNSO) is a highly specialized unit of NWS that provides direct support to the U.S. Department of Energy's (DOE's) underground nuclear testing program. The WSNSO has been associated with the DOE for >33 yr. As a result of the unique relationship with the DOE, all WSNSO emergency response meteorologists and meteorological technicians are allowed access to classified material. Meteorological phenomena play a significant role during a Federal Radiological Monitoring and Assessment Center (FRMAC) event, and WSNSO meteorologists provide direct support to ARAC. The marriage of state-of-the-art computer systems together with proven technology provides the on-scene WSNSO meteorologist with essentially a portable fully equipped, fully functional, advanced NWS weather station. The WSNSO's emergency response personnel and hardware are at the ready and can be mobilized within 2 h. WSNSO can provide on-scene weather forecasts and critical weather data collection whenever and wherever necessary.

  1. Applications in the Nuclear Industry for Thermal Spray Amorphous Metal and Ceramic Coatings

    SciTech Connect

    Blink, J; Choi, J; Farmer, J

    2007-07-09

    Amorphous metal and ceramic thermal spray coatings have been developed that can be used to enhance the corrosion resistance of containers for the transportation, aging and disposal of spent nuclear fuel and high-level radioactive wastes. Iron-based amorphous metal formulations with chromium, molybdenum and tungsten have shown the corrosion resistance believed to be necessary for such applications. Rare earth additions enable very low critical cooling rates to be achieved. The boron content of these materials, and their stability at high neutron doses, enable them to serve as high efficiency neutron absorbers for criticality control. Ceramic coatings may provide even greater corrosion resistance for container applications, though the boron-containing amorphous metals are still favored for criticality control applications. These amorphous metal and ceramic materials have been produced as gas atomized powders and applied as near full density, non-porous coatings with the high-velocity oxy-fuel process. This paper summarizes the performance of these coatings as corrosion-resistant barriers, and as neutron absorbers. Relevant corrosion models are also discussed, as well as a cost model to quantify the economic benefits possible with these new materials.

  2. Applications in the Nuclear Industry for Corrosion-Resistant Amorphous-Metal Thermal-Spray Coatings

    SciTech Connect

    Farmer, J; Choi, J

    2007-07-18

    Amorphous metal and ceramic thermal spray coatings have been developed that can be used to enhance the corrosion resistance of containers for the transportation, aging and disposal of spent nuclear fuel and high-level radioactive wastes. Fe-based amorphous metal formulations with chromium, molybdenum and tungsten have shown the corrosion resistance believed to be necessary for such applications. Rare earth additions enable very low critical cooling rates to be achieved. The boron content of these materials, and their stability at high neutron doses, enable them to serve as high efficiency neutron absorbers for criticality control. Ceramic coatings may provide even greater corrosion resistance for container applications, though the boron-containing amorphous metals are still favored for criticality control applications. These amorphous metal and ceramic materials have been produced as gas atomized powders and applied as near full density, non-porous coatings with the high-velocity oxy-fuel process. This paper summarizes the performance of these coatings as corrosion-resistant barriers, and as neutron absorbers. Relevant corrosion models are also discussed, as well as a cost model to quantify the economic benefits possible with these new materials.

  3. Commercial nuclear power 1990

    SciTech Connect

    Not Available

    1990-09-28

    This report presents the status at the end of 1989 and the outlook for commercial nuclear capacity and generation for all countries in the world with free market economies (FME). The report provides documentation of the US nuclear capacity and generation projections through 2030. The long-term projections of US nuclear capacity and generation are provided to the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) for use in estimating nuclear waste fund revenues and to aid in planning the disposal of nuclear waste. These projections also support the Energy Information Administration's annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment, and are provided to the Organization for Economic Cooperation and Development. The foreign nuclear capacity projections are used by the DOE uranium enrichment program in assessing potential markets for future enrichment contracts. The two major sections of this report discuss US and foreign commercial nuclear power. The US section (Chapters 2 and 3) deals with (1) the status of nuclear power as of the end of 1989; (2) projections of nuclear capacity and generation at 5-year intervals from 1990 through 2030; and (3) a discussion of institutional and technical issues that affect nuclear power. The nuclear capacity projections are discussed in terms of two projection periods: the intermediate term through 2010 and the long term through 2030. A No New Orders case is presented for each of the projection periods, as well as Lower Reference and Upper Reference cases. 5 figs., 30 tabs.

  4. Abandoned coal mining sites: using ecotoxicological tests to support an industrial organic sludge amendment.

    PubMed

    Chiochetta, Claudete G; Radetski, Marilice R; Corrêa, Albertina X R; Tischer, Vinícius; Tiepo, Erasmo N; Radetski, Claudemir M

    2013-11-01

    The different stages involved in coal mining-related activities result in a degraded landscape and sites associated with large amounts of dumped waste material. Remediation of these contaminated soils can be carried out by application of industrial organic sludge if the concerns regarding the potential negative environmental impacts of this experimental practice are properly addressed. In this context, the objective of this study was to use ecotoxicological tests to determine the quantity of organic industrial sludge that is required as a soil amendment to restore soil production while avoiding environmental impact. Chemical analysis of the solids (industrial sludge and soil) and their leachates was carried out as well as a battery of ecotoxicity tests on enzymes (hydrolytic activity), bacteria, algae, daphnids, earthworms, and higher plants, according to standardized methodologies. Solid and leachate samples of coal-contaminated soil were more toxic than those of industrial sludge towards enzyme activity, bacteria, algae, daphnids, and earthworms. In the case of the higher plants (lettuce, corn, wild cabbage, and Surinam cherry) the industrial sludge was more toxic than the coal-contaminated soil, and a soil/sludge mixture (66:34% dry weight basis) had a stimulatory effect on the Surinam cherry biomass. The ecotoxicological assessment of the coal-contaminated soil remediation using sludge as an amendment is very important to determine application rates that could promote a stimulatory effect on agronomic species without negatively affecting the environment.

  5. The Bad News and the Good about Nuclear Careers.

    ERIC Educational Resources Information Center

    Basta, Nicholas

    1986-01-01

    Traces the changes in the nuclear energy field since World War II, citing distinct periods of growth in the nuclear industry, as well as downtrends. Analyzes the reasons for the changes in public support for nuclear energy and the impact upon careers in the field. (TW)

  6. Joint DOE-PNC research on the use of transparency in support of nuclear nonproliferation

    SciTech Connect

    Mochiji, Toshiro; Keeney, R.; Tazaki, Makiko; Nakhleh, C.; Puckett, J.; Stanbro, W.

    1999-01-01

    PNC and LANL collaborated in research on the concept of transparency in nuclear nonproliferation. The research was based on the Action Sheet No. 21, which was signed in February 1996, ``The Joint Research on Transparency in Nuclear Nonproliferation`` under the ``Agreement between the Power Reactor and Nuclear Fuel Development Corporation of Japan (PNC) and the US Department of Energy (DOE) for Cooperation in Research and Development Concerning Nuclear Material Control and Accounting Measures for Safeguards and Nonproliferation``. The purpose of Action Sheet 21 is to provide a fundamental study on Transparency to clarify the means to improve worldwide acceptability for the nuclear energy from the nuclear nonproliferation point of view. This project consists of independent research and then joint discussion at workshops that address a series of topics and issues in transparency. The activities covered in Action Sheet 21 took place over a period of 18 months. Three workshops were held; the first and the third hosted by PNC in Tokyo, Japan and the second hosted by LANL in Los Alamos, New Mexico, US. The following is a summary of the three workshops. The first workshop addressed the policy environment of transparency. Each side presented its perspective on the following issues: (1) a definition of transparency, (2) reasons for transparency, (3) detailed goals of transparency and (4) obstacles to transparency. The topic of the second workshop was ``Development of Transparency Options.`` The activities accomplished were (1) identify type of facilities where transparency might be applied, (2) define criteria for applying transparency, and (3) delineate applicable transparency options. The goal of the third workshop, ``Technical Options for Transparency,`` was to (1) identify conceptual options for transparency system design; (2) identify instrumentation, measurement, data collection and data processing options; (3) identify data display options; and (4) identify technical

  7. More regulation of industry-supported biomedical research: are we asking the right questions?

    PubMed

    Fry-Revere, Sigrid; Malmstrom, David Bjorn

    2009-01-01

    Industry-sponsored biomedical research is under the microscope. In an attempt to achieve just results in extraordinary cases, critics are suggesting regulations that would pervert the U.S. clinical trial process. However, the arguments made to justify such regulation are weak at best. All the proposals to regulate industry sponsorship of clinical trials that we surveyed (over a hundred articles and ten books, most written in the past decade) suffer from some form of fallacious reasoning. In the interest of advocating sound policy, this article points out some of the most common reasoning errors found in the literature on financial conflicts of interest in clinical trials.

  8. Environmental characterization and radio-ecological impacts of non-nuclear industries on the Red Sea coast.

    PubMed

    El Mamoney, M H; Khater, Ashraf E M

    2004-01-01

    The Red Sea is a deep semi-enclosed and narrow basin connected to the Indian Ocean by a narrow sill in the south and to the Suez Canal in the north. Oil industries in the Gulf of Suez, phosphate ore mining activities in Safaga-Quseir region and intensified navigation activities are non-nuclear pollution sources that could have serious radiological impacts on the marine environment and the coastal ecosystems of the Red Sea. It is essential to establish the radiological base-line data, which does not exist yet, and to investigate the present radio-ecological impact of the non-nuclear industries to preserve and protect the coastal environment of the Red Sea. Some natural and man-made radionuclides have been measured in shore sediment samples collected from the Egyptian coast of the Red Sea. The specific activities of 226Ra and 210Pb (238U) series, 232Th series, 40K and 137Cs (Bq/kg dry weight) were measured using gamma ray spectrometers based on hyper-pure germanium detectors. The specific activities of 210Po (210Pb) and uranium isotopes (238U, 235U and 234U) (Bq/kg dry weight) were measured using alpha spectrometers based on surface barrier (PIPS) detectors after radiochemical separation. The absorbed radiation dose rates in air (nGy/h) due to natural radionuclides in shore sediment and radium equivalent activity index (Bq/kg) were calculated. The specific activity ratios of 228Ra/226Ra, 210Pb/226Ra, 226Ra/238U and 234U/238U were calculated for evaluation of the geo-chemical behaviour of these radionuclides. The average specific activity of 226Ra (238U) series, 232Th series, 40K and 210Pb were 24.7, 31.4, 427.5 and 25.6 Bq/kg, respectively. The concentration of 137Cs in the sediment samples was less than the lower limit of detection. The Red Sea coast is an arid region with very low rainfall and the sediment is mainly composed of sand. The specific activity of 238U, 235U and 234U were 25.3, 2.9 and 25.0 Bq/kg. The average specific activity ratios of 226Ra/228Ra, 210

  9. A case in support of implementing innovative bio-processes in the metal mining industry.

    PubMed

    Sánchez-Andrea, Irene; Stams, Alfons J M; Weijma, Jan; Gonzalez Contreras, Paula; Dijkman, Henk; Rozendal, Rene A; Johnson, D Barrie

    2016-06-01

    The metal mining industry faces many large challenges in future years, among which is the increasing need to process low-grade ores as accessible higher grade ores become depleted. This is against a backdrop of increasing global demands for base and precious metals, and rare earth elements. Typically about 99% of solid material hauled to, and ground at, the land surface currently ends up as waste (rock dumps and mineral tailings). Exposure of these to air and water frequently leads to the formation of acidic, metal-contaminated run-off waters, referred to as acid mine drainage, which constitutes a severe threat to the environment. Formation of acid drainage is a natural phenomenon involving various species of lithotrophic (literally 'rock-eating') bacteria and archaea, which oxidize reduced forms of iron and/or sulfur. However, other microorganisms that reduce inorganic sulfur compounds can essentially reverse this process. These microorganisms can be applied on industrial scale to precipitate metals from industrial mineral leachates and acid mine drainage streams, resulting in a net improvement in metal recovery, while minimizing the amounts of leachable metals to the tailings storage dams. Here, we advocate that more extensive exploitation of microorganisms in metal mining operations could be an important way to green up the industry, reducing environmental risks and improving the efficiency and the economy of metal recovery.

  10. Occupation and Industry Sex Segregation, Gender, and Workplace Support: The Use of Flexible Scheduling Policies

    ERIC Educational Resources Information Center

    Minnotte, Krista Lynn; Cook, Alison; Minnotte, Michael C.

    2010-01-01

    This study examines how industry and occupation sex segregation are related to the use of flexible scheduling policies and perceptions of the career repercussions of using such policies. The analysis is performed on data from the 2002 National Study of the Changing Workforce (N = 2,810). Findings suggest that the percentage of women per industry…

  11. Quantifying the passive gamma signal from spent nuclear fuel in support of determining the plutonium content in spent nuclear fuel with nondestructive assay

    SciTech Connect

    Fensin, Michael L; Tobin, Steven J; Menlove, Howard O; Swinhoe, Martyn T

    2009-01-01

    The objective of safeguarding nuclear material is to deter diversions of significant quantities of nuclear materials by timely monitoring and detection. There are a variety of motivations for quantifying plutonium in spent fuel (SF), by means of nondestructive assay (NDA), in order to meet this goal. These motivations include the following: strengthening the capabilities of the International Atomic Energy Agencies ability to safeguard nuclear facilities, shipper/receiver difference, input accountability at reprocessing facilities and burnup credit at repositories. Many NDA techniques exist for measuring signatures from SF; however, no single NDA technique can, in isolation, quantify elemental plutonium in SF. A study has been undertaken to determine the best integrated combination of 13 NDA techniques for characterizing Pu mass in spent fuel. This paper focuses on the development of a passive gamma measurement system in support the spent fuel assay system. Gamma ray detection for fresh nuclear fuel focuses on gamma ray emissions that directly coincide with the actinides of interest to the assay. For example, the 186-keV gamma ray is generally used for {sup 235}U assay and the 384-keV complex is generally used for assaying plutonium. In spent nuclear fuel, these signatures cannot be detected as the Compton continuum created from the fission products dominates the signal in this energy range. For SF, the measured gamma signatures from key fission products ({sup 134}Cs, {sup 137}Cs, {sup 154}Eu) are used to ascertain burnup, cooling time, and fissile content information. In this paper the Monte Carlo modeling set-up for a passive gamma spent fuel assay system will be described. The set-up of the system includes a germanium detector and an ion chamber and will be used to gain passive gamma information that will be integrated into a system for determining Pu in SF. The passive gamma signal will be determined from a library of {approx} 100 assemblies that have been

  12. Analysis of nuclear piping system seismic tests with conventional and energy absorbing supports

    SciTech Connect

    Park, Y.; DeGrassi, G.; Hofmayer, C.; Bezler, P.; Chokshi, N.

    1997-04-01

    Large-scale models of main steam and feedwater piping systems were tested on the shaking table by the Nuclear Power Engineering Cooperation (NUPEC) of Japan, as part of the Seismic Proving Test Program. This paper describes the linear and nonlinear analyses performed by NRC/BNL and compares the results to the test data.

  13. Developing a Validation Methodology for Expert-Informed Bayesian Network Models Supporting Nuclear Nonproliferation Analysis

    SciTech Connect

    White, Amanda M.; Gastelum, Zoe N.; Whitney, Paul D.

    2014-05-13

    Under the auspices of Pacific Northwest National Laboratory’s Signature Discovery Initiative (SDI), the research team developed a series of Bayesian Network models to assess multi-source signatures of nuclear programs. A Bayesian network is a mathematical model that can be used to marshal evidence to assess competing hypotheses. The purpose of the models was to allow non-expert analysts to benefit from the use of expert-informed mathematical models to assess nuclear programs, because such assessments require significant technical expertise ranging from the nuclear fuel cycle, construction and engineering, imagery analysis, and so forth. One such model developed under this research was aimed at assessing the consistency of open-source information about a nuclear facility with the facility’s declared use. The model incorporates factors such as location, security and safety features among others identified by subject matter experts as crucial to their assessments. The model includes key features, observables and their relationships. The model also provides documentation, which serves as training materials for the non-experts.

  14. Intellectual Disability and Sexuality: Attitudes of Disability Support Staff and Leisure Industry Employees

    ERIC Educational Resources Information Center

    Gilmore, Linda; Chambers, Brooke

    2010-01-01

    Background: The attitudes of support staff and others in the community towards the sexuality of individuals with an intellectual disability (ID) have the potential to influence opportunities for normalised life experiences in the area of sexuality. Method: A sample of 169 disability support staff and 50 employees from leisure and service…

  15. Assessment of elemental and NROM/TENORM hazard potential from non-nuclear industries in North Sinai, Egypt.

    PubMed

    El-Mekawy, A F; Badran, H M; Seddeek, M K; Sharshar, T; Elnimr, T

    2015-09-01

    Non-nuclear industries use raw materials containing significant levels of naturally occurring radioactive material (NORM). The processing of these materials may expose workers engaged in or even people living near such sites to technologically enhanced naturally occurring radioactive material (TENORM) above the natural background. Inductively coupled plasma and gamma ray spectrometry have been used to determine major and trace elements and radionuclide concentrations in various samples, respectively, in order to investigate the environmental impact of coal mining and cement plant in North Sinai, Egypt. Generally, very little attention was directed to the large volumes of waste generated by either type of industrial activities. Different samples were analyzed including various raw materials, coal, charcoal, Portland and white cement, sludge, and wastes. Coal mine and cement plant workers dealing with waste and kaolin, respectively, are subjected to a relatively high annual effective dose. One of the important finding is the enhancement of all measured elements and radionuclides in the sludge found in coal mine. It may pose an environmental threat because of its large volume and its use as combustion material. The mine environment may have constituted Al, Fe, Cr, and V pollution source for the local area. Higher concentration of Al, Fe, Mn, B, Co, Cr, Mn, Ni, Sr, V, and TENORM were found in Portland cement and Zn in white cement. Coal has higher concentrations of Al, Fe, B, Co, Cr, and V as well as (226)Ra and (232)Th. The compiled results from the present study and different worldwide investigations demonstrate the obvious unrealistic ranges normally used for (226)Ra and (232)Th activity concentrations in coal and provided ranges for coal, Portland and white cement, gypsum, and limestone.

  16. Supporting data for identification of biosurfactant-producing bacteria isolated from agro-food industrial effluent.

    PubMed

    Fulazzaky, Mohamad Ali; Abdullah, Shakila; Salim, Mohd Razman

    2016-06-01

    The goal of this study was to identify the biosurfactant-producing bacteria isolated from agro-food industrial effluet. The identification of the potential bacterial strain using a polymerase chain reaction of the 16S rRNA gene analysis was closely related to Serratia marcescens with its recorded strain of SA30 "Fundamentals of mass transfer and kinetics for biosorption of oil and grease from agro-food industrial effluent by Serratia marcescens SA30" (Fulazzaky et al., 2015) [1]; however, many biochemical tests have not been published yet. The biochemical tests of biosurfactant production, haemolytic assay and cell surface hydrophobicity were performed to investigate the beneficial strain of biosurfactant-producing bacteria. Here we do share data collected from the biochemical tests to get a better understanding of the use of Serratia marcescens SA30 to degrade oil, which contributes the technical features of strengthening the biological treatment of oil-contaminated wastewater in tropical environments.

  17. U.S. Department of Defense Contract Spending and the Supporting Industrial Base, 2000-2013

    DTIC Science & Technology

    2014-04-30

    2000 –2013 David Berteau, Center for Strategic & International Studies Jesse Ellman, Center for Strategic & International Studies Gregory...Industrial Base, 2000 -2013 5a. CONTRACT NUMBER 5b. GRANT NUMBER 5c. PROGRAM ELEMENT NUMBER 6. AUTHOR(S) 5d. PROJECT NUMBER 5e. TASK NUMBER 5f...federal contract dollars throughout the growth and subsequent inflection of defense spending of the 2000 ??? 2013 study period. This data will be analyzed

  18. Low nucleotide diversity for the expanded organelle and nuclear genomes of Volvox carteri supports the mutational-hazard hypothesis.

    PubMed

    Smith, David Roy; Lee, Robert W

    2010-10-01

    The noncoding-DNA content of organelle and nuclear genomes can vary immensely. Both adaptive and nonadaptive explanations for this variation have been proposed. This study addresses a nonadaptive explanation called the mutational-hazard hypothesis and applies it to the mitochondrial, plastid, and nuclear genomes of the multicellular green alga Volvox carteri. Given the expanded architecture of the V. carteri organelle and nuclear genomes (60-85% noncoding DNA), the mutational-hazard hypothesis would predict them to have less silent-site nucleotide diversity (π(silent)) than their more compact counterparts from other eukaryotes-ultimately reflecting differences in 2N(g)μ (twice the effective number of genes per locus in the population times the mutation rate). The data presented here support this prediction: Analyses of mitochondrial, plastid, and nuclear DNAs from seven V. carteri forma nagariensis geographical isolates reveal low values of π(silent) (0.00038, 0.00065, and 0.00528, respectively), much lower values than those previously observed for the more compact organelle and nuclear DNAs of Chlamydomonas reinhardtii (a close relative of V. carteri). We conclude that the large noncoding-DNA content of the V. carteri genomes is best explained by the mutational-hazard hypothesis and speculate that the shift from unicellular to multicellular life in the ancestor that gave rise to V. carteri contributed to a low V. carteri population size and thus a reduced 2N(g)μ. Complete mitochondrial and plastid genome maps for V. carteri are also presented and compared with those of C. reinhardtii.

  19. Challenges and models in supporting logistics system design for dedicated-biomass-based bioenergy industry.

    PubMed

    Zhu, Xiaoyan; Li, Xueping; Yao, Qingzhu; Chen, Yuerong

    2011-01-01

    This paper analyzed the uniqueness and challenges in designing the logistics system for dedicated biomass-to-bioenergy industry, which differs from the other industries, due to the unique features of dedicated biomass (e.g., switchgrass) including its low bulk density, restrictions on harvesting season and frequency, content variation with time and circumambient conditions, weather effects, scattered distribution over a wide geographical area, and so on. To design it, this paper proposed a mixed integer linear programming model. It covered from planting and harvesting switchgrass to delivering to a biorefinery and included the residue handling, concentrating on integrating strategic decisions on the supply chain design and tactical decisions on the annual operation schedules. The present numerical examples verified the model and demonstrated its use in practice. This paper showed that the operations of the logistics system were significantly different for harvesting and non-harvesting seasons, and that under the well-designed biomass logistics system, the mass production with a steady and sufficient supply of biomass can increase the unit profit of bioenergy. The analytical model and practical methodology proposed in this paper will help realize the commercial production in biomass-to-bioenergy industry.

  20. Virtual reality based support system for layout planning and programming of an industrial robotic work cell.

    PubMed

    Yap, Hwa Jen; Taha, Zahari; Dawal, Siti Zawiah Md; Chang, Siow-Wee

    2014-01-01

    Traditional robotic work cell design and programming are considered inefficient and outdated in current industrial and market demands. In this research, virtual reality (VR) technology is used to improve human-robot interface, whereby complicated commands or programming knowledge is not required. The proposed solution, known as VR-based Programming of a Robotic Work Cell (VR-Rocell), consists of two sub-programmes, which are VR-Robotic Work Cell Layout (VR-RoWL) and VR-based Robot Teaching System (VR-RoT). VR-RoWL is developed to assign the layout design for an industrial robotic work cell, whereby VR-RoT is developed to overcome safety issues and lack of trained personnel in robot programming. Simple and user-friendly interfaces are designed for inexperienced users to generate robot commands without damaging the robot or interrupting the production line. The user is able to attempt numerous times to attain an optimum solution. A case study is conducted in the Robotics Laboratory to assemble an electronics casing and it is found that the output models are compatible with commercial software without loss of information. Furthermore, the generated KUKA commands are workable when loaded into a commercial simulator. The operation of the actual robotic work cell shows that the errors may be due to the dynamics of the KUKA robot rather than the accuracy of the generated programme. Therefore, it is concluded that the virtual reality based solution approach can be implemented in an industrial robotic work cell.

  1. Implicit attitudes toward nuclear power and mobile phone base stations: support for the affect heuristic.

    PubMed

    Siegrist, Michael; Keller, Carmen; Cousin, Marie-Eve

    2006-08-01

    The implicit association test (IAT) measures automatic associations. In the present research, the IAT was adapted to measure implicit attitudes toward technological hazards. In Study 1, implicit and explicit attitudes toward nuclear power were examined. Implicit measures (i.e., the IAT) revealed negative attitudes toward nuclear power that were not detected by explicit measures (i.e., a questionnaire). In Study 2, implicit attitudes toward EMF (electro-magnetic field) hazards were examined. Results showed that cell phone base stations and power lines are judged to be similarly risky and, further, that base stations are more closely related to risk concepts than home appliances are. No differences between experts and lay people were observed. Results of the present studies are in line with the affect heuristic proposed by Slovic and colleagues. Affect seems to be an important factor in risk perception.

  2. Activities in Support of Continuing the Service of Nuclear Power Plant Safety-Related Concrete Structures

    SciTech Connect

    Naus, Dan J

    2014-01-01

    Nuclear power plant (NPP) concrete structures are described. In-service inspection and testing requirements in the U.S. are summarized. The license renewal process in the U.S. is outlined and its current status provided. Operating experience related to performance of the concrete structures is presented. Basic components of a program to manage aging of the concrete structures are identified and described: (1) Degradation mechanisms, damage models, and material performance; (2) Assessment and remediation: i.e., component selection, in- service inspection, non-destructive examinations, and remedial actions; and (3) Estimation of performance at present or some future point in time: i.e., application of structural reliability theory to the design and optimization of in-service inspection/maintenance strategies, and determination of the effects of degradation on plant risk. Finally, areas are noted where additional research would be of benefit to aging management of nuclear power plant concrete structures.

  3. Personal computer based decision support system for routing nuclear spent fuel

    SciTech Connect

    Chin, Shih-Miao; Joy, D.S.; Johnson, P.E. ); Bobic, S.M.; Miaou, Shaw-Pin . Transportation Center)

    1989-11-14

    An approach has been formulated to route nuclear spent fuel over the US Interstate highway network. This approach involves the generation of alternative routes so that any potential adverse impacts will not only concentrate on regions along the shortest path between the nuclear power plant and repository. Extensive literature research on the shortest path finding algorithms has been carried out. Consequently, an extremely efficient shortest path algorithm has been implemented and significantly increases the overall system performance. State-of-the-art interactive computer graphics is used. In addition to easy-to-use pop-up menus, full color mapping and display capabilities are also incorporated. All of these features have been implemented on commonly available personal computers. 6 figs., 2 tabs.

  4. Full-Scale Accident Testing in Support of Used Nuclear Fuel Transportation.

    SciTech Connect

    Durbin, Samuel G.; Lindgren, Eric R.; Rechard, Rob P.; Sorenson, Ken B.

    2014-09-01

    The safe transport of spent nuclear fuel and high-level radioactive waste is an important aspect of the waste management system of the United States. The Nuclear Regulatory Commission (NRC) currently certifies spent nuclear fuel rail cask designs based primarily on numerical modeling of hypothetical accident conditions augmented with some small scale testing. However, NRC initiated a Package Performance Study (PPS) in 2001 to examine the response of full-scale rail casks in extreme transportation accidents. The objectives of PPS were to demonstrate the safety of transportation casks and to provide high-fidelity data for validating the modeling. Although work on the PPS eventually stopped, the Blue Ribbon Commission on America’s Nuclear Future recommended in 2012 that the test plans be re-examined. This recommendation was in recognition of substantial public feedback calling for a full-scale severe accident test of a rail cask to verify evaluations by NRC, which find that risk from the transport of spent fuel in certified casks is extremely low. This report, which serves as the re-assessment, provides a summary of the history of the PPS planning, identifies the objectives and technical issues that drove the scope of the PPS, and presents a possible path for moving forward in planning to conduct a full-scale cask test. Because full-scale testing is expensive, the value of such testing on public perceptions and public acceptance is important. Consequently, the path forward starts with a public perception component followed by two additional components: accident simulation and first responder training. The proposed path forward presents a series of study options with several points where the package performance study could be redirected if warranted.

  5. Denitrification of high strength nitrate waste from a nuclear industry using acclimatized biomass in a pilot scale reactor.

    PubMed

    Dhamole, Pradip B; Nair, Rashmi R; D'Souza, Stanislaus F; Pandit, Aniruddha B; Lele, S S

    2015-01-01

    This work investigates the performance of acclimatized biomass for denitrification of high strength nitrate waste (10,000 mg/L NO3) from a nuclear industry in a continuous laboratory scale (32 L) and pilot scale reactor (330 L) operated over a period of 4 and 5 months, respectively. Effect of substrate fluctuations (mainly C/NO3-N) on denitrification was studied in a laboratory scale reactor. Incomplete denitrification (95-96 %) was observed at low C/NO3-N (≤2), whereas at high C/NO3-N (≥2.25) led to ammonia formation. Ammonia production increased from 1 to 9 % with an increase in C/NO3-N from 2.25 to 6. Complete denitrification and no ammonia formation were observed at an optimum C/NO3-N of 2.0. Microbiological studies showed decrease in denitrifiers and increase in nitrite-oxidizing bacteria and ammonia-oxidizing bacteria at high C/NO3-N (≥2.25). Pilot scale studies were carried out with optimum C/NO3-N, and sustainability of the process was checked on the pilot scale for 5 months.

  6. Defense Civil Support: DOD Has Made Progress Incorporating the Homeland Response Force into the Chemical, Biological, Radiological, and Nuclear Response Enterprise

    DTIC Science & Technology

    2016-06-01

    DEFENSE CIVIL SUPPORT DOD Has Made Progress Incorporating the Homeland Response Force into the Chemical...Biological, Radiological, and Nuclear Response Enterprise Report to the Committee on Armed Services, House of Representatives June 2016 GAO-16-599... Response Force into the Chemical, Biological, Radiological, and Nuclear Response Enterprise Why GAO Did This Study DOD is expected to play a prominent

  7. Relationship between social support, mental health and health care consciousness in developing the industrial health education of male employees.

    PubMed

    Fujita, Daisuke; Kanaoka, Midori

    2003-11-01

    The purpose of the study is to elucidate the relationship between social support, health care consciousness and mental health in developing the industrial health education aimed at improving the health habits of male employees. A questionnaire survey concerning health practices, mental health based on the General Health Questionnaire, social support from social support networks, and health care consciousness based on the Health Locus of Control was conducted on male employees in three companies in Osaka Prefecture. A total of 1,634 questionnaires were collected. Analyses by age group showed that in all age groups, the higher the social support score, the more favorable the mental health became and the stronger the family care in health care consciousness became. The better the mental health, the greater the number of good health practices was and the lower the fortune dependence in health care consciousness tended to be. The results of the study reconfirm the previous findings that it is necessary to put the mental health of male employees in good condition before everything else in effectively developing health education aimed at improving their health habits. This study also indicates that the level of perception of social support and their internal control of self and family in health care consciousness are definitely related to the stability of subjects' mental health. It is therefore presumed that measures to raise the revel of perception of social support are important since they may improve the mental health of subjects.

  8. Supporting business continuity during a highly pathogenic avian influenza outbreak: a collaboration of industry, academia, and government.

    PubMed

    Hennessey, Morgan; Lee, Brendan; Goldsmith, Timothy; Halvorson, Dave; Hueston, William; McElroy, Kristina; Waters, Katherine

    2010-03-01

    Since 2006, a collaborative group of egg industry, state, federal, and academia representatives have worked to enhance preparedness in highly pathogenic avian influenza (HPAI) planning. The collaborative group has created a draft egg product movement protocol, which calls for realistic, science-based contingency plans, biosecurity assessments, commodity risk assessments, and real-time reverse transcriptase-PCR testing to support the continuity of egg operations while also preventing and eradicating an HPAI outbreak. The work done by this group serves as an example of how industry, government, and academia can work together to achieve better preparedness in the event of an animal health emergency. In addition, in the event of an HPAI outbreak in domestic poultry, U.S. consumers will be assured that their egg products come from healthy chickens.

  9. Virtual Reality Based Support System for Layout Planning and Programming of an Industrial Robotic Work Cell

    PubMed Central

    Yap, Hwa Jen; Taha, Zahari; Md Dawal, Siti Zawiah; Chang, Siow-Wee

    2014-01-01

    Traditional robotic work cell design and programming are considered inefficient and outdated in current industrial and market demands. In this research, virtual reality (VR) technology is used to improve human-robot interface, whereby complicated commands or programming knowledge is not required. The proposed solution, known as VR-based Programming of a Robotic Work Cell (VR-Rocell), consists of two sub-programmes, which are VR-Robotic Work Cell Layout (VR-RoWL) and VR-based Robot Teaching System (VR-RoT). VR-RoWL is developed to assign the layout design for an industrial robotic work cell, whereby VR-RoT is developed to overcome safety issues and lack of trained personnel in robot programming. Simple and user-friendly interfaces are designed for inexperienced users to generate robot commands without damaging the robot or interrupting the production line. The user is able to attempt numerous times to attain an optimum solution. A case study is conducted in the Robotics Laboratory to assemble an electronics casing and it is found that the output models are compatible with commercial software without loss of information. Furthermore, the generated KUKA commands are workable when loaded into a commercial simulator. The operation of the actual robotic work cell shows that the errors may be due to the dynamics of the KUKA robot rather than the accuracy of the generated programme. Therefore, it is concluded that the virtual reality based solution approach can be implemented in an industrial robotic work cell. PMID:25360663

  10. A multi-temporal analysis approach for land cover mapping in support of nuclear incident response

    NASA Astrophysics Data System (ADS)

    Sah, Shagan; van Aardt, Jan A. N.; McKeown, Donald M.; Messinger, David W.

    2012-06-01

    Remote sensing can be used to rapidly generate land use maps for assisting emergency response personnel with resource deployment decisions and impact assessments. In this study we focus on constructing accurate land cover maps to map the impacted area in the case of a nuclear material release. The proposed methodology involves integration of results from two different approaches to increase classification accuracy. The data used included RapidEye scenes over Nine Mile Point Nuclear Power Station (Oswego, NY). The first step was building a coarse-scale land cover map from freely available, high temporal resolution, MODIS data using a time-series approach. In the case of a nuclear accident, high spatial resolution commercial satellites such as RapidEye or IKONOS can acquire images of the affected area. Land use maps from the two image sources were integrated using a probability-based approach. Classification results were obtained for four land classes - forest, urban, water and vegetation - using Euclidean and Mahalanobis distances as metrics. Despite the coarse resolution of MODIS pixels, acceptable accuracies were obtained using time series features. The overall accuracies using the fusion based approach were in the neighborhood of 80%, when compared with GIS data sets from New York State. The classifications were augmented using this fused approach, with few supplementary advantages such as correction for cloud cover and independence from time of year. We concluded that this method would generate highly accurate land maps, using coarse spatial resolution time series satellite imagery and a single date, high spatial resolution, multi-spectral image.

  11. Modeling to Support Groundwater Contaminant Boundaries for the Shoal Underground Nuclear Test

    SciTech Connect

    K. Pohlmann; G. Pohll; J. Chapman; A. Hassan; R. Carroll; C. Shirley

    2004-03-01

    The purpose of this work is to characterize groundwater flow and contaminant transport at the Shoal underground nuclear test through numerical modeling using site-specific hydrologic data. The ultimate objective is the development of a contaminant boundary, a model-predicted perimeter defining the extent of radionuclide-contaminated groundwater from the underground test throughout 1,000 years at a prescribed level of confidence. This boundary will be developed using the numerical models described here, after they are approved for that purpose by DOE and NDEP.

  12. Modeling to Support Groundwater Contaminant Boundaries for the Shoal Underground Nuclear Test

    SciTech Connect

    K. Pohlmann; G. Pohll; J. Chapman; A. Hassan; R. Carroll; C. Shirley

    2004-03-01

    Groundwater flow and radionuclide transport at the Shoal underground nuclear test are characterized using three-dimensional numerical models, based on site-specific hydrologic data. The objective of this modeling is to provide the flow and transport models needed to develop a contaminant boundary defining the extent of radionuclide-contaminated groundwater at the site throughout 1,000 years at a prescribed level of confidence. This boundary will then be used to manage the Project Shoal Area for the protection of the public and the environment.

  13. Nuclear β-catenin localization supports homology of feathers, avian scutate scales, and alligator scales in early development.

    PubMed

    Musser, Jacob M; Wagner, Günter P; Prum, Richard O

    2015-01-01

    Feathers are an evolutionary novelty found in all extant birds. Despite recent progress investigating feather development and a revolution in dinosaur paleontology, the relationship of feathers to other amniote skin appendages, particularly reptile scales, remains unclear. Disagreement arises primarily from the observation that feathers and avian scutate scales exhibit an anatomical placode-defined as an epidermal thickening-in early development, whereas alligator and other avian scales do not. To investigate the homology of feathers and archosaur scales we examined patterns of nuclear β-catenin localization during early development of feathers and different bird and alligator scales. In birds, nuclear β-catenin is first localized to the feather placode, and then exhibits a dynamic pattern of localization in both epidermis and dermis of the feather bud. We found that asymmetric avian scutate scales and alligator scales share similar patterns of nuclear β-catenin localization with feathers. This supports the hypothesis that feathers, scutate scales, and alligator scales are homologous during early developmental stages, and are derived from early developmental stages of an asymmetric scale present in the archosaur ancestor. Furthermore, given that the earliest stage of β-catenin localization in feathers and archosaur scales is also found in placodes of several mammalian skin appendages, including hair and mammary glands, we hypothesize that a common skin appendage placode originated in the common ancestor of all amniotes. We suggest a skin placode should not be defined by anatomical features, but as a local, organized molecular signaling center from which an epidermal appendage develops.

  14. Screening nucleotide binding to amino acid-coated supports by surface plasmon resonance and nuclear magnetic resonance.

    PubMed

    Cruz, Carla; Cabrita, Eurico J; Queiroz, João A

    2011-08-01

    Here, we describe a rapid and efficient screening method using surface plasmon resonance (SPR) and saturation transfer difference-nuclear magnetic resonance (STD-NMR) spectroscopy to yield information regarding the residues involved in nucleotide binding to amino acid-coated supports. The aim of this work was to explore the use of these spectroscopic techniques to study amino acid-nucleotide interactions in order to improve the binding specificity of the amino acid ligands used to purify plasmid DNA. For SPR, we present a strategy that immobilizes arginine and lysine on a surface as model supports, and we analyze binding responses when synthetic homo-deoxyoligonucleotides are injected over the amino acid surface. The binding responses are detectable and reproducible despite the small size of the immobilized amino acids. Using STD-NMR, we performed epitope mapping of homo-deoxyoligonucleotides bound to L-arginine-bisoxyran-Sepharose and L-lysine-Sepharose supports. Polynucleotide binding preferences differed; for example, polyC interacted preferentially through its backbone with the two supports, whereas polyT bound the supports through its thymine moiety. STD-NMR combined with SPR measurements was successfully used to screen amino acid-nucleotide interactions and determine the binding affinities of the complexes.

  15. Multi-Phased, Post-Accident Support of the Fukushima Dai-Ichi Nuclear Power Plant - 12246

    SciTech Connect

    Gay, Arnaud; Gillet, Philippe; Ytournel, Bertrand; Varet, Thierry; David, Laurent; Prevost, Thierry; Redonnet, Carol; Piot, Gregoire; Jouaville, Stephane; Pagis, Georges

    2012-07-01

    operation results to date. AREVA's response to the Fukushima Dai-Ichi crisis was multi-phased: emergency aid and relief supply was sent within days after the accident; AREVA-Veolia engineering teams designed and implemented a water treatment solution in record time, only 3 months; and AREVA continues to support TEPCO and propose solutions for waste management, soil remediation and decontamination of the Fukushima Dai-Ichi site. Despite the huge challenges, the Actiflo{sup TM}-Rad project has been a success: the water treatment unit started on time and performed as expected. The performance is the result of many key elements: AREVA expertise in radioactive effluents decontamination, Veolia know-how in water treatment equipments in crisis environment, and of course AREVA and Veolia teams' creativity. The project success is also due to AREVA and Veolia teams' reactivity and high level of commitment with engineering teams working 24/7 in Japan, France and Germany. AREVA and Veolia deep knowledge of the Japanese industry ensured that the multi-cultural exchanges were not an issue. Finally the excellent overall project management and execution by TEPCO and other Japanese stakeholders was very efficient. The emergency water treatment was a key step of the roadmap towards restoration from the accident at Fukushima Dai-Ichi that TEPCO designed and keeps executing with success. (authors)

  16. Density functional calculations in the automotive industry: Catalyst supports and hydrogen storage materials

    NASA Astrophysics Data System (ADS)

    Wolverton, Christopher

    2006-03-01

    In my talk, I will describe some uses of density functional theory (DFT) calculations in the research laboratory at Ford, and particularly highlight work that was inspired by, or performed in collaboration with Ken Hass. I begin with a discussion of past work on γ-Al2O3 catalyst support materials, but also discuss the current main focus of our group's activities: hydrogen storage materials. Catalyst Supports: In current three-way automotive catalysts, precious metals are often supported by the phase of aluminum oxide known as γ-Al2O3. Despite the ubiquitous nature of this oxide in current automobile catalysts, and a considerable amount of effort expended to understand this material, many questions about the phase stability and even crystal structure of γ-Al2O3 remain. DFT calculations have made significant progress in unraveling these unanswered questions, allowing one to construct realistic models of the supported catalysts materials. Hydrogen Storage Materials: One of the major bottlenecks to the widespread use of hydrogen-fueled vehicles is the ability to store sufficient energy on-board to enable vehicle attributes acceptable to customers. I will give a general introduction to the topic of hydrogen storage, and a broad survey of the various classes of hydrogen storage technologies, and point out some pros and cons associated with each class. Currently known technologies have insufficient usable energy densities, and I will describe how DFT calculations are aiding the search for improved high density storage materials.

  17. A decision analysis framework to support long-term planning for nuclear fuel cycle technology research, development, demonstration and deployment

    SciTech Connect

    Sowder, A.G.; Machiels, A.J.; Dykes, A.A.; Johnson, D.H.

    2013-07-01

    To address challenges and gaps in nuclear fuel cycle option assessment and to support research, develop and demonstration programs oriented toward commercial deployment, EPRI (Electric Power Research Institute) is seeking to develop and maintain an independent analysis and assessment capability by building a suite of assessment tools based on a platform of software, simplified relationships, and explicit decision-making and evaluation guidelines. As a demonstration of the decision-support framework, EPRI examines a relatively near-term fuel cycle option, i.e., use of reactor-grade mixed-oxide fuel (MOX) in U.S. light water reactors. The results appear as a list of significant concerns (like cooling of spent fuels, criticality risk...) that have to be taken into account for the final decision.

  18. Nuclear protein-coding genes support lungfish and not the coelacanth as the closest living relatives of land vertebrates.

    PubMed

    Brinkmann, Henner; Venkatesh, Byrappa; Brenner, Sydney; Meyer, Axel

    2004-04-06

    The colonization of land by tetrapod ancestors is one of the major questions in the evolution of vertebrates. Despite intense molecular phylogenetic research on this problem during the last 15 years, there is, until now, no statistically supported answer to the question of whether coelacanths or lungfish are the closest living relatives of tetrapods. We determined DNA sequences of the nuclear-encoded recombination activating genes (Rag1 and Rag2) from all three major lungfish groups, the Australian Neoceratodis forsteri, the South American Lepidosiren paradoxa and the African lungfish Protopterus dolloi, and the Indonesian coelacanth Latimeria menadoensis. Phylogenetic analyses of both the single gene and the concatenated data sets of RAG1 and RAG2 found that the lungfishes are the closest living relatives of the land vertebrates. These results are supported by high bootstrap values, Bayesian posterior probabilities, and likelihood ratio tests.

  19. A critical assembly designed to measure neutronic benchmarks in support of the space nuclear thermal propulsion program

    NASA Astrophysics Data System (ADS)

    Parma, Edward J.; Ball, Russell M.; Hoovler, Gary S.; Selcow, Elizabeth C.; Cerbone, Ralph J.

    1993-01-01

    A reactor designed to perform criticality experiments in support of the Space Nuclear Thermal Propulsion program is currently in operation at the Sandia National Laboratories' reactor facility. The reactor is a small, water-moderated system that uses highly enriched uranium particle fuel in a 19-element configuration. Its purpose is to obtain neutronic measurements under a variety of experimental conditions that are subsequently used to benchmark rector-design computer codes. Brookhaven National Laboratory, Babcock & Wilcox, and Sandia National Laboratories participated in determining the reactor's performance requirements, design, follow-on experimentation, and in obtaining the licensing approvals. Brookhaven National Laboratory is primarily responsible for the analytical support, Babcock & Wilcox the hardware design, and Sandia National Laboratories the operational safety. All of the team members participate in determining the experimentation requirements, performance, and data reduction. Initial criticality was achieved in October 1989. An overall description of the reactor is presented along with key design features and safety-related aspects.

  20. A critical assembly designed to measure neutronic benchmarks in support of the Space Nuclear Thermal Propulsion program

    NASA Astrophysics Data System (ADS)

    Parma, E. J.; Ball, R. M.; Hoovler, G. S.; Selcow, E. C.; Cerbone, R. J.

    1992-10-01

    A reactor designed to perform criticality experiments in support of the Space Nuclear Thermal Propulsion program is currently in operation at the Sandia National Laboratories' reactor facility. The reactor is a small, water-moderated system that uses highly enriched uranium particle fuel in a 19-element configuration. Its purpose is to obtain neutronic measurements under a variety of experimental conditions that are subsequently used to benchmark reactor-design computer codes. Brookhaven National Laboratory, Babcock & Wilcox, and Sandia National Laboratories participated in determining the reactor's performance requirements, design, follow on experimentation, and in obtaining the licensing approvals. Brookhaven National Laboratory is primarily responsible for the analytical support, Babcock & Wilcox the hardware design, and Sandia National Laboratories the operational safety. All of the team members participate in determining the experimentation requirements, performance, and data reduction. Initial criticality was achieved in October 1989. An over-all description of the reactor is presented along with key design features and safety-related aspects.

  1. Resonance Region Nuclear Data Analysis to Support Advanced Fuel Cycle Development

    SciTech Connect

    Dunn, Michael E; Derrien, Herve; Leal, Luiz C; Gil, Choong-Sup; Kim, D.

    2011-01-01

    The Oak Ridge National Laboratory (ORNL) and the Korean Atomic Energy Research Institute (KAERI) are performing collaborative research as part of a three-year United States (U.S.) / Republic of Korea (ROK) International Nuclear Energy Research Initiative (I-NERI) project to provide improved neutron cross-section data with uncertainty or covariance data important for advanced fuel cycle and nuclear safeguards applications. ORNL and KAERI have initiated efforts to prepare new cross-section evaluations for 240Pu, 237Np, and the stable Cm isotopes. At the current stage of the I-NERI project, ORNL has recently completed a preliminary resonance-region cross-section evaluation with covariance data for 240Pu and initiated resonance evaluation efforts for 237Np and 244Cm. Likewise, KAERI is performing corresponding high-energy cross-section analyses (i.e., above the resonance region) for the noted isotopes. The paper provides results pertaining to the new resonance region evaluation efforts with emphasis on the new 240Pu evaluation.

  2. Baseline Evaluations to Support Control Room Modernization at Nuclear Power Plants

    SciTech Connect

    Boring, Ronald L.; Joe, Jeffrey C.

    2015-02-01

    For any major control room modernization activity at a commercial nuclear power plant (NPP) in the U.S., a utility should carefully follow the four phases prescribed by the U.S. Nuclear Regulatory Commission in NUREG-0711, Human Factors Engineering Program Review Model. These four phases include Planning and Analysis, Design, Verification and Validation, and Implementation and Operation. While NUREG-0711 is a useful guideline, it is written primarily from the perspective of regulatory review, and it therefore does not provide a nuanced account of many of the steps the utility might undertake as part of control room modernization. The guideline is largely summative—intended to catalog final products—rather than formative—intended to guide the overall modernization process. In this paper, we highlight two crucial formative sub-elements of the Planning and Analysis phase specific to control room modernization that are not covered in NUREG-0711. These two sub-elements are the usability and ergonomics baseline evaluations. A baseline evaluation entails evaluating the system as-built and currently in use. The usability baseline evaluation provides key insights into operator performance using the control system currently in place. The ergonomics baseline evaluation identifies possible deficiencies in the physical configuration of the control system. Both baseline evaluations feed into the design of the replacement system and subsequent summative benchmarking activities that help ensure that control room modernization represents a successful evolution of the control system.

  3. Emergency/disaster medical support in the restoration project for the Fukushima nuclear power plant accident.

    PubMed

    Morimura, Naoto; Asari, Yasushi; Yamaguchi, Yoshihiro; Asanuma, Kazunari; Tase, Choichiro; Sakamoto, Tetsuya; Aruga, Tohru

    2013-12-01

    The Fukushima Daiichi Nuclear Power Plant (1F) suffered a series of radiation accidents after the Great East Japan Earthquake on 11 March 2011. In a situation where halting or delaying restoration work was thought to translate directly into a very serious risk for the entire country, it was of the utmost importance to strengthen the emergency and disaster medical system in addition to radiation emergency medical care for staff at the frontlines working in an environment that posed a risk of radiation exposure and a large-scale secondary disaster. The Japanese Association for Acute Medicine (JAAM) launched the 'Emergency Task Force on the Fukushima Nuclear Power Plant Accident' and sent physicians to the local response headquarters. Thirty-four physicians were dispatched as disaster medical advisors, response guidelines in the event of multitudinous injury victims were created and revised and, along with execution of drills, coordination and advice was given on transport of patients. Forty-nine physicians acted as directing physicians, taking on the tasks of triage, initial treatment and decontamination. A total of 261 patients were attended to by the dispatched physicians. None of the eight patients with external contamination developed acute radiation syndrome. In an environment where the collaboration between organisations in the framework of a vertically bound government and multiple agencies and institutions was certainly not seamless, the participation of the JAAM as the medical academic organisation in the local system presented the opportunity to laterally integrate the physicians affiliated with the respective organisations from the perspective of specialisation.

  4. Mapping regions in Ste5 that support Msn5-dependent and -independent nuclear export.

    PubMed

    Hu, Zhenhua; Wang, Yunmei; Yu, Lu; Mahanty, Sanjoy K; Mendoza, Natalia; Elion, Elaine A

    2016-04-01

    Careful control of the available pool of the MAPK scaffold Ste5 is important for mating-pathway activation and the prevention of inappropriate mating differentiation in haploid Saccharomyces cerevisiae. Ste5 shuttles constitutively through the nucleus, where it is degraded by a ubiquitin-dependent mechanism triggered by G1 CDK phosphorylation. Here we narrow-down regions of Ste5 that mediate nuclear export. Four regions in Ste5 relocalize SV40-TAgNLS-GFP-GFP from nucleus to cytoplasm. One region is N-terminal, dependent on exportin Msn5/Ste21/Kap142, and interacts with Msn5 in 2 hybrid assays independently of mating pheromone, Fus3, Kss1, Ptc1, the NLS/PM, and RING-H2. A second region overlaps the PH domain and Ste11 binding site and 2 others are on the vWA domain and include residues essential for MAPK activation. We find no evidence for dependence on Crm1/Xpo1, despite numerous potential nuclear export sequences (NESs) detected by LocNES and NetNES1.1 predictors. Thus, Msn5 (homolog of human Exportin-5) and one or more exportins or adaptor molecules besides Crm1/Xpo1 may regulate Ste5 through multiple recognition sites.

  5. General evidence supporting the hypothesis that Saccharomyces cerevisiae vaginal isolates originate from food industrial environments.

    PubMed

    Siccardi, Daniela; Rellini, Paolo; Corte, Laura; Bistoni, Francesco; Fatichenti, Fabrizio; Cardinali, Gianluigi

    2006-07-01

    Saccharomyces cerevisiae strains isolated from pregnant women were identified and characterized by molecular techniques which disclosed a wide chromosomal variability and possible segregations due to sporulation. The morphological analysis showed that very few strains were able to sporulate and generate pseudohyphae, whereas none produced proteases, raising some doubts on the importance of these characters in strain pathogenicity. The analysis of ethanol production revealed that these strains are quite similar to those found in fermentative plants, suggesting a possible derivation from the food industrial environment. Since the absence of relevant amounts of sugar does not confer selective advantage to strong fermentative metabolisms, these findings suggest that a metabolic adaptation to the vaginal environment did not occur yet.

  6. Creation of a Hyponatremia Registry Supported by an Industry-Derived Quality Control Methodology

    PubMed Central

    D., Giunta; N., Fuentes; V., Pazo; M. L., Posadas-Martínez; H., Michellangelo; G., Waisman; F., González Bernaldo De Quirós

    2010-01-01

    Background A clinical registry encompasses a selective set of rigorously collected and stored clinical data focused on a specific condition. Hyponatremia has multiple, complex underlying causes and is one of the most frequent laboratory abnormalities. No systematic registries of hyponatremic patients have been reported in the medical literature. The purpose of this project was to create a registry for hyponatremia in order to obtain epidemiological data that will help to better understand this condition. Objective This paper describes the creation of a registry for hyponatremia within a single institution that employs industry-based approaches for quality management to optimize data accuracy and completeness. Methods A prospective registry of incident hyponatremia cases was created for this study. A formalized statistically based quality control methodology was developed and implemented to analyze and monitor all the process indicators that were developed to ensure data quality. Results Between December 2006 and April 2009, 2443 episodes of hyponatremia were included. Six process indicators that reflect the integrity of the system were evaluated monthly, looking for variation that would suggest systematic problems. The graphical representation of the process measures through control charts allowed us to identify and subsequently address problems with maintaining the registry. Conclusion In this project we have created a novel hyponatremia registry. To ensure the quality of the data in this registry we have implemented a quality control methodology based on industrial principles that allows us to monitor the performance of the registry over time through process indicators in order to detect systematic problems. We postulate that this approach could be reproduced for other registries. PMID:23616856

  7. Exposure and genetics increase risk of beryllium sensitisation and chronic beryllium disease in the nuclear weapons industry

    SciTech Connect

    Van Dyke, M. V.; Martyny, John W.; Mroz, M. M.; Silveira, L. J.; Strand, M.; Cragle, D. L.; Tankersley, W. G.; Wells, S. M.; Newman, L. S.; Maier, L. A.

    2011-04-02

    Beryllium sensitisation (BeS) and chronic beryllium disease (CBD) are caused by exposure to beryllium with susceptibility affected by at least one well-studied genetic host factor, a glutamic acid residue at position 69 (E69) of the HLA-DPb chain (DPbE69). However, the nature of the relationship between exposure and carriage of the DPbE69 genotype has not been well studied. The goal of this study was to determine the relationship between DP{beta}E69 and exposure in BeS and CBD. Current and former workers (n=181) from a US nuclear weapons production facility, the Y-12 National Security Complex (Oak Ridge, Tennessee, USA), were enrolled in a case-control study including 35 individuals with BeS and 19 with CBD. HLA-DPB1 genotypes were determined by PCR-SSP. Beryllium exposures were assessed through worker interviews and industrial hygiene assessment of work tasks. After removing the confounding effect of potential beryllium exposure at another facility, multivariate models showed a sixfold (OR 6.06, 95% CI 1.96 to 18.7) increased odds for BeS and CBD combined among DP{beta}E69 carriers and a fourfold (OR 3.98, 95% CI 1.43 to 11.0) increased odds for those exposed over an assigned lifetime-weighted average exposure of 0.1 {micro}g/m{sup 3}. Those with both risk factors had higher increased odds (OR 24.1, 95% CI 4.77 to 122). DP{beta}E69 carriage and high exposure to beryllium appear to contribute individually to the development of BeS and CBD. Among workers at a beryllium-using facility, the magnitude of risk associated with either elevated beryllium exposure or carriage of DP{beta}E69 alone appears to be similar.

  8. Apparatus for supporting contactors used in extracting nuclear materials from liquids

    DOEpatents

    Leonard, Ralph A.; Frank, Robert C.

    1991-01-01

    Apparatus is provided for supporting one or more contactor stages used to remove radioactive materials from aqueous solutions. The contactor stages include a housing having an internal rotor, a motor secured to the top of the housing for rotating the rotor, and a drain in the bottom of the housing. The support apparatus includes two or more vertical members each secured to a ground support that is horizontal and perpendicular to the frame member, and a horizontally disposed frame member. The frame member may be any suitable shape, but is preferably a rectangular tube having substantially flat, spaced top and bottom surfaces separated by substantially vertical side surfaces. The top and bottom surfaces each have an opening through which the contactor housing is secured so that the motor is above the frame and the drain is below the frame during use.

  9. Method to develop data supporting consequence analyses of transporting nuclear materials in the United States

    SciTech Connect

    Reese, R.T.; Sandoval, R.P.

    1980-01-01

    The Transportation System Safety Evaluation (TSSE) program at Sandia National Laboratories' Transportation Technology Center was initiated to provide the necessary information on source terms for nuclear materials subjected to extreme environments. The techniques for derivation of source terms for the fuel alone has been described as well as the outline for package response. An additional facet of this problem is the development of analytical methods to describe the transport of the released radionuclides from the fuel rods to possible release points. This work is also covered in the TSSE program. Not all the work required will be performed or funded by Sandia; rather existing work will be sought out and ongoing work will be utilized in an attempt to unify the presentation of data and thus increase its usefulness.

  10. Microstructural and mineralogical characterization of selected shales in support of nuclear waste repository studies

    SciTech Connect

    Lee, S.Y.; Hyder, L.K.; Alley, P.D.

    1988-01-01

    Five shales were examined as part of the Sedimentary Rock Program evaluation of this medium as a potential host for a US civilian nuclear waste repository. The units selected for characterization were the Chattanooga Shale from Fentress County, Tennessee; the Pierre Shale from Gregory County, South Dakota; the Green River Formation from Garfield County, Colorado; and the Nolichucky Shale and Pumpkin Valley Shale from Roane County, Tennessee. The micromorphology and structure of the shales were examined by petrographic, scanning electron, and high-resolution transmission electron microscopy. Chemical and mineralogical compositions were studied through the use of energy-dispersive x-ray, neutron activation, atomic absorption, thermal, and x-ray diffraction analysis techniques. 18 refs., 12 figs., 2 tabs.

  11. Emergency/disaster medical support in the restoration project for the Fukushima nuclear power plant accident

    PubMed Central

    Morimura, Naoto; Asari, Yasushi; Yamaguchi, Yoshihiro; Asanuma, Kazunari; Tase, Choichiro; Sakamoto, Tetsuya; Aruga, Tohru

    2013-01-01

    The Fukushima Daiichi Nuclear Power Plant (1F) suffered a series of radiation accidents after the Great East Japan Earthquake on 11 March 2011. In a situation where halting or delaying restoration work was thought to translate directly into a very serious risk for the entire country, it was of the utmost importance to strengthen the emergency and disaster medical system in addition to radiation emergency medical care for staff at the frontlines working in an environment that posed a risk of radiation exposure and a large-scale secondary disaster. The Japanese Association for Acute Medicine (JAAM) launched the ‘Emergency Task Force on the Fukushima Nuclear Power Plant Accident’ and sent physicians to the local response headquarters. Thirty-four physicians were dispatched as disaster medical advisors, response guidelines in the event of multitudinous injury victims were created and revised and, along with execution of drills, coordination and advice was given on transport of patients. Forty-nine physicians acted as directing physicians, taking on the tasks of triage, initial treatment and decontamination. A total of 261 patients were attended to by the dispatched physicians. None of the eight patients with external contamination developed acute radiation syndrome. In an environment where the collaboration between organisations in the framework of a vertically bound government and multiple agencies and institutions was certainly not seamless, the participation of the JAAM as the medical academic organisation in the local system presented the opportunity to laterally integrate the physicians affiliated with the respective organisations from the perspective of specialisation. PMID:23184925

  12. Kwazulu-Natal minibus taxi drivers' perceptions on HIV and AIDS: transmission, prevention, support and effects on the industry.

    PubMed

    McHunu, Gugu; Ncama, Busisiwe; Naidoo, Joanne Rachel; Majeke, Sisana; Myeza, Thandazile; Ndebele, Thandiwe; Pillay, Padmini

    2012-11-01

    In South Africa, the minibus taxi drivers are largely becoming another high-risk category in the HIV and AIDS epidemic. Although previous studies have shown that knowledge of HIV and AIDS is relatively high among the taxi drivers it is still not clear how this sub-population perceive the support rendered to them with regard to HIV and AIDS prevention strategies. This study aimed to focus on this atypical workplace and explore the KwaZulu-Natal, minibus taxi drivers' perceptions on HIV and AIDS. In this study, qualitative methods were utilized to determine the minibus taxi drivers' understanding of HIV and AIDS infection, HIV prevention strategies, existing support strategies and effects of HIV and AIDS on the taxi industry. Focus-group discussions were conducted, to collect data. The results showed that even though the taxi drivers had some understanding on HIV and AIDS there was still a dire need for interventions that were geared towards addressing HIV-related needs of the drivers in this industry.

  13. Removal of pertechnetate from simulated nuclear waste streams using supported zerovalent iron

    SciTech Connect

    Darab, John; Amonette, Alexandra; Burke, Deborah; Orr, Robert; Ponder, Sherman; Schrick, Bettina; Mallouk, Thomas; Lukens, Wayne; Caulder, Dana; Shuh, David

    2007-07-11

    The application of nanoparticles of predominantly zerovalent iron (nanoiron), either unsupported or supported, to the separation and reduction of pertechnetate anions (TcO4-) from complex waste mixtures was investigated as an alternative approach to current waste-processing schemes. Although applicable to pertechnetate-containing waste streams in general, the research discussed here was directed at two specific potential applications at the U.S. Department of Energy's Hanford Site: (1) the direct removal of pertechnetate from highly alkaline solutions, typical of those found in Hanford tank waste, and (2) the removal of dilute pertechnetate from near-neutral solutions, typical of the eluate streams from commercial organic ion-exchange resins that may be used to remediate Hanford tank wastes. It was envisioned that both applications would involve the subsequent encapsulation of the loaded sorbent material into a separate waste form. A high surface area (>200 M2/g) base-stable, nanocrystalline zirconia was used as a support for nanoiron for tests with highly alkaline solutions, while a silica gel support was used for tests with near-neutral solutions. It was shown that after 24 h of contact time, the high surface area zirconia supported nanoiron sorbent removed about 50percent (K-d = 370 L/kg) of the pertechnetate from a pH 14 tank waste simulant containing 0.51 mM TCO4- and large concentrations of Na+, OH-, NO3-, and CO32- for a phase ratio of 360 L simulant per kg of sorbent. It was also shown that after 18 h of contact time, the silica-supported nanoiron removed>95percent pertechnetate from a neutral pH eluate simulant containing 0.076 mM TcO4_ for a phase ratio of 290 L/kg. It was determined that in all cases, nanoiron reduced the Tc(VII) to Tc(IV), or possibly to Tc(V), through a redox reaction. Finally, it was demonstrated that a mixture of 20 mass percent of the solid reaction products obtained from contacting zirconia- supported nanoiron with an alkaline

  14. Removal of Pertechnetate From Simulated Nuclear Waste Streams Using Supported Zerovalent Iron

    SciTech Connect

    Darab, J.G.; Amonette, A.B.; Burke, D.S.D.; Orr, R.D.; Ponder, S.M.; Schrick, B.; Mallouk, T.E.; Lukens, W.W.; Caulder, D.L.; Shuh, D.K.

    2009-06-02

    The application of nanoparticles of predominantly zerovalent iron (nanoiron), either unsupported or supported, to the separation and reduction of pertechnetate anions (TcO{sub 4{sup -}}) from complex waste mixtures was investigated as an alternative approach to current waste-processing schemes. Although applicable to pertechnetate-containing waste streams in general, the research discussed here was directed at two specific potential applications at the U.S. Department of Energy's Hanford Site: (1) the direct removal of pertechnetate from highly alkaline solutions, typical of those found in Hanford tank waste, and (2) the removal of dilute pertechnetate from near-neutral solutions, typical of the eluate streams from commercial organic ion-exchange resins that may be used to remediate Hanford tank wastes. It was envisioned that both applications would involve the subsequent encapsulation of the loaded sorbent material into a separate waste form. A high surface area (>200 m{sup 2}/g) base-stable, nanocrystalline zirconia was used as a support for nanoiron for tests with highly alkaline solutions, while a silica gel support was used for tests with near-neutral solutions. It was shown that after 24 h of contact time, the high surface area zirconia supported nanoiron sorbent removed about 50% (K{sub d} = 370 L/kg) of the pertechnetate from a pH 14 tank waste simulant containing 0.51 mM TcO{sub 4{sup -}} and large concentrations of Na{sup +}, OH{sup -}, NO{sub 3{sup -}}, and CO{sub 3{sup 2-}} for a phase ratio of 360 L simulant per kg of sorbent. It was also shown that after 18 h of contact time, the silica-supported nanoiron removed >95% pertechnetate from a neutral pH eluate simulant containing 0.076 mM TcO{sub 4{sup -}} for a phase ratio of 290 L/kg. It was determined that in all cases, nanoiron reduced the Tc(VII) to Tc(IV), or possibly to Tc(V), through a redox reaction. Finally, it was demonstrated that a mixture of 20 mass % of the solid reaction products obtained

  15. Identifying industrial best practices for the waste minimization of low-level radioactive materials

    SciTech Connect

    Levin, V.

    1996-04-01

    In US DOE, changing circumstances are affecting the management and disposal of solid, low-level radioactive waste (LLW). From 1977 to 1991, the nuclear power industry achieved major reductions in solid waste disposal, and DOE is interested in applying those practices to reduce solid waste at DOE facilities. Project focus was to identify and document commercial nuclear industry best practices for radiological control programs supporting routine operations, outages, and decontamination and decommissioning activities. The project team (DOE facility and nuclear power industry representatives) defined a Work Control Process Model, collected nuclear power industry Best Practices, and made recommendations to minimize LLW at DOE facilities.

  16. Generation of neutronic thermal data in support of space nuclear propulsion

    SciTech Connect

    Mughabghab, S.; Schmidt, E.; Ludewig, H.

    1993-01-01

    The scattering kernel data for [sup 7]LiH have been generated for the first time in the temperature range 50--1000 K. This is based on a phonon distribution function derived from both experimental data and theoretical calculations. A detailed study of the variation of the moderator temperature coefficient [alpha][sub m](T) with temperature, T, is carried out for a typical space nuclear reactor of the particle bed type. It is established that the moderator temperature coefficient due to chemical binding effects follows the relationship [alpha][sub m](T) = C F[sub v](H)[sup 1.6] where F[sub v](H) is the volume fraction of bound solid hydrogen and C is a normalization constant which depends on the moderator capture thermal cross section. The value 1.65 is to be compared with 1.54 [plus minus] 0.06 derived in a previous study where water scattering kernels are applied. For control and safety reasons, a minimization of this positive component temperature coefficient can be most effective by operating the moderator at high temperatures. Advantages of this approach are outlined. In addition, suggestions are made to render the overall temperature coefficient negative.

  17. Generation of neutronic thermal data in support of space nuclear propulsion

    SciTech Connect

    Mughabghab, S.; Schmidt, E.; Ludewig, H.

    1993-05-01

    The scattering kernel data for {sup 7}LiH have been generated for the first time in the temperature range 50--1000 K. This is based on a phonon distribution function derived from both experimental data and theoretical calculations. A detailed study of the variation of the moderator temperature coefficient {alpha}{sub m}(T) with temperature, T, is carried out for a typical space nuclear reactor of the particle bed type. It is established that the moderator temperature coefficient due to chemical binding effects follows the relationship {alpha}{sub m}(T) = C F{sub v}(H){sup 1.6} where F{sub v}(H) is the volume fraction of bound solid hydrogen and C is a normalization constant which depends on the moderator capture thermal cross section. The value 1.65 is to be compared with 1.54 {plus_minus} 0.06 derived in a previous study where water scattering kernels are applied. For control and safety reasons, a minimization of this positive component temperature coefficient can be most effective by operating the moderator at high temperatures. Advantages of this approach are outlined. In addition, suggestions are made to render the overall temperature coefficient negative.

  18. Geotechnical support and topical studies for nuclear waste geologic repositories: Annual report, Fiscal Year 1986

    SciTech Connect

    Not Available

    1986-11-01

    The multidisciplinary project was initiated in fiscal year 1986. It comprises two major interrelated parts: (1) Technical Assistance. This part of the project includes: (a) review of the progress of major projects in the DOE Office of Civilian Radioactive Waste Management Program and advise the Engineering and Geotechnology Division on significant technical issues facing each project; (b) analyze geotechnical data, reports, tests, surveys and plans for the different projects; (c) review and comment on major technical reports and other program documents such as site characterization plans and area characterization plans and (d) provide scientific and technical input at technical meetings. (2) Topical Studies. This activity comprises studies on scientific and technical topics, and issues of significance to in-situ testing, test analysis methods, and performance assessment of nuclear waste geologic repositories. The subjects of study were selected based on discussions with DOE staff. For fiscal year 1986, one minor and one major area of investigation were undertaken. The minor topic is a preliminary consideration and planning exercise for post-closure monitoring studies. The major topic, with subtasks involving various geoscience disciplines, is on the mechanical, hydraulic, geophysical and geochemical properties of fractures in geologic rock masses. The present report lists the technical reviews and comments made during the fiscal year and summarizes the technical progress of the topical studies.

  19. DOE Spent Nuclear Fuel Information in Support of TSPA-SR

    SciTech Connect

    H. H. Loo

    1999-08-01

    The Department of Energy (DOE) Office of Civilian Radioactive Waste Management (RW) has started the recommendation (SR) effort to show that Yucca Mountain could be selected as the first geologic repository for spent nuclear fuel (SNF) and high-level waste. One component of the site recommendation will be a total system performance assessment (TSPA), based on the design concept and the scientific data and analysis available, describing the repository's probable behavior relative to the overall system performance standards. Thus, all the data collected from the Exploratory Studies Facilities to-date have been incorporated into the latest TSPA model. To ensure that the DOE-owned SNF continues to be acceptable for disposal in the repository, it will be included in the TSPA-SR evaluation. A number of parameters are needed in the TSPA-SR models to predict the performance of the DOE-owned SNF materials placed into the potential repository. This report documents all of the basis and/or derivation for each of these parameters. A number of properties were not readily available at the time the TSPA-SR data were requested. Thus, expert judgement and opinion were used to determine a best property value. The performance of the DOE-owned SNF will be published as part of the TSPA-SR report.

  20. Supporting Technology for Chain of Custody of Nuclear Weapons and Materials throughout the Dismantlement and Disposition Processes

    SciTech Connect

    Bunch, Kyle J.; Jones, Anthony M.; Ramuhalli, Pradeep; Benz, Jacob M.; Denlinger, Laura Schmidt

    2014-05-04

    signatures of sealed metallic containers can be used to rapidly confirm the presence of specific components on a yes/no basis without revealing classified information. PNNL researchers have also used ultrasonic measurements to obtain images of material microstructures which may be used as templates or unique identifiers of treaty-limited items. Such alternative technologies are suitable for application in various stages of weapons dismantlement and often include the advantage of an inherent information barrier due to the inability to extract classified weapon design information from the collected data. As a result, these types of technologies complement radiation-based verification methods for arms control. This article presents an overview of several alternative verification technologies that are suitable for supporting a future, broader and more intrusive arms control regime that spans the nuclear weapons disarmament lifecycle. The general capabilities and limitations of each verification modality are discussed and example technologies are presented. Potential applications are defined in the context of the nuclear material and weapons lifecycle. Example applications range from authentication (e.g., tracking and signatures within the chain of custody from downloading through weapons storage, unclassified templates and unique identification) to verification of absence and final material disposition.

  1. Ergonomics support for local initiative in improving safety and health at work: International Labour Organization experiences in industrially developing countries.

    PubMed

    Kawakami, T; Kogi, K

    2005-04-15

    Ergonomics has played essential roles in the technical cooperation activities of the International Labour Organization (ILO) in occupational safety and health in industrially developing countries. Ergonomics support focusing on practical day-to-day needs at the grass-root workplace has strengthened the local initiative in improving safety and health. Practical action-tools such as ergonomics checklists, local good example photos and group discussions have assisted workers and employers in identifying feasible solutions using locally available resources. Direct participation of workers and employers has been promoted in ergonomics training aimed at immediate solutions. ILO Guidelines on Occupational Safety and Health Management Systems have played increasingly important roles in the systematic planning of local improvement actions. Policy-level programmes to develop network support mechanisms to the grass-root workplace were essential for following up and sustaining local achievements. Practical ergonomics support tools, such as action checklists and low-cost improvement guides, should be developed and widely applied so as to reach grass-root levels and help local people create safer and healthier workplaces.

  2. Lessons Learned in Over a Decade of Technical Support for U.S. Nuclear Cyber Security Programmes

    SciTech Connect

    Glantz, Clifford S.; Landine, Guy P.; Craig, Philip A.; Bass, Robert B.

    2013-09-05

    Pacific Northwest National Laboratory’s (PNNL) nuclear cyber security team has been providing technical support to the U.S. Nuclear Regulatory Commission (NRC) since 2002. This team has provided cyber security technical experties in conducting cyber security inspections, developing of regulatory rules and guidance, reviewing facility cyber security plans, developing inspection guidance, and developing and teaching NRC inspectors how to conduct cyber security assessments. The extensive experience the PNNL team has gathered has allowed them to compile a lenghty list of recommendations on how to improve cyber security programs and conduct assessments. A selected set of recommendations are presented, including the need to: integrate an array of defenisve strategies into a facility’s cyber security program, coordinate physical and cyber security activities, train phycial security forces to resist a cyber-enabled physical attack, improve estimates of the consequences of a cyber attack, properly resource cyber security assessments, appropropriately account for insider threats, routinely monitor security devices for potential attacks, supplement compliance-based requirements with risk-based decision making, and introduce the concept of resilience into cyber security programs.

  3. Self-heating of dried industrial wastewater sludge: lab-scale investigation of supporting conditions.

    PubMed

    Della Zassa, M; Biasin, A; Zerlottin, M; Refosco, D; Canu, P

    2013-06-01

    We studied the reactivity of dried sludge produced by treatment of wastewater, mainly from tanneries. The solids transformations have been first characterized with thermal analysis (TGA and DSC) proving that exothermic transformation takes place at fairly low temperature, before the total organic combustion that occurs in air above 400°C. The onset of low temperature reactions depends on the heating rate and it can be below 100°C at very small heating rate. Then, we reproducibly determined the conditions to trigger dried sludge self-heating at the laboratory scale, on samples in the 0.2-0.3 kg size. Thermal insulation, some aeration and addition of water are key factors. Mastering the self-heating at this scale allows more detailed investigations as well as manipulation of conditions, to understand its nature, course and remediation. Here we report proves and discussions on the role of air, water, particle size, porosity and biological activity, as well as proving that also dried sludge from similar sources lead to self-heating. Tests demonstrate that air and water are simultaneously required for significant self-heating to occur. They act in diverging directions, both triggering the onset of the reactions and damping the temperature rise, by supporting heat loss. The higher the O2 concentration, the higher the solids heating rate. More added water prolongs the exothermic phase. Further additions of water can reactivate the material. Water emphasizes the exothermic processes, but it is not sufficient to start it in an air-free atmosphere. The initial solid moisture concentration (between 8% and 15%) affects the onset of self-heating as intuitive. The sludge particles size strongly determines the strength and extent of the heat release, indicating that surface reactions are taking place. In pelletized particles, limitations to water and air permeability mitigates the reaction course.

  4. The National Atmospheric Release Advisory Center (NARAC) Modeling and Decision Support System for Radiological and Nuclear Emergency Preparedness and Response

    SciTech Connect

    Nasstrom, J S; Sugiyama, G; Baskett, R; Larsen, S; Bradley, M

    2005-04-01

    This paper describes the tools and services provided by the National Atmospheric Release Advisory Center (NARAC) at Lawrence Livermore National Laboratory (LLNL) for modeling the impacts of airborne hazardous materials. NARAC provides atmospheric plume modeling tools and services for chemical, biological, radiological, and nuclear airborne hazards. NARAC can simulate downwind effects from a variety of scenarios, including fires, industrial and transportation accidents, radiation dispersal device explosions, hazardous material spills, sprayers, nuclear power plant accidents, and nuclear detonations. NARAC collaborates with several government agencies and laboratories in order to accomplish its mission. The NARAC suite of software tools include simple stand-alone, local-scale plume modeling tools for end-user's computers, and Web- and Internet-based software to access advanced modeling tools and expert analyses from the national center at LLNL. Initial automated, 3-D predictions of plume exposure limits and protective action guidelines for emergency responders and managers are available from the center in 5-10 minutes. These can be followed immediately by quality-assured, refined analyses by 24 x 7 on-duty or on-call NARAC staff. NARAC continues to refine calculations using updated on-scene information, including measurements, until all airborne releases have stopped and the hazardous threats are mapped and impacts assessed. Model predictions include the 3-D spatial and time-varying effects of weather, land use, and terrain, on scales from the local to regional to global. Real-time meteorological data and forecasts are provided by redundant communications links to the U.S. National Oceanic and Atmospheric Administration (NOAA), U.S. Navy, and U.S. Air Force, as well as an in-house mesoscale numerical weather prediction model. NARAC provides an easy-to-use Geographical Information System (GIS) for display of plume predictions with affected population counts and

  5. Requirements for a Dynamic Solvent Extraction Module to Support Development of Advanced Technologies for the Recycle of Used Nuclear Fuel

    SciTech Connect

    Jack Law; Veronica Rutledge; Candido Pereira; Jackie Copple; Kurt Frey; John Krebs; Laura Maggos; Kevin Nichols; Kent Wardle; Pratap Sadasivan; Valmor DeAlmieda; David Depaoli

    2011-06-01

    The Department of Energy's Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program has been established to create and deploy next generation, verified and validated nuclear energy modeling and simulation capabilities for the design, implementation, and operation of future nuclear energy systems to improve the U.S. energy security. As part of the NEAMS program, Integrated Performance and Safety Codes (IPSC's) are being produced to significantly advance the status of modeling and simulation of energy systems beyond what is currently available to the extent that the new codes be readily functional in the short term and extensible in the longer term. The four IPSC areas include Safeguards and Separations, Reactors, Fuels, and Waste Forms. As part of the Safeguards and Separations (SafeSeps) IPSC effort, interoperable process models are being developed that enable dynamic simulation of an advanced separations plant. A SafeSepss IPSC 'toolkit' is in development to enable the integration of separation process modules and safeguards tools into the design process by providing an environment to compose, verify and validate a simulation application to be used for analysis of various plant configurations and operating conditions. The modules of this toolkit will be implemented on a modern, expandable architecture with the flexibility to explore and evaluate a wide range of process options while preserving their stand-alone usability. Modules implemented at the plant-level will initially incorporate relatively simple representations for each process through a reduced modeling approach. Final versions will incorporate the capability to bridge to subscale models to provide required fidelity in chemical and physical processes. A dynamic solvent extraction model and its module implementation are needed to support the development of this integrated plant model. As a stand-alone application, it will also support solvent development of extraction flowsheets and integrated

  6. A Characteristic Back Support Structure in the Bisphenol A-Binding Pocket in the Human Nuclear Receptor ERRγ

    PubMed Central

    Liu, Xiaohui; Matsushima, Ayami; Shimohigashi, Miki; Shimohigashi, Yasuyuki

    2014-01-01

    The endocrine disruptor bisphenol A (BPA) affects various genes and hormones even at merely physiological levels. We recently demonstrated that BPA binds strongly to human nuclear receptor estrogen-related receptor (ERR) γ and that the phenol-A group of BPA is in a receptacle pocket with essential amino acid residues to provide structural support at the backside. This led BPA to bind to ERRγ in an induced-fit-type binding mode, for example, with a rotated motion of Val313 to support the Tyr326-binding site. A similar binding mechanism appears to occur at the binding site of the BPA phenol-B ring. X-ray crystal analysis of the ERRγ-ligand-binding domain/BPA complex suggested that the ERRγ receptor residues Leu342, Leu345, Asn346, and Ile349 function as intrinsic binding sites of the BPA phenol-B, whereas Leu265, Leu268, Ile310, Val313, Leu324, Tyr330, Lys430, Ala431, and His434 work as structural elements to assist these binding sites. In the present study, by evaluating the mutant receptors replaced by a series of amino acids, we demonstrated that a finely assembled structural network indeed exists around the two adjacent Leu342-Asn346 and Leu345-Ile349 ridges on the same α-helix 7 (H7), constructing a part of the binding pocket structure with back support residues for the BPA phenol-B ring. The results reveal that the double-layer binding sites, namely, the ordinary ligand binding sites and their back support residues, substantiate the strong binding of BPA to ERRγ. When ERRγ-Asn346 was replaced by the corresponding Gly and Tyr in ERRα and ERRβ, respectively, the binding affinity of BPA and even 4-hydroxytamxifen (4-OHT) is much reduced. Asn346 was found to be one of the residues that make ERRγ to be exclusive to BPA. PMID:24978476

  7. A characteristic back support structure in the bisphenol A-binding pocket in the human nuclear receptor ERRγ.

    PubMed

    Liu, Xiaohui; Matsushima, Ayami; Shimohigashi, Miki; Shimohigashi, Yasuyuki

    2014-01-01

    The endocrine disruptor bisphenol A (BPA) affects various genes and hormones even at merely physiological levels. We recently demonstrated that BPA binds strongly to human nuclear receptor estrogen-related receptor (ERR) γ and that the phenol-A group of BPA is in a receptacle pocket with essential amino acid residues to provide structural support at the backside. This led BPA to bind to ERRγ in an induced-fit-type binding mode, for example, with a rotated motion of Val313 to support the Tyr326-binding site. A similar binding mechanism appears to occur at the binding site of the BPA phenol-B ring. X-ray crystal analysis of the ERRγ-ligand-binding domain/BPA complex suggested that the ERRγ receptor residues Leu342, Leu345, Asn346, and Ile349 function as intrinsic binding sites of the BPA phenol-B, whereas Leu265, Leu268, Ile310, Val313, Leu324, Tyr330, Lys430, Ala431, and His434 work as structural elements to assist these binding sites. In the present study, by evaluating the mutant receptors replaced by a series of amino acids, we demonstrated that a finely assembled structural network indeed exists around the two adjacent Leu342-Asn346 and Leu345-Ile349 ridges on the same α-helix 7 (H7), constructing a part of the binding pocket structure with back support residues for the BPA phenol-B ring. The results reveal that the double-layer binding sites, namely, the ordinary ligand binding sites and their back support residues, substantiate the strong binding of BPA to ERRγ. When ERRγ-Asn346 was replaced by the corresponding Gly and Tyr in ERRα and ERRβ, respectively, the binding affinity of BPA and even 4-hydroxytamxifen (4-OHT) is much reduced. Asn346 was found to be one of the residues that make ERRγ to be exclusive to BPA.

  8. Exploring the Relationship of Organizational Culture and Implicit Leadership Theory to Performance Differences in the Nuclear and Fossil Energy Industry

    NASA Astrophysics Data System (ADS)

    Cravey, Kristopher J.

    Notable performance differences exist between nuclear and fossil power generation plants in areas such as safety, outage duration efficiency, and capacity factor. This study explored the relationship of organizational culture and implicit leadership theory to these performance differences. A mixed methods approach consisting of quantitative instruments, namely the Organizational Culture Assessment Instrument and the GLOBE Leadership Scales, and qualitative interviews were used in this study. Subjects were operations middle managers in a U.S. energy company that serves nuclear or fossil power plants. Results from the quantitative instruments revealed no differences between nuclear and fossil groups in regards to organizational culture types and implicit leadership theories. However, the qualitative results did reveal divergence between the two groups in regards to what is valued in the organization and how that drives behaviors and decision making. These organizational phenomenological differences seem to explain why performance differences exist between nuclear and fossil plants because, ultimately, they affect how the organization functions.

  9. Bonding with the Nuclear Industry: A Technical Communication Professor and His Students Partner With Y-12 National Security Complex

    ERIC Educational Resources Information Center

    Hirst, Russel

    2016-01-01

    This article describes how a special kind of academe-industry collaboration--based on a joint appointment agreement between a university and an industry site--was set up, promoted, and experienced by a professor of technical communication and his student interns. To illustrate the nature and value of this kind of collaboration, the article…

  10. A multi-temporal fusion-based approach for land cover mapping in support of nuclear incident response

    NASA Astrophysics Data System (ADS)

    Sah, Shagan

    An increasingly important application of remote sensing is to provide decision support during emergency response and disaster management efforts. Land cover maps constitute one such useful application product during disaster events; if generated rapidly after any disaster, such map products can contribute to the efficacy of the response effort. In light of recent nuclear incidents, e.g., after the earthquake/tsunami in Japan (2011), our research focuses on constructing rapid and accurate land cover maps of the impacted area in case of an accidental nuclear release. The methodology involves integration of results from two different approaches, namely coarse spatial resolution multi-temporal and fine spatial resolution imagery, to increase classification accuracy. Although advanced methods have been developed for classification using high spatial or temporal resolution imagery, only a limited amount of work has been done on fusion of these two remote sensing approaches. The presented methodology thus involves integration of classification results from two different remote sensing modalities in order to improve classification accuracy. The data used included RapidEye and MODIS scenes over the Nine Mile Point Nuclear Power Station in Oswego (New York, USA). The first step in the process was the construction of land cover maps from freely available, high temporal resolution, low spatial resolution MODIS imagery using a time-series approach. We used the variability in the temporal signatures among different land cover classes for classification. The time series-specific features were defined by various physical properties of a pixel, such as variation in vegetation cover and water content over time. The pixels were classified into four land cover classes - forest, urban, water, and vegetation - using Euclidean and Mahalanobis distance metrics. On the other hand, a high spatial resolution commercial satellite, such as RapidEye, can be tasked to capture images over the

  11. A molecular phylogeny of nuclear and mitochondrial sequences in Hymenolepis nana (Cestoda) supports the existence of a cryptic species.

    PubMed

    Macnish, M G; Morgan-Ryan, U M; Monis, P T; Behnke, J M; Thompson, R C A

    2002-12-01

    Since isolates of Hymenolepis nana infecting humans and rodents are morphologically indistinguishable, the only way they can be reliably identified is by comparing the parasite in each host using molecular tools. In the current study, isolates of H. nana from rodent and human hosts from a broad geographical range were sequenced at the ribosomal first internal transcribed spacer (ITS1), the mitochondrial cytochrome c oxidase subunit 1 (C01) gene and the nuclear paramyosin gene loci. Twenty-three isolates of H. nana were sequenced at the ITS1 locus and this confirmed the existence of spacers which, although similar in length (approximately 646 bp), differed in their primary sequences which led to the separation of the isolates into 2 clusters when analysed phylogenetically. This sequence variation was not, however, related to the host of origin of the isolate, thus was not a marker of genetic distinction between H. nana from rodents and humans. Sequencing of a 444 bp fragment of the mitochondrial cytochrome c oxidase 1 gene (C01) in 9 isolates of H. nana from rodents and 6 from humans identified a phylogenetically supported genetic divergence of approximately 5% between some mouse and human isolates. This suggests that H. nana is a species complex, or 'cryptic' species (=morphologically identical yet genetically distinct). A small segment of the nuclear gene, paramyosin, (625 bp or 840 bp) was sequenced in 4 mouse and 3 human isolates of H. nana. However, this gene did not provide the level of heterogeneity required to distinguish between isolates from rodent and human hosts. From the results obtained from faster evolving genes, and the epidemiological evidence, we believe that the life-cycle of H. nana that exists in the north-west of Western Australia is likely to involve mainly 'human to human' transmission.

  12. Long-term storage facility for reactor compartments in Sayda Bay - German support for utilization of nuclear submarines in Russia

    SciTech Connect

    Wolff, Dietmar; Voelzke, Holger; Weber, Wolfgang; Noack, Volker; Baeuerle, Guenther

    2007-07-01

    The German-Russian project that is part of the G8 initiative on Global Partnership Against the Spread of Weapons and Materials of Mass Destruction focuses on the speedy construction of a land-based interim storage facility for nuclear submarine reactor compartments at Sayda Bay near Murmansk. This project includes the required infrastructure facilities for long-term storage of about 150 reactor compartments for a period of about 70 years. The interim storage facility is a precondition for effective activities of decommissioning and dismantlement of almost all nuclear-powered submarines of the Russian Northern Fleet. The project also includes the establishment of a computer-assisted waste monitoring system. In addition, the project involves clearing Sayda Bay of other shipwrecks of the Russian navy. On the German side the project is carried out by the Energiewerke Nord GmbH (EWN) on behalf of the Federal Ministry of Economics and Labour (BMWi). On the Russian side the Kurchatov Institute holds the project management of the long-term interim storage facility in Sayda Bay, whilst the Nerpa Shipyard, which is about 25 km away from the storage facility, is dismantling the submarines and preparing the reactor compartments for long-term interim storage. The technical monitoring of the German part of this project, being implemented by BMWi, is the responsibility of the Federal Institute for Materials Research and Testing (BAM). This paper gives an overview of the German-Russian project and a brief description of solutions for nuclear submarine disposal in other countries. At Nerpa shipyard, being refurbished with logistic and technical support from Germany, the reactor compartments are sealed by welding, provided with biological shielding, subjected to surface treatment and conservation measures. Using floating docks, a tugboat tows the reactor compartments from Nerpa shipyard to the interim storage facility at Sayda Bay where they will be left on the on-shore concrete

  13. Attracting students to nuclear careers: INPO educational assistance program

    SciTech Connect

    Dunkle, M.

    1981-10-01

    The utility industry is responding to a manpower shortage of 2000 at nuclear plants with a concerted analysis of regional training centers and educational assistance programs through the Institute of Nuclear Power Operations (INPO). University support and cooperation are generally strong. The INPO program includes undergraduate- and graduate-level scholarships and fellowships. (DCK)

  14. Application of laboratory data from small-scale simulators to human performance issues in the nuclear industry

    SciTech Connect

    Spettell, C.M.

    1986-01-01

    Laboratory analogs of nuclear power plant tasks were simulated on personal computers in two experimental studies. Human performance data were collected during each experimental study. The goal of the first experiment was to validate a quantitative model of dependence among human errors during testing, calibration, and maintenance activities. This model, the Multiple Sequential Failure (MSF) model (NUREG/CR-2211) has been used to quantify dependent human error failure probabilities for human reliability analyses in Probabilistic Risk Assessments (PRAs). The goal of the second experiment was to examine the relationship among psychological and behavioral characteristics of individuals and their performance at controlling a simulated nuclear power plant. These studies demonstrated the usefulness of the experimental psychology approach for validating models of human performance at nuclear power plant tasks.

  15. Characterizing substrate–surface interactions on alumina-supported metal catalysts by dynamic nuclear polarization-enhanced double-resonance NMR spectroscopy [Characterizing substrate-surface interactions on alumina supported metal catalysts by DNP-enhanced double-resonance NMR spectroscopy

    DOE PAGES

    Perras, Frederic A.; Padmos, J. Daniel; Johnson, Robert L.; ...

    2017-01-23

    The characterization of nanometer-scale interactions between carbon-containing substrates and alumina surfaces is of paramount importance to industrial and academic catalysis applications, but it is also very challenging. Here, we demonstrate that dynamic nuclear polarization surface-enhanced NMR spectroscopy (DNP SENS) allows the unambiguous description of the coordination geometries and conformations of the substrates at the alumina surface through high-resolution measurements of 13C–27Al distances. We apply this new technique to elucidate the molecular-level geometry of 13C-enriched methionine and natural abundance poly(vinyl alcohol) adsorbed on γ-Al2O3-supported Pd catalysts, and we support these results with element-specific X-ray absorption near-edge measurements. Furthermore, this work clearlymore » demonstrates a surprising bimodal coordination of methionine at the Pd–Al2O3 interface.« less

  16. Interoperability of Materials Database Systems in Support of Nuclear Energy Development and Potential Applications for Fuel Cell Material Selection

    DOE PAGES

    Lin, Lianshan; Austin, Timothy; Ren, Weiju

    2015-01-01

    Materials database interoperability has been of great interest in recent years for information exchange in support of research and development (R&D). In response to data and knowledge sharing needs of the GenIV International Forum (GIF) for global collaboration in nuclear energy R&D, the European Commission JRC Institute for Energy and Transport (JRC-IET) and the Oak Ridge National Laboratory (ORNL) have established a materials database interoperability project that develops techniques for automated materials data exchange between systems hosted at the two institutes MatDB Online at JRC IET and the Gen IV Materials Handbook at ORNL, respectively. The work to enable automatedmore » exchange of data between the two systems leverages the XML data import and export functionalities of both systems in combination with recently developed standards for engineering materials data. The preliminary results of data communication between the two systems have demonstrated the feasibility and efficiency of materials database interoperability, which constructs an interoperation framework that can be seamlessly integrated into the high-throughput First Principles material databases and thus advance the discovery of novel materials in fuel cell applications.« less

  17. Interoperability of Materials Database Systems in Support of Nuclear Energy Development and Potential Applications for Fuel Cell Material Selection

    SciTech Connect

    Lin, Lianshan; Austin, Timothy; Ren, Weiju

    2015-01-01

    Materials database interoperability has been of great interest in recent years for information exchange in support of research and development (R&D). In response to data and knowledge sharing needs of the GenIV International Forum (GIF) for global collaboration in nuclear energy R&D, the European Commission JRC Institute for Energy and Transport (JRC-IET) and the Oak Ridge National Laboratory (ORNL) have established a materials database interoperability project that develops techniques for automated materials data exchange between systems hosted at the two institutes MatDB Online at JRC IET and the Gen IV Materials Handbook at ORNL, respectively. The work to enable automated exchange of data between the two systems leverages the XML data import and export functionalities of both systems in combination with recently developed standards for engineering materials data. The preliminary results of data communication between the two systems have demonstrated the feasibility and efficiency of materials database interoperability, which constructs an interoperation framework that can be seamlessly integrated into the high-throughput First Principles material databases and thus advance the discovery of novel materials in fuel cell applications.

  18. Improved performance of a biomaterial-based cation exchanger for the adsorption of uranium(VI) from water and nuclear industry wastewater.

    PubMed

    Anirudhan, T S; Radhakrishnan, P G

    2009-03-01

    The amine-modified polyhydroxyethylmethacrylate (poly(HEMA))-grafted biomaterial (tamarind fruit shell, TFS) carrying carboxyl functional groups at the chain end (PGTFS-COOH) was prepared and used as an adsorbent for the removal of uranium(VI) from water and nuclear industry wastewater. FTIR spectral analysis revealed that U(VI) ions and PGTFS-COOH formed a chelate complex. The adsorption process was relatively fast, requiring only 120 min to attain equilibrium. The adsorption kinetic data were best described by the pseudo-second-order equation. The equilibrium adsorption data were correlated with the Sips isotherm model. The maximum U(VI) ions uptake with PGTFS-COOH was estimated to be 100.79 mg/g. The complete removal of 10mg/L U(VI) from simulated nuclear industry wastewater was achieved by 3.5 g/L PGTFS-COOH. The reusability of the adsorbent was demonstrated over 4 cycles using NaCl (1.0M)+HCl (0.5M) solution mixture to de-extract the U(VI). The results show that the PGTFS-COOH tested is very promising for the recovery of U(VI) from water and wastewater.

  19. U.S. Department of Energy, Defense Programs, activities to support the safe, secure dismantlement of nuclear weapons in the Former Soviet Union

    SciTech Connect

    Turner, J.

    1993-12-31

    In September 1991 President Bush announced sweeping cuts in the US nuclear weapon stockpile as well as changes in deployment to remove significant numbers of weapons from alert status and to return to the US for storage many weapons formerly based abroad in US sites. In October 1991 President Gorbachev announced similar moves for the Soviet Union. Even though the Gorbachev announcement represented a substantial step forward in reducing tension between the US and the Soviet Union, the US continued to be concerned about the deteriorating situation in the Soviet Union and the prospects for internal stability. As a result, in November 1991 the Administration began talks with the Soviets in a number of areas including field disablement of nuclear weapons to prevent unauthorized use, emergency response in the event of a weapons accident, and command and control of nuclear weapons. The Nunn-Lugar legislation assured assistance to the Soviet Union in the safe, secure dismantlement (SSD) of weapons to implement the Gorbachev commitment and in the development of measures to prevent the proliferation of weapons of mass destruction. The Department of Energy (DOE) is supporting and collaborating with the Department of Defense (DOD) in several areas due to the DOE responsibilities for developing, assembling, and dismantling US warheads and as the custodian of the nuclear materials stockpile. Russia, as the successor state to the Soviet Union, controls the nuclear weapons of the Former Soviet Union. Thus, DOE`s nuclear weapon and nuclear materials expertise are being applied particularly to Russia. However, the DOE is also providing assistance to Belarus and is prepared to assist Ukraine and Kazakhstan as well if agreements can be reached. In this paper, the DOE SSD activities in support of DOD as the US Executive Agent will be discussed. Two areas will not be covered, namely, DOD activities and the purchase of highly enriched uranium.

  20. Space teleoperation research. American Nuclear Society Executive conference: remote operations and robotics in the nuclear industry; remote maintenance in other hostile environments

    SciTech Connect

    Meintel, A.J. Jr.; Will, R.W.

    1985-01-01

    This presentation consists of four sections. The first section is a brief introduction to the NASA Space Program. The second portion summarizes the results of a congressionally mandated study of automation and robotics for Space Station. The third portion presents a number of concepts for space teleoperator systems. The remainder of the presentation describes Langley Research Center's teleoperator/robotic research to support remote space operations. 16 refs.

  1. Space teleoperation research. American Nuclear Society Executive conference: Remote operations and robotics in the nuclear industry; remote maintenance in other hostile environments

    NASA Technical Reports Server (NTRS)

    Meintel, A. J., Jr.; Will, R. W.

    1985-01-01

    This presentation consists of four sections. The first section is a brief introduction to the NASA Space Program. The second portion summarized the results of a congressionally mandated study of automation and robotics for space station. The third portion presents a number of concepts for space teleoperator systems. The remainder of the presentation describes Langley Research Center's teleoperator/robotic research to support remote space operations.

  2. Current significant challenges in the decommissioning and environmental remediation of radioactive facilities: A perspective from outside the nuclear industry.

    PubMed

    Gil-Cerezo, V; Domínguez-Vilches, E; González-Barrios, A J

    2017-05-01

    This paper presents the results of implementing an extrajudicial environmental mediation procedure in the socioenvironmental conflict associated with routine operation of the El Cabril Disposal Facility for low- and medium- activity radioactive waste (Spain). We analyse the socio-ethical perspective of this facility's operation with regard to its nearby residents, detailing the structure and development of the environmental mediation procedure through the participation of society and interested parties who are or may become involved in such a conflict. The research, action, and participation method was used to apply the environmental mediation procedure. This experience provides lessons that could help improve decision-making processes in nuclear or radioactive facility decommissioning projects or in environmental remediation projects dealing with ageing facilities or with those in which nuclear or radioactive accidents/incidents may have occurred.

  3. A Nuclear Energy Renaissance in the U.S.?

    SciTech Connect

    Kessler, Carol E.; Mahy, Heidi A.; Ankrum, Al; Buelt, James L.; Branch, Kristi M.; Phillips, Jon R.

    2008-01-01

    Is it time for a nuclear energy renaissance? Among other things, nuclear power is a carbon neutral source of base load power. With the growth in energy use expected over the next 20 years and the growing negative impacts of global climate changes, the cost of oil and gas, energy security and diversity concerns, and progress on advanced reactor designs, it may be the right time for nuclear power to enter a new age of growth. Asia and Russia are both planning for a nuclear renaissance. In Europe, Finland and France have both taken steps to pursue new nuclear reactors. U.S. utilities are preparing for orders of new reactors; one submitted a request to the U.S. Nuclear Regulatory Commission (NRC) to review its request to construct a new reactor on an existing site. What has the industry been doing since nuclear energy was birthed in the 1960s? In those days a bold new industry boasted that nuclear power in the United States was going to be “too cheap to meter”, but as we all know this did not come about for many reasons. Eventually, it became clear that industry had neglected to do its homework. Critiques of the industry were made on safety, security, environment, economic competitiveness (without government support), and nonproliferation. All of these factors need to be effectively addressed to promote the confidence and support of the public – without which a nuclear power program is not feasible.

  4. Engineer and technical training at GPUN's nuclear generating stations

    SciTech Connect

    Coe, R.P. )

    1993-01-01

    GPU Nuclear (GPUN) owns and operates the Oyster Creek and Three Mile Island (TMI) unit I nuclear generating stations. They also continue the recovery efforts of the damaged reactor at TMI-2. Technical training for engineers and support staff is managed by the GPUN Corporate Training Department. The group also manages the Institute of Nuclear Power Operations (INPO)-accredited Engineering Support Personnel (ESP) Training Program and the GPUN New Engineer Training Program. The New Engineer Training Program has been in existence since 1982 and has trained and oriented [approximately]100 new college graduates to the nuclear industry.

  5. World nuclear capacity and fuel cycle requirements, November 1993

    SciTech Connect

    Not Available

    1993-11-30

    This analysis report presents the current status and projections of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. Long-term projections of US nuclear capacity, generation, fuel cycle requirements, and spent fuel discharges for three different scenarios through 2030 are provided in support of the Department of Energy`s activities pertaining to the Nuclear Waste Policy Act of 1982 (as amended in 1987). The projections of uranium requirements also support the Energy Information Administration`s annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment.

  6. Mitochondrial and nuclear DNA sequences support a Cretaceous origin of Columbiformes and a dispersal-driven radiation in the Paleocene .

    PubMed

    Pereira, Sergio L; Johnson, Kevin P; Clayton, Dale H; Baker, Allan J

    2007-08-01

    Phylogenetic relationships among genera of pigeons and doves (Aves, Columbiformes) have not been fully resolved because of limited sampling of taxa and characters in previous studies. We therefore sequenced multiple nuclear and mitochondrial DNA genes totaling over 9000 bp from 33 of 41 genera plus 8 outgroup taxa, and, together with sequences from 5 other pigeon genera retrieved from GenBank, recovered a strong phylogenetic hypothesis for the Columbiformes. Three major clades were recovered with the combined data set, comprising the basally branching New World pigeons and allies (clade A) that are sister to Neotropical ground doves (clade B), and the Afro-Eurasian and Australasian taxa (clade C). None of these clades supports the monophyly of current families and subfamilies. The extinct, flightless dodo and solitaires (Raphidae) were embedded within pigeons and doves (Columbidae) in clade C, and monophyly of the subfamily Columbinae was refuted because the remaining subfamilies were nested within it. Divergence times estimated using a Bayesian framework suggest that Columbiformes diverged from outgroups such as Apodiformes and Caprimulgiformes in the Cretaceous before the mass extinction that marks the end of this period. Bayesian and maximum likelihood inferences of ancestral areas, accounting for phylogenetic uncertainty and divergence times, respectively, favor an ancient origin of Columbiformes in the Neotropical portion of what was then Gondwana. The radiation of modern genera of Columbiformes started in the Early Eocene to the Middle Miocene, as previously estimated for other avian groups such as ratites, tinamous, galliform birds, penguins, shorebirds, parrots, passerine birds, and toucans. Multiple dispersals of more derived Columbiformes between Australasian and Afro-Eurasian regions are required to explain current distributions.

  7. Sorption (Kd) measurements on cinder block and grout in support of dose assessments for Zion Nuclear Station decommissioning

    SciTech Connect

    Milian L.; Sullivan T.

    2014-06-24

    The Zion Nuclear Power Station is being decommissioned. ZionSolutions proposes to leave much of the below grade structures in place and to fill them with a backfill to provide structural support. Backfills under consideration include “clean” concrete demolition debris from the above grade parts of the facility, a flowable grout, cinder block construction debris and sand. A previous study (Yim, 2012) examined the sorption behavior of five nuclides (Fe-55, Co-60, Ni-63, Sr-85, and Cs-137) on concrete and local soils. This study, commissioned by ZionSolutions and conducted by the Brookhaven National Laboratory (BNL) examines the sorption behavior on cinder block and grout materials. Specifically, this study measured the distribution coefficient for four radionuclides of concern using site-groundwater and cinder block from the Zion site and a flowable grout. The distributions coefficient is a measure of the amount of the radionuclide that will remain sorbed to the solid material that is present relative to the amount that will remain in solution. A high distribution coefficient indicates most of the radionuclide will remain on the solid material and will not be available for transport by the groundwater. The radionuclides examined in this set of tests were Co-60, Ni-63, Sr-85, and Cs-137. Tests were performed following ASTM C1733-10, Standard Test Methods for Distribution Coefficients of Inorganic Species by the Batch Method. Sr-85 was used in the testing as an analogue for Sr-90 because it behaves similarly with respect to sorption and has a gamma emission that is easier to detect than the beta emission from Sr-90.

  8. Bonneville Power Administration and the Industrial Technologies Program Leverage Support to Overcome Energy Efficiency Barriers in the Northwest

    SciTech Connect

    2010-06-18

    Through its Energy Smart Industrial program, BPA is informing and assisting utilities and industries to have a better understanding of the benefits that come from participating in energy-savings programs. Read about how BPA is encouraging energy efficiency projects through its utilities.

  9. Radiation risks in lung cancer screening programs: a comparison with nuclear industry workers and atomic bomb survivors.

    PubMed

    McCunney, Robert J; Li, Jessica

    2014-03-01

    The National Lung Cancer Screening Trial (NLST) demonstrated that screening with low-dose CT (LDCT) scan reduced lung cancer and overall mortality by 20% and 7%, respectively. The LDCT scanning involves an approximate 2-mSv dose, whereas full-chest CT scanning, the major diagnostic study used to follow up nodules, may involve a dose of 8 mSv. Radiation associated with CT scanning and other diagnostic studies to follow up nodules may present an independent risk of lung cancer. On the basis of the NLST, we estimated the incidence and prevalence of nodules detected in screening programs. We followed the Fleischner guidelines for follow-up of nodules to assess cumulative radiation exposure over 20- and 30-year periods. We then evaluated nuclear worker cohort studies and atomic bomb survivor studies to assess the risk of lung cancer from radiation associated with long-term lung cancer screening programs. The findings indicate that a 55-year-old lung screening participant may experience a cumulative radiation exposure of up to 280 mSv over a 20-year period and 420 mSv over 30 years. These exposures exceed those of nuclear workers and atomic bomb survivors. This assessment suggests that long-term (20-30 years) LDCT screening programs are associated with nontrivial cumulative radiation doses. Current lung cancer screening protocols, if conducted over 20- to 30-year periods, can independently increase the risk of lung cancer beyond cigarette smoking as a result of cumulative radiation exposure. Radiation exposures from LDCT screening and follow-up diagnostic procedures exceed lifetime radiation exposures among nuclear power workers and atomic bomb survivors.

  10. Ionizing Radiation and Risk of Chronic Lymphocytic Leukemia in the 15-Country Study of Nuclear Industry Workers

    PubMed Central

    Vrijheid, Martine; Cardis, Elisabeth; Ashmore, Patrick; Auvinen, Anssi; Gilbert, Ethel; Habib, Rima R.; Malker, Hans; Muirhead, Colin R.; Richardson, David B.; Rogel, Agnes; Schubauer-Berigan, Mary; Tardy, Hélène; Telle-Lamberton, Maylis

    2014-01-01

    In contrast to other types of leukemia, chronic lymphocytic leukemia (CLL) has long been regarded as non-radiogenic, i.e. not caused by ionizing radiation. However, the justification for this view has been challenged. We therefore report on the relationship between CLL mortality and external ionizing radiation dose within the 15-country nuclear workers cohort study. The analyses included, in seven countries with CLL deaths, a total of 295,963 workers with more than 4.5 million person-years of follow-up and an average cumulative bone marrow dose of 15 mSv; there were 65 CLL deaths in this cohort. The relative risk (RR) at an occupational dose of 100 mSv compared to 0 mSv was 0.84 (95% CI 0.39, 1.48) under the assumption of a 10-year exposure lag. Analyses of longer lag periods showed little variation in the RR, but they included very small numbers of cases with relatively high doses. In conclusion, the largest nuclear workers cohort study to date finds little evidence for an association between low doses of external ionizing radiation and CLL mortality. This study had little power due to low doses, short follow-up periods, and uncertainties in CLL ascertainment from death certificates; an extended follow-up of the cohorts is merited and would ideally include incident cancer cases. PMID:18959468

  11. Nuclear Power in China

    NASA Astrophysics Data System (ADS)

    Zhou, Yun

    2012-02-01

    In response to the Fukushima accident, China is strengthening its nuclear safety at reactors in operation, under construction and in preparation, including efforts to improve nuclear safety regulations and guidelines based on lessons learned from the accident. Although China is one of the major contributors in the global nuclear expansion, China's nuclear power industry is relatively young. Its nuclear safety regulators are less experienced compared to those in other major nuclear power countries. To realize China's resolute commitment to rapid growth of safe nuclear energy, detailed analyses of its nuclear safety regulatory system are required. This talk explains China's nuclear energy program and policy at first. It also explores China's governmental activities and future nuclear development after Fukushima accidents. At last, an overview of China's nuclear safety regulations and practices are provided. Issues and challenges are also identified for police makers, regulators, and industry professionals.

  12. Report to DOE and Exelon Corporation: Matching Grant Program for the Nuclear Engineering Program at University of Wisconsin, Madison

    SciTech Connect

    Corradini, Michael L.

    2002-02-18

    The DOE Industry Matching Grant Program, which began in 1992, is designed to encourage collaborative support for nuclear engineering education as well as research between the nation's nuclear industry and the U.S. Department of Energy (DOE). Over the past two decades nuclear engineering programs in the United States have witnessed a serious decline in student enrollments, number of faculty members and support from their host universities. Despite this decline, the discipline of nuclear engineering remains important to the advancement of the mission goals of the U.S. Department of Energy. These academic programs are also critically important in maintaining a viable workforce for the nation's nuclear industry. As conceived by Commonwealth Edison, this program has focused on creating a partnership between DOE and private sector businesses, which employ nuclear engineers. The program is designed to ensure that academic programs in nuclear engineering are maintained and enhanced in universities throughout the United States.

  13. Accurate determination of ⁴¹Ca concentrations in spent resins from the nuclear industry by accelerator mass spectrometry.

    PubMed

    Nottoli, Emmanuelle; Bourlès, Didier; Bienvenu, Philippe; Labet, Alexandre; Arnold, Maurice; Bertaux, Maité

    2013-12-01

    The radiological characterisation of nuclear waste is essential for managing storage sites. Determining the concentration of Long-Lived RadioNuclides (LLRN) is fundamental for their long-term management. This paper focuses on the measurement of low (41)Ca concentrations in ions exchange resins used for primary fluid purification in Pressurised Water Reactors (PWR). (41)Ca concentrations were successfully measured by Accelerator Mass Spectrometry (AMS) after the acid digestion of resin samples, followed by radioactive decontamination and isobaric suppression through successive hydroxide, carbonate, nitrate and final CaF2 precipitations. Measured (41)Ca concentrations ranged from 0.02 to 0.03 ng/g, i.e. from 0.06 to 0.09 Bq/g. The (41)Ca/(60)Co activity ratios obtained were remarkably reproducible and in good agreement with the current ratio used for resins management.

  14. Britain`s nuclear quandary

    SciTech Connect

    1994-07-01

    This article is review of energy policy in the United Kingdom, in particular, the British government`s review of the nuclear industry. Major topics of this review include: (1) The economic viability of new nuclear stations, (2) The privitization of the nuclear industry, (3) Nuclear waste disposal, and (4) Liabilities associated with decommissioning.

  15. Combination of physico-chemical analysis, Allium cepa test system and Oreochromis niloticus erythrocyte based comet assay/nuclear abnormalities tests for cyto-genotoxicity assessments of treated effluents discharged from textile industries.

    PubMed

    Hemachandra, Chamini K; Pathiratne, Asoka

    2016-09-01

    Bioassays for cyto-genotoxicity assessments are generally not required in current textile industry effluent discharge management regulations. The present study applied in vivo plant and fish based toxicity tests viz. Allium cepa test system and Oreochromis niloticus erythrocyte based comet assay and nuclear abnormalities tests in combination with physico-chemical analysis for assessing potential cytotoxic/genotoxic impacts of treated textile industry effluents reaching a major river (Kelani River) in Sri Lanka. Of the treated effluents tested from two textile industries, color in the Textile industry 1 effluents occasionally and color, biochemical oxygen demand and chemical oxygen demand in the Textile industry 2 effluents frequently exceeded the specified Sri Lankan tolerance limits for discharge of industrial effluents into inland surface waters. Exposure of A. cepa bulbs to 100% and 12.5% treated effluents from both industries resulted in statistically significant root growth retardation, mito-depression, and induction of chromosomal abnormalities in root meristematic cells in comparison to the dilution water in all cases demonstrating cyto-genotoxicity associated with the treated effluents. Exposure of O. niloticus to the 100% and 12.5% effluents, resulted in erythrocytic genetic damage as shown by elevated total comet scores and induction of nuclear abnormalities confirming the genotoxicity of the treated effluents even with 1:8 dilution. The results provide strong scientific evidence for the crucial necessity of incorporating cyto-genotoxicity impact assessment tools in textile industry effluent management regulations considering human health and ecological health of the receiving water course under chronic exposure.

  16. Applications of nuclear physics.

    PubMed

    Hayes, A C

    2017-02-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applications of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.

  17. Applications of nuclear physics

    DOE PAGES

    Hayes-Sterbenz, Anna Catherine

    2017-01-10

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applicationsmore » of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Lastly, each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.« less

  18. Applications of nuclear physics

    NASA Astrophysics Data System (ADS)

    Hayes, A. C.

    2017-02-01

    Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applications of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.

  19. Nuclear Waste Disposal

    SciTech Connect

    Gee, Glendon W.; Meyer, Philip D.; Ward, Andy L.

    2005-01-12

    Nuclear wastes are by-products of nuclear weapons production and nuclear power generation, plus residuals of radioactive materials used by industry, medicine, agriculture, and academia. Their distinctive nature and potential hazard make nuclear wastes not only the most dangerous waste ever created by mankind, but also one of the most controversial and regulated with respect to disposal. Nuclear waste issues, related to uncertainties in geologic disposal and long-term protection, combined with potential misuse by terrorist groups, have created uneasiness and fear in the general public and remain stumbling blocks for further development of a nuclear industry in a world that may soon be facing a global energy crisis.

  20. The Lhc Cryomagnet Supports in Glass-Fiber Reinforced Epoxy: a Large Scale Industrial Production with High Reproducibility in Performance

    NASA Astrophysics Data System (ADS)

    Poncet, A.; Struik, M.; Trigo, J.; Parma, V.

    2008-03-01

    The about 1700 LHC main ring super-conducting magnets are supported within their cryostats on 4700 low heat in leak column-type supports. The supports were designed to ensure a precise and stable positioning of the heavy dipole and quadrupole magnets while keeping thermal conduction heat loads within budget. A trade-off between mechanical and thermal properties, as well as cost considerations, led to the choice of glass fibre reinforced epoxy (GFRE). Resin Transfer Moulding (RTM), featuring a high level of automation and control, was the manufacturing process retained to ensure the reproducibility of the performance of the supports throughout the large production. The Spanish aerospace company EADS-CASA Espacio developed the specific RTM process, and produced the total quantity of supports between 2001 and 2004. This paper describes the development and the production of the supports, and presents the production experience and the achieved performance.

  1. Midwest Nuclear Science and Engineering Consortium

    SciTech Connect

    Dr. Wynn Volkert; Dr. Arvind Kumar; Dr. Bryan Becker; Dr. Victor Schwinke; Dr. Angel Gonzalez; Dr. DOuglas McGregor

    2010-12-08

    The objective of the Midwest Nuclear Science and Engineering Consortium (MNSEC) is to enhance the scope, quality and integration of educational and research capabilities of nuclear sciences and engineering (NS/E) programs at partner schools in support of the U.S. nuclear industry (including DOE laboratories). With INIE support, MNSEC had a productive seven years and made impressive progress in achieving these goals. Since the past three years have been no-cost-extension periods, limited -- but notable -- progress has been made in FY10. Existing programs continue to be strengthened and broadened at Consortium partner institutions. The enthusiasm generated by the academic, state, federal, and industrial communities for the MNSEC activities is reflected in the significant leveraging that has occurred for our programs.

  2. A Study of Community Leaders in a Nuclear Host Community: Local Issues, Expectations and Support and Opposition.

    ERIC Educational Resources Information Center

    Bronfman, B. H.

    As part of a continuing effort to assess the social impacts on communities of energy facility planning, construction, operation, and decommissioning, a May 1977 survey of 37 community leaders in Hartsville, Tennessee (site of a nuclear power plant) establishes major local issues (past, present, and future) which leaders feel are important to…

  3. Overview of U.S. nuclear launch safety approval process, supporting launch vehicle databook and probabilistic risk assessment methods

    NASA Technical Reports Server (NTRS)

    Reinhart, L. E.

    2001-01-01

    This paper provides an overview of the U.S. space nuclear power system launch approval process as defined by the two separate requirements of the National Environmental Policy Act (NEPA) and Presidential Directive/National Security Council Memorandum No. 25 (PD/NSC-25).

  4. Development of the System of Investment Support of Projects in the Industrial-Innovative Development of Kazakhstan

    ERIC Educational Resources Information Center

    Doskaliyeva, Bayan B.; Orynbassarova, Yerkenazym D.; Omarkhanov?, Zhibek M.; Karibaev, Yerkebulan S.; Baimukhametova, Ayagul S.

    2016-01-01

    The purpose of this study is to determine specific features of investment regulation mechanism aimed at providing effective implementation of projects in the context of industrial-innovative development of Kazakhstan. There the used the system of general scientific and special research methods providing the possibility to disclose processes and…

  5. Empirical Study of the Role of Government Support and Success Factors in Industry-University-Institute Cooperation

    ERIC Educational Resources Information Center

    Zhimin, Guan; Zhongpeng, Cao; Jin, Tao

    2016-01-01

    Empirical research methods were used to study the state of industry-university-institute collaboration in China and the factors influencing the results of cooperation between members of technological innovation alliances, from the dual perspectives of enterprises and universities/research institutes On the basis of questionnaire surveys of 100…

  6. Radioisotope Power System Delivery, Ground Support and Nuclear Safety Implementation: Use of the Multi-Mission Radioisotope Thermoelectric Generator for the NASA's Mars Science Laboratory

    SciTech Connect

    S.G. Johnson; K.L. Lively; C.C. Dwight

    2014-07-01

    Radioisotope power systems have been used for over 50 years to enable missions in remote or hostile environments. They are a convenient means of supplying a few milliwatts up to a few hundred watts of useable, long-term electrical power. With regard to use of a radioisotope power system, the transportation, ground support and implementation of nuclear safety protocols in the field is a complex process that requires clear identification of needed technical and regulatory requirements. The appropriate care must be taken to provide high quality treatment of the item to be moved so it arrives in a condition to fulfill its missions in space. Similarly it must be transported and managed in a manner compliant with requirements for shipment and handling of special nuclear material. This presentation describes transportation, ground support operations and implementation of nuclear safety and security protocols for a radioisotope power system using recent experience involving the Multi-Mission Radioisotope Thermoelectric Generator for National Aeronautics and Space Administration’s Mars Science Laboratory, which launched in November of 2011.

  7. Collapse of an industry

    SciTech Connect

    Campbell, J.L.

    1988-01-01

    The author details the politics of nuclear energy in the U.S. and points out the advantages and disadvantages of various forms of industrial planning for this sector. He uses the nuclear industry as an example of how capitalism and democracy can be incompatible in some situations.

  8. Nuclear analytical chemistry

    SciTech Connect

    Brune, D.; Forkman, B.; Persson, B.

    1984-01-01

    This book covers the general theories and techniques of nuclear chemical analysis, directed at applications in analytical chemistry, nuclear medicine, radiophysics, agriculture, environmental sciences, geological exploration, industrial process control, etc. The main principles of nuclear physics and nuclear detection on which the analysis is based are briefly outlined. An attempt is made to emphasise the fundamentals of activation analysis, detection and activation methods, as well as their applications. The book provides guidance in analytical chemistry, agriculture, environmental and biomedical sciences, etc. The contents include: the nuclear periodic system; nuclear decay; nuclear reactions; nuclear radiation sources; interaction of radiation with matter; principles of radiation detectors; nuclear electronics; statistical methods and spectral analysis; methods of radiation detection; neutron activation analysis; charged particle activation analysis; photon activation analysis; sample preparation and chemical separation; nuclear chemical analysis in biological and medical research; the use of nuclear chemical analysis in the field of criminology; nuclear chemical analysis in environmental sciences, geology and mineral exploration; and radiation protection.

  9. Nuclear fuel cycle information workshop

    SciTech Connect

    Not Available

    1983-01-01

    This overview of the nuclear fuel cycle is divided into three parts. First, is a brief discussion of the basic principles of how nuclear reactors work; second, is a look at the major types of nuclear reactors being used and world-wide nuclear capacity; and third, is an overview of the nuclear fuel cycle and the present industrial capability in the US.

  10. Nuclear energy.

    PubMed

    Wilson, Peter D

    2010-01-01

    The technical principles and practices of the civil nuclear industry are described with particular reference to fission and its products, natural and artificial radioactivity elements principally concerned and their relationships, main types of reactor, safety issues, the fuel cycle, waste management, issues related to weapon proliferation, environmental considerations and possible future developments.

  11. Measurement of 37Ar to support technology for On-Site Inspection under the Comprehensive Nuclear-Test-BanTreaty

    NASA Astrophysics Data System (ADS)

    Aalseth, C. E.; Day, A. R.; Haas, D. A.; Hoppe, E. W.; Hyronimus, B. J.; Keillor, M. E.; Mace, E. K.; Orrell, J. L.; Seifert, A.; Woods, V. T.

    2011-10-01

    On-Site Inspection (OSI) is a key component of the verification regime for the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Measurements of radionuclide isotopes created by an underground nuclear explosion are a valuable signature of a Treaty violation. Argon-37 is produced by neutron interaction with calcium in soil, 40Ca( n, α) 37Ar. For OSI, the 35-day half-life of 37Ar provides both high specific activity and sufficient time for completion of an inspection before decay limits sensitivity. This paper presents a low-background internal-source gas proportional counter with an 37Ar measurement sensitivity level equivalent to 45 mBq/SCM in wholeair.

  12. Measurement of 37Ar to support technology for On-site Inspection under the Comprehensive Nuclear-Test-Ban Treaty

    SciTech Connect

    Aalseth, Craig E.; Day, Anthony R.; Haas, Derek A.; Hoppe, Eric W.; Hyronimus, Brian J.; Keillor, Martin E.; Mace, Emily K.; Orrell, John L.; Seifert, Allen; Woods, Vincent T.

    2011-10-01

    On-Site Inspection (OSI) is a key component of the verification regime for the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Measurements of radionuclide isotopes created by an underground nuclear explosion are a valuable signature of a Treaty violation. Argon-37 is produced from neutron interaction with calcium in soil, 40Ca(n,α)37Ar. For OSI, the 35-day half-life of 37Ar provides both high specific activity and sufficient time for completion of an inspection before decay limits sensitivity. This paper presents a low-background internal-source gas proportional counter with an 37Ar measurement sensitivity level equivalent to 45.1 mBq/SCM in whole air.

  13. Study of the Capability of the United States Textile and Apparel Industries to Support National Defense. Volume 1

    DTIC Science & Technology

    1983-06-01

    which was geophysically and interna- tionally limited, and yet today might yield greater risk for global confrontation and full mobilization. E. Full...converting other producers in an emergency situation. In addition, this approach toward industry involvement would increase the exposure which both NLABS and...developed responses to handle the potential risk of loss of supply. These responses range from backward integration by du Pont into controlling a

  14. Development of Cesium and Strontium Separation and Immobilization Technologies in Support of an Advanced Nuclear Fuel Cycle

    SciTech Connect

    Jack D. Law; Troy G. Garn; R. Scott Herbst; David H. Meikrantz; Dean R. Peterman; Catherine L. Riddle; Terry A. Todd; Julie L. Tripp

    2006-02-01

    As part of the Advanced Fuel Cycle Initiative, two solvent extraction technologies are being developed at the Idaho National Laboratory to simultaneously separate cesium and strontium from dissolved spent nuclear fuel. The chlorinated cobalt dicarbollide/polyethylene glycol (CCD/PEG) process utilizes a solvent consisting of chlorinated cobalt dicarbollide for the extraction of Cs and polyethylene glycol for the synergistic extraction of Sr in a phenyltrifluoromethyl sulfone diluent. Countercurrent flowsheets have been designed and tested on simulated and actual spent nuclear fuel feed streams with both cesium and strontium removal efficiencies of greater than 99%. The Fission Product Extraction (FPEX) process is based on two highly-specific extractants: 4,4',(5')-Di-(t-butyldicyclo-hexano)-18-crown-6 (DtBuCH18C6) for the extraction of Sr and Calix[4]arene-bis-(tert-octylbenzo-crown-6) (BOBCalixC6) for the extraction of Cs. Laboratory test results of the FPEX process, using simulated feed solution spiked with radiotracers, indicate good Cs and Sr extraction and stripping performance. A preliminary solvent extraction flowsheet for the treatment of spent nuclear fuel with the FPEX process has been developed, and testing of the flowsheet with simulated spent nuclear fuel solutions is planned in the near future. Steam reforming is currently being developed for stabilization of the Cs/Sr product stream because it can produce a solid waste form while retaining the Cs and Sr in the solid, destroy the nitrates and organics present in these aqueous solutions, and convert the Cs and Sr into leach resistant aluminosilicate minerals. A bench-scale steam reforming pilot plant has been operated with several potential feed compositions and steam reformed product has been generated and analyzed.

  15. Coordinating Space Nuclear Research Advancement and Education

    SciTech Connect

    John D. Bess; Jonathon A. Webb; Brian J. Gross; Aaron E. Craft

    2009-11-01

    The advancement of space exploration using nuclear science and technology has been a goal sought by many individuals over the years. The quest to enable space nuclear applications has experienced many challenges such as funding restrictions; lack of political, corporate, or public support; and limitations in educational opportunities. The Center for Space Nuclear Research (CSNR) was established at the Idaho National Laboratory (INL) with the mission to address the numerous challenges and opportunities relevant to the promotion of space nuclear research and education.1 The CSNR is operated by the Universities Space Research Association and its activities are overseen by a Science Council comprised of various representatives from academic and professional entities with space nuclear experience. Program participants in the CSNR include academic researchers and students, government representatives, and representatives from industrial and corporate entities. Space nuclear educational opportunities have traditionally been limited to various sponsored research projects through government agencies or industrial partners, and dedicated research centers. Centralized research opportunities are vital to the growth and development of space nuclear advancement. Coordinated and focused research plays a key role in developing the future leaders in the space nuclear field. The CSNR strives to synchronize research efforts and provide means to train and educate students with skills to help them excel as leaders.

  16. Radiation exposure and cancer incidence in a cohort of nuclear power industry workers in the Republic of Korea, 1992-2005.

    PubMed

    Jeong, Meeseon; Jin, Young-Woo; Yang, Kwang Hee; Ahn, Yoon-Ok; Cha, Chang-Yong

    2010-03-01

    Sievert was estimated to be 1.69 (95% CI -2.07 to 8.21) for all cancers combined assuming a 10 years lag time. Consequently, a significant excess of cancer incidence among radiation workers in the nuclear power industry in Korea was not observed. Further follow-up and an expansion of the cohort are needed to overcome the lack of statistical power in the study.

  17. Wartime nuclear weapons research in Germany and Japan.

    PubMed

    Grunden, Walter E; Walker, Mark; Yamnazaki, Masakatsu

    2005-01-01

    This article compares military research projects during the Second World War to develop nuclear weapons in Germany and Japan, two countries who lost the war and failed to create nuclear weapons. The performance and motivations of the scientists, as well as the institutional support given the work, is examined, explaining why, in each case, the project went as far as it did-but no further. The story is carried over into the postwar period, when the two cultures and their scientists had to deal with the buildup of nuclear weapons during the cold war and the new nuclear power industry.

  18. 78 FR 7784 - Draft Guidance for Industry on Enrichment Strategies for Clinical Trials To Support Approval of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-02-04

    ... enrichment. The guidance also discusses general clinical trial design considerations, provides examples of potential clinical trial designs, and discusses regulatory considerations when using enrichment strategies... Clinical Trials To Support Approval of Human Drugs and Biological Products; Extension of Comment...

  19. Nuclear energy related research

    NASA Astrophysics Data System (ADS)

    Rintamaa, R.

    1992-05-01

    The annual Research Program Plan describes publicly funded nuclear energy related research to be carried out mainly at the Technical Research Center of Finland (VTT) in 1992. The research is financed primarily by the Ministry of Trade and Industry (KTM), the Finnish Center for Radiation and Nuclear Safety (STUK), and VTT itself. Other research institutes, utilities, and industry also contribute to many projects.

  20. Nuclear Space Power Systems Materials Requirements

    SciTech Connect

    Buckman, R.W. Jr.

    2004-02-04

    High specific energy is required for space nuclear power systems. This generally means high operating temperatures and the only alloy class of materials available for construction of such systems are the refractory metals niobium, tantalum, molybdenum and tungsten. The refractory metals in the past have been the construction materials selected for nuclear space power systems. The objective of this paper will be to review the past history and requirements for space nuclear power systems from the early 1960's through the SP-100 program. Also presented will be the past and present status of refractory metal alloy technology and what will be needed to support the next advanced nuclear space power system. The next generation of advanced nuclear space power systems can benefit from the review of this past experience. Because of a decline in the refractory metal industry in the United States, ready availability of specific refractory metal alloys is limited.

  1. The 15-Country Collaborative Study of Cancer Risk among Radiation Workers in the Nuclear Industry: estimates of radiation-related cancer risks.

    PubMed

    Cardis, E; Vrijheid, M; Blettner, M; Gilbert, E; Hakama, M; Hill, C; Howe, G; Kaldor, J; Muirhead, C R; Schubauer-Berigan, M; Yoshimura, T; Bermann, F; Cowper, G; Fix, J; Hacker, C; Heinmiller, B; Marshall, M; Thierry-Chef, I; Utterback, D; Ahn, Y-O; Amoros, E; Ashmore, P; Auvinen, A; Bae, J-M; Bernar, J; Biau, A; Combalot, E; Deboodt, P; Diez Sacristan, A; Eklöf, M; Engels, H; Engholm, G; Gulis, G; Habib, R R; Holan, K; Hyvonen, H; Kerekes, A; Kurtinaitis, J; Malker, H; Martuzzi, M; Mastauskas, A; Monnet, A; Moser, M; Pearce, M S; Richardson, D B; Rodriguez-Artalejo, F; Rogel, A; Tardy, H; Telle-Lamberton, M; Turai, I; Usel, M; Veress, K

    2007-04-01

    A 15-Country collaborative cohort study was conducted to provide direct estimates of cancer risk following protracted low doses of ionizing radiation. Analyses included 407,391 nuclear industry workers monitored individually for external radiation and 5.2 million person-years of follow-up. A significant association was seen between radiation dose and all-cause mortality [excess relative risk (ERR) 0.42 per Sv, 90% CI 0.07, 0.79; 18,993 deaths]. This was mainly attributable to a dose-related increase in all cancer mortality (ERR/Sv 0.97, 90% CI 0.28, 1.77; 5233 deaths). Among 31 specific types of malignancies studied, a significant association was found for lung cancer (ERR/Sv 1.86, 90% CI 0.49, 3.63; 1457 deaths) and a borderline significant (P = 0.06) association for multiple myeloma (ERR/Sv 6.15, 90% CI <0, 20.6; 83 deaths) and ill-defined and secondary cancers (ERR/Sv 1.96, 90% CI -0.26, 5.90; 328 deaths). Stratification on duration of employment had a large effect on the ERR/Sv, reflecting a strong healthy worker survivor effect in these cohorts. This is the largest analytical epidemiological study of the effects of low-dose protracted exposures to ionizing radiation to date. Further studies will be important to better assess the role of tobacco and other occupational exposures in our risk estimates.

  2. Cooperation between scientists, NGOs and industry in support of sustainable fisheries: the South African hake Merluccius spp. trawl fishery experience.

    PubMed

    Field, J G; Attwood, C G; Jarre, A; Sink, K; Atkinson, L J; Petersen, S

    2013-10-01

    This paper examines the increasingly close interaction between natural and social scientists, non-governmental organizations (NGO) and industry, in pursuit of responsible ecosystem-based management of fisheries. South Africa has committed to implementing an ecosystem approach to fisheries management. Management advice stems from multi-stakeholder representation on government-led scientific and management working groups. In the hake Merluccius capensis and Merluccius paradoxus fishery, the primary management measure is an annual total allowable catch (TAC), the level of which is calculated using a management procedure (MP) that is revised approximately every 4 years. Revision of the MP is a consultative process involving most stakeholders, and is based on simulation modelling of projected probable scenarios of resource and fishery dynamics under various management options. NGOs, such as the Worldwide Fund for Nature in South Africa (WWF-SA), have played an important role in influencing consumers, the fishing industry and government to develop responsible fishing practices that minimize damage to marine ecosystems. Cooperation between industry, government and scientists has helped to improve sustainability and facilitated the meeting of market-based incentives for more responsible fisheries. Research includes ecosystem modelling, spatial analysis and ecosystem risk assessment with increasing research focus on social and economic aspects of the fishery. A four-year cooperative experiment to quantify the effect of trawling on benthic community structure is being planned. The food requirements of top predators still need to be included in the TAC-setting formulae and more social and economic research is needed. This paper also demonstrates how NGO initiatives such as Marine Stewardship Council certification and the Southern African Sustainable Seafood Initiative, a traffic light system of classifying seafood for consumers, have contributed to responsible fishing

  3. Supporting Pacific Island Countries to Strengthen Their Resistance to Tobacco Industry Interference in Tobacco Control: A Case Study of Papua New Guinea and Solomon Islands

    PubMed Central

    McCool, Judith; McKenzie, Jeanie; Lyman, Annabel; Allen, Matthew

    2013-01-01

    Tobacco use is the biggest single preventable cause of non-communicable diseases (NCDs) in the Western Pacific region. Currently, 14 Pacific Island countries have ratified the WHO Framework Convention on Tobacco Control (FCTC) and, in having done so, are committed to implementing tobacco control measures aligned with the FCTC. Progressing strong and effective tobacco control legislation is essential to achieving long term gains in public health in small island countries. However, survey evidence suggests that pervasive tobacco industry interference serves to undermine tobacco control and public policy in several Pacific countries. An initiative was developed to provide dedicated, in-country technical support for developing legislation and policy to support implementation of Article 5.3 of the FCTC in the Solomon Islands and Papua New Guinea. This paper examines the factors that have assisted the two Pacific countries to make progress in implementing Article 5.3 and what this might mean for supporting progress in other Pacific settings. A document analysis was undertaken to identify the process and outcome of the intervention. Two significant outputs from the project including having identified and documented specific examples of TII and the development of draft legislation for Article 5.3 and other key resources for public servants both within and outside the health sector. Key determinants of progress included a motivated and engaged Ministry of Health, active civil society group or champion and access to media to prepare tobacco industry related material to stimulate public and policy sector debate. PMID:23924884

  4. Final Report: Technical Support for Innovative Energy Systems the U.S. Chemical Industry -- Innovative Energy Systems Pilot Project - Chemicals Project Integrator

    SciTech Connect

    John Cuttica - Principal Investigator; Dr Steffen Mueller - Lead Engineer

    2008-10-30

    The University of Illinois at Chicago Energy Resources Center (UIC/ERC) was originally selected to carry out the role of project integrator for a planned solicitation calling for proposals for innovative concepts for energy efficient systems in the chemical industry. The selection was made as a result of a DOE Announcement of Funding Opportunity issued by the DOE Golden Field Office. The U.S. DOE, due to funding constraints, decided to change the role of project integrator into one of technical support to DOE and the Vision 2020 Steering Committee in carrying out the oversight and management of the projects selected from the planned innovative concepts solicitation. This project, initiated in April, 2005, was established to provide that technical support to the U.S. DOE Innovative Energy Systems Pilot Project for the US Chemical Industry. In the late summer of 2006, and as a continuation of the baseline technology analysis conducted by UIC/ERC under this project, DOE requested that UIC/ERC assist in the development of “technology briefs” in support of the DOE Save Energy Now program. The 100 technology briefs developed under this contract were utilized by the Energy Experts as part of their Energy Saving Assessments (ESA).

  5. Constellation nuclear instrument analysis required in support of the Extended Power Up-rate for Ginna Station

    SciTech Connect

    Guider, J.; Quinn, E. L.

    2006-07-01

    The purpose of this paper is to provide an overview of the Instrumentation and Control design changes required for the Extended Power Up-rate (EPU) at the R.E. Ginna Nuclear Station in Ontario, N.Y. Ginna is a pressurized-water reactor (PWR) plant of the Westinghouse 2-loop design. The request for the EPU was filed on July 7, 2005 and approved by NRC on July 11, 2006 and included an increase in the maximum steady-state reactor core power level from 1520 megawatts thermal to 1775 MWt, which is an increase of approximately 17%. (authors)

  6. Alternative Approach to Nuclear Data Representation: Building the infrastructure to support QMU and next-generation simulations

    SciTech Connect

    Pruet, J; Brown, D A; Beck, B; McNabb, D P

    2006-01-17

    The nuclear data infrastructure currently relies on punch-card era formats designed some five decades ago. Though this system has worked well, recent interest in non-traditional and complicated physics processes has demanded a change. Here we present an alternative approach under development at LLNL. In this approach data is described through collections of distinct and self-contained simple data structures. This structure-based format is compared with traditional ENDF and ENDL, which can roughly be characterized as dictionary-based representations.

  7. Artificial intelligence and nuclear power. Report by the Technology Transfer Artificial Intelligence Task Team

    SciTech Connect

    Not Available

    1985-06-01

    The Artificial Intelligence Task Team was organized to review the status of Artificial Intelligence (AI) technology, identify guidelines for AI work, and to identify work required to allow the nuclear industry to realize maximum benefit from this technology. The state of the nuclear industry was analyzed to determine where the application of AI technology could be of greatest benefit. Guidelines and criteria were established to focus on those particular problem areas where AI could provide the highest possible payoff to the industry. Information was collected from government, academic, and private organizations. Very little AI work is now being done to specifically support the nuclear industry. The AI Task Team determined that the establishment of a Strategic Automation Initiative (SAI) and the expansion of the DOE Technology Transfer program would ensure that AI technology could be used to develop software for the nuclear industry that would have substantial financial payoff to the industry. The SAI includes both long and short term phases. The short-term phase includes projects which would demonstrate that AI can be applied to the nuclear industry safely, and with substantial financial benefit. The long term phase includes projects which would develop AI technologies with specific applicability to the nuclear industry that would not be developed by people working in any other industry.

  8. Second Nuclear Era

    SciTech Connect

    Weinberg, A.M.; Spiewak, I.; Barkenbus, J.N.; Livingston, R.S.; Phung, D.L.

    1984-03-01

    The Institute for Energy Analysis with support from The Andrew W. Mellon Foundation has studied the decline of the present nuclear era in the United States and the characteristics of a Second Nuclear Era which might be instrumental in restoring nuclear power to an appropriate place in the energy options of our country. The study has determined that reactors operating today are much safer than they were at the time of the TMI accident. A number of concepts for a supersafe reactor were reviewed and at least two were found that show considerable promise, the PIUS, a Swedish pressurized water design, and a gas-cooled modular design of German and US origin. Although new, safer, incrementally improved, conventional reactors are under study by the nuclear industry, the complete lack of new orders in the United States will slow their introduction and they are likely to be more expensive than present designs. The study recommends that supersafe reactors be taken seriously and that federal and private funds both be used to design and, if feasible, to build a prototype reactor of substantial size. 146 references, 8 figures, 2 tables.

  9. Older Workers' Perspectives on Training and Retention of Older Workers: South Australian Construction Industry Study. Support Document

    ERIC Educational Resources Information Center

    Lundberg, David; Marshallsay, Zariah

    2007-01-01

    Older workers' perspectives are examined in a national survey of the finance sector and case studies of aged care and construction workers. The majority of older workers intend to work beyond retirement age, to achieve a better lifestyle. With training, older workers could mentor younger workers. This support document includes a national survey of…

  10. Data trimming, nuclear emissions, and climate change.

    PubMed

    Shrader-Frechette, Kristin Sharon

    2009-03-01

    Ethics requires good science. Many scientists, government leaders, and industry representatives support tripling of global-nuclear-energy capacity on the grounds that nuclear fission is "carbon free" and "releases no greenhouse gases." However, such claims are scientifically questionable (and thus likely to lead to ethically questionable energy choices) for at least 3 reasons. (i) They rely on trimming the data on nuclear greenhouse-gas emissions (GHGE), perhaps in part because flawed Kyoto Protocol conventions require no full nuclear-fuel-cycle assessment of carbon content. (ii) They underestimate nuclear-fuel-cycle releases by erroneously assuming that mostly high-grade uranium ore, with much lower emissions, is used. (iii) They inconsistently compare nuclear-related GHGE only to those from fossil fuels, rather than to those from the best GHG-avoiding energy technologies. Once scientists take account of (i)-(iii), it is possible to show that although the nuclear fuel cycle releases (per kWh) much fewer GHG than coal and oil, nevertheless it releases far more GHG than wind and solar-photovoltaic. Although there may be other, ethical, reasons to support nuclear tripling, reducing or avoiding GHG does not appear to be one of them.

  11. Institute of Nuclear Power Operations 1994 annual report

    SciTech Connect

    1994-12-31

    This annual report highlights the activities of the Institute of Nuclear Power Operations. The topics of the report include the president and chairmen`s joint message, overview of programs serving as the foundation for most of its activities, performance indicators for the US nuclear utility industry, and INPO`s 1994 financial reports and rosters. INPO has four technical cornerstone programs that serve as the foundation for most of its activities. (1) Evaluations of nuclear power plants operated by member utilities are conducted on a regularly scheduled basis. (2) INPO supports its member utilities in their work to achieve and maintain accreditation of training programs. (3) Events analysis programs identify and communicate lessons learned from plant events so utilities can take action to prevent similar events at their plants. (4) INPO helps members improve in nuclear operations areas through assistance programs and other activities that continually evolve to meet the changing needs of the nuclear industry

  12. Institute of Nuclear Power Operations annual report, 1993

    SciTech Connect

    1993-12-31

    This annual report highlights the activities of the Institute of Nuclear Power Operations. The topics of the report include the president and chairmen`s joint message, overview of programs serving as the foundation for most of its activities, performance indicators for the US nuclear utility industry, and INPO`s 1993 financial reports and rosters. INPO has four technical cornerstone programs that serve as the foundation for most of its activities. (1) Evaluations of nuclear power plants operated by member utilities are conducted on a regularly scheduled basis. (2) INPO supports its member utilities in their work to achieve and maintain accreditation of training programs. (3) Events analysis programs identify and communicate lessons learned from plant events so utilities can take action to prevent similar events at their plants. (4) INPO helps members improve in nuclear operations areas through assistance programs and other activities that continually evolve to meet the changing needs of the nuclear industry.

  13. Swedish nuclear waste efforts

    SciTech Connect

    Rydberg, J.

    1981-09-01

    After the introduction of a law prohibiting the start-up of any new nuclear power plant until the utility had shown that the waste produced by the plant could be taken care of in an absolutely safe way, the Swedish nuclear utilities in December 1976 embarked on the Nuclear Fuel Safety Project, which in November 1977 presented a first report, Handling of Spent Nuclear Fuel and Final Storage of Vitrified Waste (KBS-I), and in November 1978 a second report, Handling and Final Storage of Unreprocessed Spent Nuclear Fuel (KBS II). These summary reports were supported by 120 technical reports prepared by 450 experts. The project engaged 70 private and governmental institutions at a total cost of US $15 million. The KBS-I and KBS-II reports are summarized in this document, as are also continued waste research efforts carried out by KBS, SKBF, PRAV, ASEA and other Swedish organizations. The KBS reports describe all steps (except reprocessing) in handling chain from removal from a reactor of spent fuel elements until their radioactive waste products are finally disposed of, in canisters, in an underground granite depository. The KBS concept relies on engineered multibarrier systems in combination with final storage in thoroughly investigated stable geologic formations. This report also briefly describes other activities carried out by the nuclear industry, namely, the construction of a central storage facility for spent fuel elements (to be in operation by 1985), a repository for reactor waste (to be in operation by 1988), and an intermediate storage facility for vitrified high-level waste (to be in operation by 1990). The R and D activities are updated to September 1981.

  14. Proceedings of the eighth symposium on training of nuclear facility personnel

    SciTech Connect

    Not Available

    1989-04-01

    This conference brought together those persons in the nuclear industry who have a vital interest in the training and licensing of nuclear reactor and nuclear fuel processing plant operators, senior operators, and support personnel for the purpose of an exchange of ideas and information related to the various aspects of training, retraining, examination, and licensing. The document contains 64 papers; each paper was abstracted for the data.

  15. Algorithm for decision support as the tool for control system of industries with variable assortment of products

    NASA Astrophysics Data System (ADS)

    Ladaniuk, Anatolii; Ivashchuk, Viacheslav; Kisała, Piotr; Askarova, Nursanat; Sagymbekova, Azhar

    2015-12-01

    Conditions of diversification of enterprise products are involving for changes of higher levels of management hierarchy, so it's leading by tasks correcting and changing schedule for operating of production plans. Ordinary solve by combination of enterprise resource are planning and management execution system often has exclusively statistical content. So, the development of decision support system, that helps to use knowledge about subject for capabilities estimating and order of operation of production object is relevant in this time.

  16. U.S. Department of Defense Services Contract Spending and the Supporting Industrial Base, 2000-2011

    DTIC Science & Technology

    2012-04-30

    provided in the FPDS data). The CSIS also researched all the mergers and acquisitions by defense contractors, as well as joint ventures among DoD service...Health Net. The impact of mergers and acquisitions is also evident, as three of the top 20 contractors in 2000 were later acquired by Northrop...Prescribed by ANSI Std Z39-18 The research presented at the symposium was supported by the acquisition chair of the Graduate School of Business

  17. Report of the Joint Industry - DoD Task Force on Computer Aided Logistic Support (CALS). Volume 1. Summary.

    DTIC Science & Technology

    1985-06-01

    features , computer optimization will be applied to maintenance tasks (via modeling of maintenance scenarios resulting from defined battle scenarios...34illities" engineers’ own experience, with little or no tradeoff between performance-related and support-related design features . This is due to the lack...implementable but will also be translated to design features to ensure compliance. (5). Accurate and Timely Analyses. The many reliability

  18. National Nanotechnology Initiative. Research and Development Supporting the Next Industrial Revolution. Supplement to the President’s 2004 Budget

    DTIC Science & Technology

    2004-01-01

    Aeronautics and Space Administration ( NASA ) Minoo N. Dastoor Murray S. Hirschbein National Institutes of Health (NIH) Eleni Kousvelari Jeffery A. Schloss...innovative technologies. Many agencies such as DOD, DOE, EPA, NASA , NIH, NIST, and USDA support applied research aimed at devel- oping technology related to...DHS Department of Homeland Security IA Intelligence Agencies DOC Department of Commerce NASA National Aeronautics and Space Administration DOD

  19. Promise and challenges with the use of mobile applications to support and improve patient care: an industry perspective.

    PubMed

    Bucklen, K W; Abbott, B M

    2014-05-01

    Mobile applications represent an immense opportunity to support and improve patient health care, as the scope and functionality of medical apps are enabling physicians and patients to manage care in new, fast, and personalized ways. Several challenges exist in medical-app development, including careful attention to quality systems, medical-device regulation, and app life span. Despite these complexities, we find that development of mobile medical apps is a worthwhile undertaking given their potential to improve outcomes for patients.

  20. A system for the calculation and visualisation of radiation field for maintenance support in nuclear power plants.

    PubMed

    Ohga, Yukiharu; Fukuda, Mitsuko; Shibata, Kiyotaka; Kawakami, Takashi; Matsuzaki, Tomokazu

    2005-01-01

    A system has been developed to improve the efficiency of maintenance work while decreasing the radiation exposure of maintenance personnel in nuclear power plants. The input data for dose rate calculation are automatically generated by using computer-aided design data. Changes for the input data corresponding to the progress of maintenance work, such as installation of a radiation shield and removal of a component, are easily input interactively on a graphical user interface (GUI). A new method was proposed which searches the sets of source and detector points between which gamma-ray attenuation is changed by the component movement. The calculation is performed only for the changed sets, so that the change of the three-dimensional dose rate distribution is calculated rapidly according to the work progress. The dose rate distribution and the radiation exposure of maintenance personnel are displayed three-dimensionally in colour with plant components and pipes on the GUI.

  1. A Decision Support System Coupling Fuzzy Logic and Probabilistic Graphical Approaches for the Agri-Food Industry: Prediction of Grape Berry Maturity.

    PubMed

    Perrot, Nathalie; Baudrit, Cédric; Brousset, Jean Marie; Abbal, Philippe; Guillemin, Hervé; Perret, Bruno; Goulet, Etienne; Guerin, Laurence; Barbeau, Gérard; Picque, Daniel

    2015-01-01

    Agri-food is one of the most important sectors of the industry and a major contributor to the global warming potential in Europe. Sustainability issues pose a huge challenge for this sector. In this context, a big issue is to be able to predict the multiscale dynamics of those systems using computing science. A robust predictive mathematical tool is implemented for this sector and applied to the wine industry being easily able to be generalized to other applications. Grape berry maturation relies on complex and coupled physicochemical and biochemical reactions which are climate dependent. Moreover one experiment represents one year and the climate variability could not be covered exclusively by the experiments. Consequently, harvest mostly relies on expert predictions. A big challenge for the wine industry is nevertheless to be able to anticipate the reactions for sustainability purposes. We propose to implement a decision support system so called FGRAPEDBN able to (1) capitalize the heterogeneous fragmented knowledge available including data and expertise and (2) predict the sugar (resp. the acidity) concentrations with a relevant RMSE of 7 g/l (resp. 0.44 g/l and 0.11 g/kg). FGRAPEDBN is based on a coupling between a probabilistic graphical approach and a fuzzy expert system.

  2. A Decision Support System Coupling Fuzzy Logic and Probabilistic Graphical Approaches for the Agri-Food Industry: Prediction of Grape Berry Maturity

    PubMed Central

    Brousset, Jean Marie; Abbal, Philippe; Guillemin, Hervé; Perret, Bruno; Goulet, Etienne; Guerin, Laurence; Barbeau, Gérard; Picque, Daniel

    2015-01-01

    Agri-food is one of the most important sectors of the industry and a major contributor to the global warming potential in Europe. Sustainability issues pose a huge challenge for this sector. In this context, a big issue is to be able to predict the multiscale dynamics of those systems using computing science. A robust predictive mathematical tool is implemented for this sector and applied to the wine industry being easily able to be generalized to other applications. Grape berry maturation relies on complex and coupled physicochemical and biochemical reactions which are climate dependent. Moreover one experiment represents one year and the climate variability could not be covered exclusively by the experiments. Consequently, harvest mostly relies on expert predictions. A big challenge for the wine industry is nevertheless to be able to anticipate the reactions for sustainability purposes. We propose to implement a decision support system so called FGRAPEDBN able to (1) capitalize the heterogeneous fragmented knowledge available including data and expertise and (2) predict the sugar (resp. the acidity) concentrations with a relevant RMSE of 7 g/l (resp. 0.44 g/l and 0.11 g/kg). FGRAPEDBN is based on a coupling between a probabilistic graphical approach and a fuzzy expert system. PMID:26230334

  3. Decision support for environmental management of industrial non-hazardous secondary materials: New analytical methods combined with simulation and optimization modeling.

    PubMed

    Little, Keith W; Koralegedara, Nadeesha H; Northeim, Coleen M; Al-Abed, Souhail R

    2017-03-08

    Non-hazardous solid materials from industrial processes, once regarded as waste and disposed in landfills, offer numerous environmental and economic advantages when put to beneficial uses (BUs). Proper management of these industrial non-hazardous secondary materials (INSM) requires estimates of their probable environmental impacts among disposal as well as BU options. The U.S. Environmental Protection Agency (EPA) has recently approved new analytical methods (EPA Methods 1313-1316) to assess leachability of constituents of potential concern in these materials. These new methods are more realistic for many disposal and BU options than historical methods, such as the toxicity characteristic leaching protocol. Experimental data from these new methods are used to parameterize a chemical fate and transport (F&T) model to simulate long-term environmental releases from flue gas desulfurization gypsum (FGDG) when disposed of in an industrial landfill or beneficially used as an agricultural soil amendment. The F&T model is also coupled with optimization algorithms, the Beneficial Use Decision Support System (BUDSS), under development by EPA to enhance INSM management.

  4. Opening Doors of Opportunity to Develop the Future Nuclear Workforce - 13325

    SciTech Connect

    Mets, Mindy

    2013-07-01

    The United States' long-term demand for highly skilled nuclear industry workers is well-documented by the Nuclear Energy Institute. In addition, a study commissioned by the SRS Community Reuse Organization concludes that 10,000 new nuclear workers are needed in the two-state region of Georgia and South Carolina alone. Young adults interested in preparing for these nuclear careers must develop specialized skills and knowledge, including a clear understanding of the nuclear workforce culture. Successful students are able to enter well-paying career fields. However, the national focus on nuclear career opportunities and associated training and education programs has been minimal in recent decades. Developing the future nuclear workforce is a challenge, particularly in the midst of competition for similar workers from various industries. In response to regional nuclear workforce development needs, the SRS Community Reuse Organization established the Nuclear Workforce Initiative (NWI{sup R}) to promote and expand nuclear workforce development capabilities by facilitating integrated partnerships. NWI{sup R} achievements include a unique program concept called NWI{sup R} Academies developed to link students with nuclear career options through firsthand experiences. The academies are developed and conducted at Aiken Technical College and Augusta Technical College with support from workforce development organizations and nuclear employers. Programs successfully engage citizens in nuclear workforce development and can be adapted to other communities focused on building the future nuclear workforce. (authors)

  5. Fifty years with nuclear fission

    SciTech Connect

    Behrens, J.W.; Carlson, A.D. )

    1989-01-01

    The news of the discovery of nuclear fission, by Otto Hahn and Fritz Strassmann in Germany, was brought to the United States by Niels Bohr in January 1939. Since its discovery, the United States, and the world for that matter, has never been the same. It therefore seemed appropriate to acknowledge the fifieth anniversary of its discovery by holding a topical meeting entitled, Fifty Years with Nuclear Fission,'' in the United States during the year 1989. The objective of the meeting was to bring together pioneers of the nuclear industry and other scientists and engineers to report on reminiscences of the past and on the more recent development in fission science and technology. The conference highlighted the early pioneers of the nuclear industry by dedicated a full day (April 26), consisting of two plenary sessions, at the National Academy of Sciences (NAS) in Washington, DC. More recent developments in fission science and technology in addition to historical reflections were topics for two fully days of sessions (April 27 and 28) at the main site of the NIST in Gaithersburg, Maryland. The wide range of topics covered in this Volume 1 by this topical meeting included plenary invited, and contributed sessions entitled: Preclude to the First Chain Reaction -- 1932 to 1942; Early Fission Research -- Nuclear Structure and Spontaneous Fission; 50 Years of Fission, Science, and Technology; Nuclear Reactors, Secure Energy for the Future; Reactors 1; Fission Science 1; Safeguards and Space Applications; Fission Data; Nuclear Fission -- Its Various Aspects; Theory and Experiments in Support of Theory; Reactors and Safeguards; and General Research, Instrumentation, and By-Product. The individual papers have been cataloged separately.

  6. Emerging Environmental Justice Issues in Nuclear Power and Radioactive Contamination

    PubMed Central

    Kyne, Dean; Bolin, Bob

    2016-01-01

    Nuclear hazards, linked to both U.S. weapons programs and civilian nuclear power, pose substantial environment justice issues. Nuclear power plant (NPP) reactors produce low-level ionizing radiation, high level nuclear waste, and are subject to catastrophic contamination events. Justice concerns include plant locations and the large potentially exposed populations, as well as issues in siting, nuclear safety, and barriers to public participation. Other justice issues relate to extensive contamination in the U.S. nuclear weapons complex, and the mining and processing industries that have supported it. To approach the topic, first we discuss distributional justice issues of NPP sites in the U.S. and related procedural injustices in siting, operation, and emergency preparedness. Then we discuss justice concerns involving the U.S. nuclear weapons complex and the ways that uranium mining, processing, and weapons development have affected those living downwind, including a substantial American Indian population. Next we examine the problem of high-level nuclear waste and the risk implications of the lack of secure long-term storage. The handling and deposition of toxic nuclear wastes pose new transgenerational justice issues of unprecedented duration, in comparison to any other industry. Finally, we discuss the persistent risks of nuclear technologies and renewable energy alternatives. PMID:27420080

  7. Emerging Environmental Justice Issues in Nuclear Power and Radioactive Contamination.

    PubMed

    Kyne, Dean; Bolin, Bob

    2016-07-12

    Nuclear hazards, linked to both U.S. weapons programs and civilian nuclear power, pose substantial environment justice issues. Nuclear power plant (NPP) reactors produce low-level ionizing radiation, high level nuclear waste, and are subject to catastrophic contamination events. Justice concerns include plant locations and the large potentially exposed populations, as well as issues in siting, nuclear safety, and barriers to public participation. Other justice issues relate to extensive contamination in the U.S. nuclear weapons complex, and the mining and processing industries that have supported it. To approach the topic, first we discuss distributional justice issues of NPP sites in the U.S. and related procedural injustices in siting, operation, and emergency preparedness. Then we discuss justice concerns involving the U.S. nuclear weapons complex and the ways that uranium mining, processing, and weapons development have affected those living downwind, including a substantial American Indian population. Next we examine the problem of high-level nuclear waste and the risk implications of the lack of secure long-term storage. The handling and deposition of toxic nuclear wastes pose new transgenerational justice issues of unprecedented duration, in comparison to any other industry. Finally, we discuss the persistent risks of nuclear technologies and renewable energy alternatives.

  8. Proposed Holistic Strategy for the Closure of F-Area, A Large Nuclear Industrial Complex at the Savannah River Site, South Carolina

    SciTech Connect

    SHEDROW, CB

    2004-02-10

    F-Area is a large nuclear complex located near the center of the Department of Energy's (DOEs) Savannah River Site in South Carolina. The present closure strategy for F-Area is based on established SRS protocol for a site-specific, graded approach to deactivation and decommissioning. Uncontaminated facilities will be closed under the National Environmental Policy Act (NEPA). Facilities requiring removal or in-situ disposition of residual chemical and/or radiological inventories will be decommissioned under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). The F-Area Tank Farm, which is permitted under the Clean Water Act, will be closed in accordance with an industrial wastewater closure plan. F-Area closure will also involve the near- and long-term remediation of contaminated soil and groundwater resources. The proposed holistic F-Area closure strategy would enhance the existing project-specific SRS closure protocol by incorporating a comprehensive area-wide groundwater modeling tool, or Composite Analysis. The use of this methodology would allow for the assessment of the relative impacts of individual projects, as well as the cumulative effect of all F-Area closure actions, on area groundwater resources. Other critical elements of the proposed strategy include (i) the consistent use of site-specific Risk Assessments (RAs) and Performance Assessments (PAs), (ii) the closer integration of selected soil and groundwater closure projects and near-term D and D projects, and (iii) the creation of an Area Core Team (ACT) consisting of DOE and selected regulator decision-makers to direct area D and D and environmental restoration activities. This holistic approach would facilitate the effective targeting of agency resources on high priority projects whose closure would have the greatest impact on achieving the desired area-wide risk-based end-state and accelerate delisting of F-Area from the National Priority List (NPL).

  9. Nanocellulose/nanobentonite composite anchored with multi-carboxyl functional groups as an adsorbent for the effective removal of Cobalt(II) from nuclear industry wastewater samples.

    PubMed

    Anirudhan, T S; Deepa, J R; Christa, J

    2016-04-01

    A novel adsorbent, poly(itaconic acid/methacrylic acid)-grafted-nanocellulose/nanobentonite composite [P(IA/MAA)-g-NC/NB] with multi carboxyl functional groups for the effective removal of Cobalt(II) [Co(II)] from aqueous solutions. The adsorbent was characterized using FTIR, XRD, SEM-EDS, AFM and potentiometric titrations before and after adsorption of Co(II) ions. FTIR spectra revealed that Co(II) adsorption on to the polymer may be due to the involvement of COOH groups. The surface morphological changes were observed by the SEM images. The pH was optimized as 6.0. An adsorbent dose of 2.0g/L found to be sufficient for the complete removal of Co(II) from 100mg/L at room temperature. Pseudo-first-order and pseudo-second-order models were tested to describe kinetic data and adsorption of Co(II) follows pseudo-second-order model. The equilibrium attained at 120min. Isotherm studies were conducted and data were analyzed using Langmuir, Freundlich and Sips isotherm models and best fit was Sips model. Thermodynamic study confirmed endothermic and physical nature of adsorption of the Co(II) onto the adsorbent. Desorption experiments were done with 0.1MHCl proved that without significant loss in performance adsorbent could be reused for six cycles. The practical efficacy and effectiveness of the adsorbent were tested using nuclear industrial wastewater. A double stage batch adsorption system was designed from the adsorption isotherm data of Co(II) by constructing operating lines.

  10. Nuclear Data Needs and Capabilities for Applications

    SciTech Connect

    Brown, D.

    2015-05-27

    In July 2014, DOE NP carried out a review of the US Nuclear Data Program. This led to several recommendations, including that the USNDP should “devise effective and transparent mechanisms to solicit input and feedback from all stakeholders on nuclear data needs and priorities.” The review also recommended that USNDP pursue experimental activities of relevance to nuclear data; the revised 2014 Mission Statement accordingly states that the USNDP uses “targeted experimental studies” to address gaps in nuclear data. In support of these recommendations, DOE NP requested that USNDP personnel organize a Workshop on Nuclear Data Needs and Capabilities for Applications (NDNCA). This Workshop was held at Lawrence Berkeley National Laboratory (LBNL) on 27-29 May 2015. The goal of the NDNCA Workshop was to compile nuclear data needs across a wide spectrum of applied nuclear science, and to provide a summary of associated capabilities (accelerators, reactors, spectrometers, etc.) available for the required measurements. The first two days of the workshop consisted of 25 plenary talks by speakers from 16 different institutions, on nuclear energy (NE), national security (NS), isotope production (IP), and industrial applications (IA). There were also shorter “capabilities” talks that described the experimental facilities and instrumentation available for the measurement of nuclear data. This was followed by a third day of topic-specific “breakout” sessions and a final closeout session. The agenda and copies of these talks are available online at http://bang.berkeley.edu/events/NDNCA/agenda. The importance of nuclear data to both basic and applied nuclear science was reflected in the fact that while the impetus for the workshop arose from the 2014 USNDP review, joint sponsorship for the workshop was provided by the Nuclear Science and Security Consortium, a UC-Berkeley based organization funded by the National Nuclear Security Administration (NNSA).

  11. Optimizing Characterization of Site Hydrology in Support of New Reactor Licensing at the U.S. Nuclear Regulatory Commission (Invited)

    NASA Astrophysics Data System (ADS)

    Nicholson, T. J.; Raione, R.; Ahn, H.; Barnhurst, D.; Giacinto, J.; McBride, M.; Tiruneh, N. D.

    2009-12-01

    The NRC regulates the civilian use of radioactive materials and facilities in an open and transparent manner. The NRC regulatory criteria are designed to protect human health and safety, and the environment by regulating nuclear facilities. During review of new reactor licensing applications, NRC staff reviews and independently verifies hydrogeologic information submitted by the applicant in several topical areas such as development and testing of Conceptual Site Models (CSM) which may involve perched aquifers; engineered water level fluctuations of surface-water reservoirs; ground-water collector wells and local ground-water uses; design-basis ground-water levels for structural analysis; analysis of scenarios for potential release of radionuclides to the subsurface; deep well injection of effluents; and monitoring to detect radionuclide releases. This information is reviewed in a systematic manner in accordance with NRC requirements and guidance to evaluate safety and environmental impacts and reduce the uncertainties for these impacts. NRC licensing staff is reviewing 14 applications for siting new reactors. Experience gained through these licensing activities has shown the value of using site-specific data to evaluate the CSM and its use to assess design and operational issues. Optimizing the information flow process through a systemically and thorough review process creates efficiencies. Through an iterative process of evaluating various geographical settings and associated ground-water conditions, NRC staff has developed methods to minimize prediction uncertainty through the use of confirmatory analyses performed under conservative, hierarchal approaches.

  12. The Planning, Licensing, Modifications, and Use of a Russian Vessel for Shipping Spent Nuclear Fuel by Sea in Support of the DOE RRRFR Program

    SciTech Connect

    Michael Tyacke; Dr. Igor Bolshinsky; Wlodzimierz Tomczak; Sergey Naletov; Oleg Pichugin

    2001-10-01

    The Russian Research Reactor Fuel Return (RRRFR) Program, under the U.S. Department of Energy’s Global Threat Reduction Initiative, began returning Russian-supplied high-enriched uranium (HEU) spent nuclear fuel (SNF), stored at Russian-designed research reactors throughout the world, to Russia in January 2006. During the first years of making HEU SNF shipments, it became clear that the modes of transportation needed to be expanded from highway and railroad to include sea and air to meet the extremely aggressive commitment of completing the first series of shipments by the end of 2010. The first shipment using sea transport was made in October 2008 and used a non-Russian flagged vessel. The Russian government reluctantly allowed a one-time use of the foreign-owned vessel into their highly secured seaport, with the understanding that any future shipments would be made using a vessel owned and operated by a Russian company. ASPOL-Baltic of St. Petersburg, Russia, owns and operates a small fleet of vessels and has a history of shipping nuclear materials. ASPOL-Baltic’s vessels were licensed for shipping nuclear materials; however, they were not licensed to transport SNF materials. After a thorough review of ASPOL Baltic’s capabilities and detailed negotiations, it was agreed that a contract would be let with ASPOL-Baltic to license and refit their MCL Trader vessel for hauling SNF in support of the RRRFR Program. This effort was funded through a contract between the RRRFR Program, Idaho National Laboratory, and Radioactive Waste Management Plant of Swierk, Poland. This paper discusses planning, Russian and international maritime regulations and requirements, Russian authorities’ reviews and approvals, licensing, design, and modifications made to the vessel in preparation for SNF shipments. A brief summary of actual shipments using this vessel, experiences, and lessons learned also are described.

  13. Guidance for industry: patient-reported outcome measures: use in medical product development to support labeling claims: draft guidance.

    PubMed

    2006-10-11

    This guidance describes how the FDA evaluates patient-reported outcome (PRO) instruments used as effectiveness endpoints in clinical trials. It also describes our current thinking on how sponsors can develop and use study results measured by PRO instruments to support claims in approved product labeling (see appendix point 1). It does not address the use of PRO instruments for purposes beyond evaluation of claims made about a drug or medical product in its labeling. By explicitly addressing the review issues identified in this guidance, sponsors can increase the efficiency of their endpoint discussions with the FDA during the product development process, streamline the FDA's review of PRO endpoint adequacy, and provide optimal information about the patient's perspective of treatment benefit at the time of product approval. A PRO is a measurement of any aspect of a patient's health status that comes directly from the patient (i.e., without the interpretation of the patient's responses by a physician or anyone else). In clinical trials, a PRO instrument can be used to measure the impact of an intervention on one or more aspects of patients' health status, hereafter referred to as PRO concepts, ranging from the purely symptomatic (response of a headache) to more complex concepts (e.g., ability to carry out activities of daily living), to extremely complex concepts such as quality of life, which is widely understood to be a multidomain concept with physical, psychological, and social components. Data generated by a PRO instrument can provide evidence of a treatment benefit from the patient perspective. For this data to be meaningful, however, there should be evidence that the PRO instrument effectively measures the particular concept that is studied. Generally, findings measured by PRO instruments may be used to support claims in approved product labeling if the claims are derived from adequate and well-controlled investigations that use PRO instruments that reliably

  14. Promyelocytic leukemia nuclear bodies support a late step in DNA double-strand break repair by homologous recombination.

    PubMed

    Yeung, Percy Luk; Denissova, Natalia G; Nasello, Cara; Hakhverdyan, Zhanna; Chen, J Don; Brenneman, Mark A

    2012-05-01

    The PML protein and PML nuclear bodies (PML-NB) are implicated in multiple cellular functions relevant to tumor suppression, including DNA damage response. In most cases of acute promyelocytic leukemia, the PML and retinoic acid receptor alpha (RARA) genes are translocated, resulting in expression of oncogenic PML-RARα fusion proteins. PML-NB fail to form normally, and promyelocytes remain in an undifferentiated, abnormally proliferative state. We examined the involvement of PML protein and PML-NB in homologous recombinational repair (HRR) of chromosomal DNA double-strand breaks. Transient overexpression of wild-type PML protein isoforms produced hugely enlarged or aggregated PML-NB and reduced HRR by ~2-fold, suggesting that HRR depends to some extent upon normal PML-NB structure. Knockdown of PML by RNA interference sharply attenuated formation of PML-NB and reduced HRR by up to 20-fold. However, PML-knockdown cells showed apparently normal induction of H2AX phosphorylation and RAD51 foci after DNA damage by ionizing radiation. These findings indicate that early steps in HRR, including recognition of DNA double-strand breaks, initial processing of ends, and assembly of single-stranded DNA/RAD51 nucleoprotein filaments, do not depend upon PML-NB. The HRR deficit in PML-depleted cells thus reflects inhibition of later steps in the repair pathway. Expression of PML-RARα fusion proteins disrupted PML-NB structure and reduced HRR by up to 10-fold, raising the possibility that defective HRR and resulting genomic instability may figure in the pathogenesis, progression and relapse of acute promyelocytic leukemia.

  15. Nuclear markers support the mitochondrial phylogeny of Vipera ursinii-renardi complex (Squamata: Viperidae) and species status for the Greek meadow viper.

    PubMed

    Mizsei, Edvárd; Jablonski, Daniel; Roussos, Stephanos A; Dimaki, Maria; Ioannidis, Yannis; Nilson, Göran; Nagy, Zoltán T

    2017-01-31

    Meadow vipers (Vipera ursinii-renardi complex) are small-bodied snakes that live in either lowland grasslands or montane subalpine-alpine meadows spanning a distribution from France to western China. This complex has previously been the focus of several taxonomic studies which were based mainly on morphological, allozyme or immunological characters and did not clearly resolve the relationships between the various taxa. Recent mitochondrial DNA analyses found unexpected relationships within the complex which had taxonomical consequences for the detected lineages. The most surprising was the basal phylogenetic position of Vipera ursinii graeca, a taxon described almost 30 years ago from the mountains of Greece. We present here new analyses of three nuclear markers (BDNF, NT3, PRLR; a first for studies of meadow and steppe vipers) as well as analyses of newly obtained mitochondrial DNA sequences (CYT B, ND4).Our Bayesian analyses of nuclear sequences are concordant with previous studies of mitochondrial DNA, in that the phylogenetic position of the graeca clade is a clearly distinguished and distinct lineage separated from all other taxa in the complex. These phylogenetic results are also supported by a distinct morphology, ecology and isolated distribution of this unique taxon. Based on several data sets and an integrative species concept we recommend to elevate this taxon to species level: Vipera graeca Nilson & Andrén, 1988 stat. nov.

  16. LWRS II&C Industry and Regulatory Engagement Activities for FY 11

    SciTech Connect

    Ken Thomas

    2011-09-01

    To ensure broad industry support and coordination for the Advanced Instrumentation, Information, and Controls (II&C) Systems Technologies research pathway, an engagement process will be continually pursued with nuclear asset owners, vendors, and suppliers, Nuclear Regulatory Commission (NRC), and the major industry support organizations of Electric Power Research Institute (EPRI), Institute of Nuclear Power Operations (INPO), and Nuclear Energy Institute (NEI). Nuclear asset owner engagement is a necessary and enabling activity to obtain data and accurate characterization of long-term operational challenges, assess the suitability of proposed research for addressing long-term needs, and gain access to data and representative infrastructure and expertise needed to ensure success of the proposed research and development (R&D) activities. Engagement with vendors and suppliers will ensure that vendor expectations and needs can be translated into requirements that can be met through technology commercialization.

  17. New Mitochondrial and Nuclear Evidences Support Recent Demographic Expansion and an Atypical Phylogeographic Pattern in the Spittlebug Philaenus spumarius (Hemiptera, Aphrophoridae)

    PubMed Central

    Rodrigues, Ana S. B.; Silva, Sara E.; Marabuto, Eduardo; Silva, Diogo N.; Wilson, Mike R.; Thompson, Vinton; Yurtsever, Selçuk; Halkka, Antti; Borges, Paulo A. V.; Quartau, José A.; Paulo, Octávio S.; Seabra, Sofia G.

    2014-01-01

    Philaenus spumarius is a widespread insect species in the Holarctic region. Here, by focusing on the mtDNA gene COI but also using the COII and Cyt b genes and the nuclear gene EF-1α, we tried to explain how and when its current biogeographic pattern evolved by providing time estimates of the main demographic and evolutionary events and investigating its colonization patterns in and out of Eurasia. Evidence of recent divergence and expansion events at less than 0.5 Ma ago indicate that climate fluctuations in the Mid-Late Pleistocene were important in shaping the current phylogeographic pattern of the species. Data support a first split and differentiation of P. spumarius into two main mitochondrial lineages: the “western”, in the Mediterranean region and the “eastern”, in Anatolia/Caucasus. It also supports a following differentiation of the “western” lineage into two sub-lineages: the “western-Mediterranean”, in Iberia and the “eastern-Mediterranean” in the Balkans. The recent pattern seems to result from postglacial range expansion from Iberia and Caucasus/Anatolia, thus not following one of the four common paradigms. Unexpected patterns of recent gene-flow events between Mediterranean peninsulas, a close relationship between Iberia and North Africa, as well as high levels of genetic diversity being maintained in northern Europe were found. The mitochondrial pattern does not exactly match to the nuclear pattern suggesting that the current biogeographic pattern of P. spumarius may be the result of both secondary admixture and incomplete lineage sorting. The hypothesis of recent colonization of North America from both western and northern Europe is corroborated by our data and probably resulted from accidental human translocations. A probable British origin for the populations of the Azores and New Zealand was revealed, however, for the Azores the distribution of populations in high altitude native forests is somewhat puzzling and may imply a

  18. The Nuclear Renaissance in the United States

    SciTech Connect

    Buongiorno, Jacopo

    2008-07-30

    Nuclear power currently provides 20% of the electricity generation in the U.S. and about 16% worldwide. As a carbon-free energy source, nuclear is receiving a lot of attention by industry, lawmakers and environmental groups, as they attempt to resolve the issue of man-made climate change. For the first time in 30 years several U.S. electric utilities have applied for construction and operation licenses of new nuclear power plants. This talk will review the safety, operational and economic record of the existing U.S. commercial reactor fleet, will provide an overview of the reactor designs considered for the new wave of plant construction, and will discuss several research projects being conducted at the Massachusetts Institute of Technology to support the expansion of nuclear power in the U.S. and overseas.

  19. Reactor Physics Parametric and Depletion Studies in Support of TRISO Particle Fuel Specification for the Next Generation Nuclear Plant

    SciTech Connect

    James W. Sterbentz; Bren Phillips; Robert L. Sant; Gray S. Chang; Paul D. Bayless

    2003-09-01

    Reactor physics calculations were initiated to answer several major questions related to the proposed TRISO-coated particle fuel that is to be used in the prismatic Very High Temperature Reactor (VHTR) or the Next Generation Nuclear Plant (NGNP). These preliminary design evaluation calculations help ensure that the upcoming fuel irradiation tests will test appropriate size and type of fuel particles for a future NGNP reactor design. Conclusions from these calculations are expected to confirm and suggest possible modifications to the current particle fuel parameters specified in the evolving Fuel Specification. Calculated results dispel the need for a binary fuel particle system, which is proposed in the General Atomics GT-MHR concept. The GT-MHR binary system is composed of both a fissile and fertile particle with 350- and 500- micron kernel diameters, respectively. For the NGNP reactor, a single fissile particle system (single UCO kernel size) can meet the reactivity and power cycle length requirements demanded of the NGNP. At the same time, it will provide substantial programmatic cost savings by eliminating the need for dual particle fabrication process lines and dual fuel particle irradiation tests required of a binary system. Use of a larger 425-micron kernel diameter single fissile particle (proposed here), as opposed to the 350-micron GT-MHR fissile particle size, helps alleviate current compact particle packing fractions fabrication limitations (<35%), improves fuel block loading for higher n-batch reload options, and tracks the historical correlation between particle size and enrichment (10 and 14 wt% U-235 particle enrichments are proposed for the NGNP). Overall, the use of the slightly larger kernel significantly broadens the NGNP reactor core design envelope and provides increased design margin to accommodate the (as yet) unknown final NGNP reactor design. Maximum power-peaking factors are calculated for both the initial and equilibrium NGNP cores

  20. Results of 2001 Groundwater Sampling in Support of Conditional No Longer Contained-In Determination for the Snake River Plain Aquifer in the Vicinity of the Idaho Nuclear Technology and Engineering Center

    SciTech Connect

    Meachum, T.R.

    2002-04-26

    This report summarizes the results of sampling five groundwater monitoring wells in the vicinity of the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory in 2001. Information on general sampling practices, quality assurance practices, parameter concentrations, representativeness of sampling results, and cumulative cancer risk are presented. The information is provided to support a conditional No Longer Contained-In Determination for the Snake River Plain Aquifer in the vicinity of the Idaho Nuclear Technology and Engineering Center.

  1. Anode regeneration following carbon depositions in an industrial-sized anode supported solid oxide fuel cell operating on synthetic diesel reformate

    NASA Astrophysics Data System (ADS)

    Subotić, Vanja; Schluckner, Christoph; Mathe, Jörg; Rechberger, Jürgen; Schroettner, Hartmuth; Hochenauer, Christoph

    2015-11-01

    Carbon deposition is a primary concern during operation of solid oxide fuel cells (SOFCs) fueled with carbon-containing fuels. It leads to cell degradation and thus reduces SOFC sustained operation and durability. This paper reports on an experimental investigation of carbon formation on the nickel/yttria-stabilized zirconia (Ni/YSZ) anode of an anode-supported SOFC and its regeneration. The cell was fueled with a synthetically produced diesel reformate to investigate and simulate the cell behavior under real operating conditions. For this purpose the cell was operated under load to determine the critical operating time. Rapid carbon generation, such as at open circuit voltage (OCV), can be prevented when the cell is under load. Carbon depositions were detected using scanning electron microscopy (SEM) and further analyzed by Raman spectroscopy. Industrial-size cells suitable for commercial applications were studied. This study proves the reversibility of carbon formation and the reproducibility of the regeneration process. It shows that carbon formations can be recognized and effectively, fully and cell-protecting regenerated. It indicates the excellent possibility of using SOFCs in the automotive industry as an auxiliary power unit (APU) or combined power-heat unit, operated with diesel reformate, without danger from cell degradation caused by carbon-containing fuels.

  2. Contrast variation by dynamic nuclear polarization and time-of-flight small-angle neutron scattering. I. Application to industrial multi-component nanocomposites1

    PubMed Central

    Noda, Yohei; Koizumi, Satoshi; Masui, Tomomi; Mashita, Ryo; Kishimoto, Hiroyuki; Yamaguchi, Daisuke; Kumada, Takayuki; Takata, Shin-ichi; Ohishi, Kazuki; Suzuki, Jun-ichi

    2016-01-01

    Dynamic nuclear polarization (DNP) at low temperature (1.2 K) and high magnetic field (3.3 T) was applied to a contrast variation study in small-angle neutron scattering (SANS) focusing on industrial rubber materials. By varying the scattering contrast by DNP, time-of-flight SANS profiles were obtained at the pulsed neutron source of the Japan Proton Accelerator Research Complex (J-PARC). The concentration of a small organic molecule, (2,2,6,6-tetramethylpiperidine-1-yl)oxy (TEMPO), was carefully controlled by a doping method using vapour sorption into the rubber specimens. With the assistance of microwave irradiation (94 GHz), almost full polarization of the paramagnetic electronic spin of TEMPO was transferred to the spin state of hydrogen (protons) in the rubber materials to obtain a high proton spin polarization (P H). The following samples were prepared: (i) a binary mixture of styrene–butadiene random copolymer (SBR) with silica particles (SBR/SP); and (ii) a ternary mixture of SBR with silica and carbon black particles (SBR/SP/CP). For the binary mixture (SBR/SP), the intensity of SANS significantly increased or decreased while keeping its q dependence for P H = −35% or P H = 40%, respectively. The q behaviour of SANS for the SBR/SP mixture can be reproduced using the form factor of a spherical particle. The intensity at low q (∼0.01 Å−1) varied as a quadratic function of P H and indicated a minimum value at P H = 30%, which can be explained by the scattering contrast between SP and SBR. The scattering intensity at high q (∼0.3 Å−1) decreased with increasing P H, which is attributed to the incoherent scattering from hydrogen. For the ternary mixture (SBR/SP/CP), the q behaviour of SANS was varied by changing P H. At P H = −35%, the scattering maxima originating from the form factor of SP prevailed, whereas at P H = 29% and P H = 38%, the scattering maxima disappeared. After decomposition of the total SANS according to inverse matrix

  3. Contrast variation by dynamic nuclear polarization and time-of-flight small-angle neutron scattering. I. Application to industrial multi-component nanocomposites.

    PubMed

    Noda, Yohei; Koizumi, Satoshi; Masui, Tomomi; Mashita, Ryo; Kishimoto, Hiroyuki; Yamaguchi, Daisuke; Kumada, Takayuki; Takata, Shin-Ichi; Ohishi, Kazuki; Suzuki, Jun-Ichi

    2016-12-01

    Dynamic nuclear polarization (DNP) at low temperature (1.2 K) and high magnetic field (3.3 T) was applied to a contrast variation study in small-angle neutron scattering (SANS) focusing on industrial rubber materials. By varying the scattering contrast by DNP, time-of-flight SANS profiles were obtained at the pulsed neutron source of the Japan Proton Accelerator Research Complex (J-PARC). The concentration of a small organic molecule, (2,2,6,6-tetramethylpiperidine-1-yl)oxy (TEMPO), was carefully controlled by a doping method using vapour sorption into the rubber specimens. With the assistance of microwave irradiation (94 GHz), almost full polarization of the paramagnetic electronic spin of TEMPO was transferred to the spin state of hydrogen (protons) in the rubber materials to obtain a high proton spin polarization (PH). The following samples were prepared: (i) a binary mixture of styrene-butadiene random copolymer (SBR) with silica particles (SBR/SP); and (ii) a ternary mixture of SBR with silica and carbon black particles (SBR/SP/CP). For the binary mixture (SBR/SP), the intensity of SANS significantly increased or decreased while keeping its q dependence for PH = -35% or PH = 40%, respectively. The q behaviour of SANS for the SBR/SP mixture can be reproduced using the form factor of a spherical particle. The intensity at low q (∼0.01 Å(-1)) varied as a quadratic function of PH and indicated a minimum value at PH = 30%, which can be explained by the scattering contrast between SP and SBR. The scattering intensity at high q (∼0.3 Å(-1)) decreased with increasing PH, which is attributed to the incoherent scattering from hydrogen. For the ternary mixture (SBR/SP/CP), the q behaviour of SANS was varied by changing PH. At PH = -35%, the scattering maxima originating from the form factor of SP prevailed, whereas at PH = 29% and PH = 38%, the scattering maxima disappeared. After decomposition of the total SANS according to inverse matrix calculations

  4. Technologists for Nuclear Medicine

    ERIC Educational Resources Information Center

    Barnett, Huey D.

    1974-01-01

    Physicians need support personnel for work with radioisotopes in diagnosing dangerous diseases. The Nuclear Medicine Technology (NMT) Program at Hillsborough Community College in Tampa, Florida, is described. (MW)

  5. Independent technical support for the frozen soil barrier installation and operation at the Fukushima Daiichi Nuclear Power Station (F1 Site)

    SciTech Connect

    Looney, Brian B.; Jackson, Dennis G.; Truex, Michael J.; Johnson, Christian D.

    2015-02-23

    TEPCO is implementing a number of water countermeasures to limit the releases and impacts of contaminated water to the surrounding environment. The diverse countermeasures work together in an integrated manner to provide different types, and several levels, of protection. In general, the strategy represents a comprehensive example of a “defense in depth” concept that is used for nuclear facilities around the world. One of the key countermeasures is a frozen soil barrier encircling the damaged reactor facilities. The frozen barrier is intended to limit the flow of water into the area and provide TEPCO the ability to reduce the amount of contaminated water that requires treatment and storage. The National Laboratory team supports the selection of artificial ground freezing and the incorporation of the frozen soil barrier in the contaminated water countermeasures -- the technical characteristics of a frozen barrier are relatively well suited to the Fukushima-specific conditions and the need for inflow reduction. Further, our independent review generally supports the TEPCO/Kajima design, installation strategy and operation plan.

  6. Optimal Model-Based Fault Estimation and Correction for Particle Accelerators and Industrial Plants Using Combined Support Vector Machines and First Principles Models

    SciTech Connect

    Sayyar-Rodsari, Bijan; Schweiger, Carl; /SLAC /Pavilion Technologies, Inc., Austin, TX

    2010-08-25

    Timely estimation of deviations from optimal performance in complex systems and the ability to identify corrective measures in response to the estimated parameter deviations has been the subject of extensive research over the past four decades. The implications in terms of lost revenue from costly industrial processes, operation of large-scale public works projects and the volume of the published literature on this topic clearly indicates the significance of the problem. Applications range from manufacturing industries (integrated circuits, automotive, etc.), to large-scale chemical plants, pharmaceutical production, power distribution grids, and avionics. In this project we investigated a new framework for building parsimonious models that are suited for diagnosis and fault estimation of complex technical systems. We used Support Vector Machines (SVMs) to model potentially time-varying parameters of a First-Principles (FP) description of the process. The combined SVM & FP model was built (i.e. model parameters were trained) using constrained optimization techniques. We used the trained models to estimate faults affecting simulated beam lifetime. In the case where a large number of process inputs are required for model-based fault estimation, the proposed framework performs an optimal nonlinear principal component analysis of the large-scale input space, and creates a lower dimension feature space in which fault estimation results can be effectively presented to the operation personnel. To fulfill the main technical objectives of the Phase I research, our Phase I efforts have focused on: (1) SVM Training in a Combined Model Structure - We developed the software for the constrained training of the SVMs in a combined model structure, and successfully modeled the parameters of a first-principles model for beam lifetime with support vectors. (2) Higher-order Fidelity of the Combined Model - We used constrained training to ensure that the output of the SVM (i.e. the

  7. Small modular reactor modeling using modelica for nuclear-renewable hybrid energy systems applications

    DOE PAGES

    Mikkelson, Daniel; Chang, Chih -Wei; Cetiner, Sacit M.; ...

    2015-10-01

    Here, the U.S. Department of Energy (DOE) supports research and development (R&D) that could lead to more efficient utilization of clean energy generation sources, including renewable and nuclear options, to meet grid demand and industrial thermal energy needs [1]. One hybridization approach being investigated by the DOE Offices of Nuclear Energy (NE) and the DOE Energy Efficiency and Renewable Energy (EERE) is tighter coupling of nuclear and renewable energy sources to better manage overall energy use for the combined electricity, industrial manufacturing, and transportation sectors.

  8. A Nuclear Energy Renaissance: Challenges to Nuclear Weapon Nonproliferation

    DTIC Science & Technology

    2009-03-30

    civilian nuclear power infrastructure. Light water reactors require enriched uranium to operate, albeit at much lower enrichment percentages...the horizon. Twenty-two years after the Chernobyl nuclear reactor accident the world’s nuclear energy industry is booming.1 Nuclear energy is...experiencing a strong revival around the world and in the United States. There are currently 439 nuclear reactors operating worldwide, in 30 countries. Thirty

  9. Data feature: World nuclear power plant capacity 1991

    SciTech Connect

    Not Available

    1992-11-01

    At this point, the future of the nuclear power industry remains largely in doubt. The gloomy predictions about global warming have done little to convince politicians and the public of the benefits of nuclear power. Meanwhile, the setbacks to nuclear have continued apace: The United States has failed to take the expected lead in ordering new nuclear plants. And President-elect Bill Clinton does not consider nuclear a major part of his energy strategy. The situation looks equally bleak in other countries. Canada's biggest utility, Ontario Hydro, was forced under intense political pressure to defer its ambitious nuclear expansion program until after the year 2010. In Europe, the suspension of France's Superphenix fast-breeder reactor in June could stop progress on the technology indefinitely. And the Finnish parliament dropped plans for expansion of nuclear power from its national energy strategy. Developing and semi-industrialized countries, such as Brazil and Argentina, have shown little progress, taking upwards of twenty years to complete plants already under construction. Nuclear's problems seem always to hinge on economics. Nuclear has little chance of revival during the current global recession, especially in countries fighting for their long-term economic survival. That is why NUKEM believes nuclear power will not grow much in the CIS and Eastern Europe beyond the projects already in the advanced stages of construction. What's more, the longer countries such as Italy, the Netherlands, Spain, Switzerland and Finland keep their nuclear expansion plans on hold, the harder it will be to get the political support to restart them. So far in 1992, only two nuclear plants, with a combined capacity of 1,520 MWe, have gone into commercial operation. One more 1,330 MWe reactor may start up by year's end. By then, NUKEM expects world nuclear plant capacity to stand at 330.3 GWe.

  10. Industry Support for Art Education.

    ERIC Educational Resources Information Center

    Putnam, Beverly

    1981-01-01

    A secondary art teacher describes how, when faced with district budget cuts, she developed links with local businesses willing to donate supplies, grants, and display spaces for her art program. (SJL)

  11. TARDEC Industrial Base Overview

    DTIC Science & Technology

    2010-11-30

    TARDEC Industrial Base Overview Randal Gaereminck, Associate Director, Industrial Base, Manufacturing, Logistics, & Value Engineering TARDEC...8-98) Prescribed by ANSI Std Z39-18 PURPOSE 2 To inform the conference attendees about TARDEC’s Industrial Base Mission and Capabilities AGENDA 3...Partnership • IBIT Policy Benefits • IBIT Mission • Industrial Base Engineering Support • Sustainment Engineering – Obsolescence • Industrial Base Engineering

  12. Signatures support program

    NASA Astrophysics Data System (ADS)

    Hawley, Chadwick T.

    2009-05-01

    The Signatures Support Program (SSP) leverages the full spectrum of signature-related activities (collections, processing, development, storage, maintenance, and dissemination) within the Department of Defense (DOD), the intelligence community (IC), other Federal agencies, and civil institutions. The Enterprise encompasses acoustic, seismic, radio frequency, infrared, radar, nuclear radiation, and electro-optical signatures. The SSP serves the war fighter, the IC, and civil institutions by supporting military operations, intelligence operations, homeland defense, disaster relief, acquisitions, and research and development. Data centers host and maintain signature holdings, collectively forming the national signatures pool. The geographically distributed organizations are the authoritative sources and repositories for signature data; the centers are responsible for data content and quality. The SSP proactively engages DOD, IC, other Federal entities, academia, and industry to locate signatures for inclusion in the distributed national signatures pool and provides world-wide 24/7 access via the SSP application.

  13. The role of research in nuclear regulation: A Korean perspective

    SciTech Connect

    Yoon, Won-Hyo

    1997-01-01

    Korea has carried out a very ambitious nuclear power program since the 1970`s as part of the nation`s industrialization policy. Ever since, Korea has also maintained a strong commitment to nuclear power development as an integral part of the national energy policy which aims at reducing external vulnerability and ensuring against a global fossil fuel shortage. The introduction of nuclear power into Korea has progressed through three stages: the first was a turn-key package supplied by the manufacturer; the second involved a major contractor who was responsible for project management, and design and construction was contracted out, with Korean industry becoming more involved; the third stage has seen Korean industries involved as main contractors based on experience gained from earlier plants. The success of Korea`s nuclear power program depends in large part on how to insure safety. Safety has the highest priority in nuclear energy development. Public acceptance has been the most critical problem faced by the nuclear industry in Korea. The public demands the highest level of safety all through the design, construction, and operation of nuclear power plants. Korea has learned that a nuclear plant designed with well addressed safety, implementation of a well grounded QA program during construction, and operated with a proven record of safety, are the only ways to earn public support. Competent and efficient regulation with a strong safety culture and openness in all issues is the most desirable image for regulators to strive for. Korea established a ten year R & D program to obtain self-reliance in nuclear technology and international competitiveness by the early 2000`s in 1992. It has actively participated in coordinated research programs in safety issues with bodies including the USNRC, AECB of Canada, IAEA, and OECD/NEA.

  14. Nuclear waste

    SciTech Connect

    Not Available

    1988-05-01

    This paper discusses how, as part of the Department of Energy's implementation of the Nuclear Waste Policy Act of 1982, DOE is required to investigate a site at Yucca Mountain, Nevada and, if it determines that the site is suitable, recommend to the President its selection for a nuclear waste repository. The Nuclear Regulatory Commission, in considering development of the plan, issued five objections, one of which is DOE's failure to recognize the range of alternative conceptual models of the Yucca Mountain site that can be supported by the limited existing technical data. At the end of the quarter DOE directed its project offices in Washington and Texas to begin orderly phase-out of all site-specific repository activities. Costs for this phase-out are $53 million for the Deaf Smith site and $85 million for the Hanford site.

  15. Nuclear material accounting software for Ukraine

    SciTech Connect

    Doll, M.; Ewing, T.; Lindley, R.; McWilliams, C.; Roche, C.; Sakunov, I.; Walters, G.

    1999-07-26

    Among the needs identified during initial surveys of nuclear facilities in Ukraine was improved accounting software for reporting material inventories to the regulatory body. AIMAS (Automated Inventory/Material Accounting System) is a PC-based application written in Microsoft Access that was jointly designed by an US/Ukraine development team. The design is highly flexible and configurable, and supports a wide range of computing infrastructure needs and facility requirements including situations where networks are not available or reliable. AIMAS has both English and Russian-language options for displays and reports, and it operates under Windows 3.1, 95, or NT 4.0{trademark}. AIMAS functions include basic physical inventory tracking, transaction histories, reporting, and system administration functions (system configuration, security, data backup and recovery). Security measures include multilevel password access control, all transactions logged with the user identification, and system administration control. Interfaces to external modules provide nuclear fuel burn-up adjustment and barcode scanning capabilities for physical inventory taking. AIMAS has been installed at Kiev Institute of Nuclear Research (KINR), South Ukraine Nuclear Power Plant (SUNPP), Kharkov Institute of Physics and Technology (KIPT), Sevastopol Institute of Nuclear Energy and Industry (SINEI), and the Ministry of Environmental Protection and Nuclear Safety/Nuclear Regulatory Administration (MEPNS/NRA). Facility specialists are being trained to use the application to track material movement and report to the national regulatory authority.

  16. Updating of ASME Nuclear Code Case N-201 to Accommodate the Needs of Metallic Core Support Structures for High Temperature Gas Cooled Reactors Currently in Development

    SciTech Connect

    Mit Basol; John F. Kielb; John F. MuHooly; Kobus Smit

    2007-05-02

    On September 29, 2005, ASME Standards Technology, LLC (ASME ST-LLC) executed a multi-year, cooperative agreement with the United States DOE for the Generation IV Reactor Materials project. The project's objective is to update and expand appropriate materials, construction, and design codes for application in future Generation IV nuclear reactor systems that operate at elevated temperatures. Task 4 was embarked upon in recognition of the large quantity of ongoing reactor designs utilizing high temperature technology. Since Code Case N-201 had not seen a significant revision (except for a minor revision in September, 2006 to change the SA-336 forging reference for 304SS and 316SS to SA-965 in Tables 1.2(a) and 1.2(b), and some minor editorial changes) since December 1994, identifying recommended updates to support the current high temperature Core Support Structure (CSS) designs and potential new designs was important. As anticipated, the Task 4 effort identified a number of Code Case N-201 issues. Items requiring further consideration range from addressing apparent inconsistencies in definitions and certain material properties between CC-N-201 and Subsection NH, to inclusion of additional materials to provide the designer more flexibility of design. Task 4 developed a design parameter survey that requested input from the CSS designers of ongoing high temperature gas cooled reactor metallic core support designs. The responses to the survey provided Task 4 valuable input to identify the design operating parameters and future needs of the CSS designers. Types of materials, metal temperature, time of exposure, design pressure, design life, and fluence levels were included in the Task 4 survey responses. The results of the survey are included in this report. This research proves that additional work must be done to update Code Case N-201. Task 4 activities provide the framework for the Code Case N-201 update and future work to provide input on materials. Candidate

  17. A randomised crossover simulation study comparing the impact of chemical, biological, radiological or nuclear substance personal protection equipment on the performance of advanced life support interventions.

    PubMed

    Schumacher, J; Arlidge, J; Garnham, F; Ahmad, I

    2017-03-02

    Recent incidents involving chemical, biological, radiological and nuclear substances have stressed the importance of sufficient personal protection equipment for medical first-responders. Modern lightweight, battery-independent, suit ensembles may prove superior to the current protective suit used in the UK. This study compared the powered respiratory protective suit (PRPS ensemble) with a lightweight suit consisting of a SARATOGA(®) Multipurpose CBRN Protective Coverall Polyprotect 12 in conjunction with the Avon C50 Respirator/Avon CBRNF12CE filter canister and butyl rubber protective gloves (Polyprotect 12 ensemble). Thirty anaesthetists carried out a standardised resuscitation scenario either unprotected (control) or wearing the PRPS or Polyprotect 12 ensembles in a randomised, crossover simulation study. Treatment times for five simulated advanced life support interventions (application of monitoring; bag/mask ventilation; tracheal intubation; drug and fluid administration; and external pacing) were measured. Wearer comfort was also assessed for the two protective suits by questionnaire. All participants accomplished the treatment objectives of all study arms without adverse events. Total mean (SD) completion time for the five interventions was significantly longer for the PRPS compared with the Polyprotect 12 ensemble (204 (53) s vs. 149 (36) s, respectively; p < 0.0001). Participants rated mobility, noise, heat, vision, dexterity and speech intelligibility significantly better in the Polyprotect 12 ensemble compared with the PRPS ensemble. The combination of a lightweight Polyprotect 12 suit and an Avon C50 air-purifying respirator is preferable to the powered respiratory protective suit during simulated emergency life support, due to a combination of shorter task completion times and improved mobility, communication and dexterity.

  18. Sensitive Electrochemical Immunosensor for Detection of Nuclear Matrix Protein-22 based on NH2-SAPO-34 Supported Pd/Co Nanoparticles.

    PubMed

    Wu, Dan; Wang, Yaoguang; Zhang, Yong; Ma, Hongmin; Yan, Tao; Du, Bin; Wei, Qin

    2016-04-18

    A novel sandwich-type electrochemical immunosensor using the new amino group functionalized silicoaluminophosphates molecular sieves (NH2-SAPO-34) supported Pd/Co nanoparticles (NH2-SAPO-34-Pd/Co NPs) as labels for the detection of bladder cancer biomarker nuclear matrix protein-22 (NMP-22) was developed in this work. The reduced graphene oxide-NH (rGO-NH) with good conductivity and large surface area was used to immobilize primary antibody (Ab1). Due to the excellent catalytic activity toward hydrogen peroxide, NH2-SAPO-34-Pd/Co NPs were used as labels and immobilized secondary antibody (Ab2) through adsorption capacity of Pd/Co NPs to protein. The immunosensor displayed a wide linear range (0.001-20 ng/mL) and low detection limit (0.33 pg/mL). Good reproducibility and stability have showed satisfying results in the analysis of clinical urine samples. This novel and ultrasensitive immunosensor may have the potential application in the detection of different tumor markers.

  19. Sensitive Electrochemical Immunosensor for Detection of Nuclear Matrix Protein-22 based on NH2-SAPO-34 Supported Pd/Co Nanoparticles

    PubMed Central

    Wu, Dan; Wang, Yaoguang; Zhang, Yong; Ma, Hongmin; Yan, Tao; Du, Bin; Wei, Qin

    2016-01-01

    A novel sandwich-type electrochemical immunosensor using the new amino group functionalized silicoaluminophosphates molecular sieves (NH2-SAPO-34) supported Pd/Co nanoparticles (NH2-SAPO-34-Pd/Co NPs) as labels for the detection of bladder cancer biomarker nuclear matrix protein-22 (NMP-22) was developed in this work. The reduced graphene oxide-NH (rGO-NH) with good conductivity and large surface area was used to immobilize primary antibody (Ab1). Due to the excellent catalytic activity toward hydrogen peroxide, NH2-SAPO-34-Pd/Co NPs were used as labels and immobilized secondary antibody (Ab2) through adsorption capacity of Pd/Co NPs to protein. The immunosensor displayed a wide linear range (0.001–20 ng/mL) and low detection limit (0.33 pg/mL). Good reproducibility and stability have showed satisfying results in the analysis of clinical urine samples. This novel and ultrasensitive immunosensor may have the potential application in the detection of different tumor markers. PMID:27086763

  20. Perception of risk and the future of nuclear power

    SciTech Connect

    Slovic, P.

    1993-04-01

    Public support for nuclear power has declined greatly, driven by a number of powerful forces and events. Numerous studies have demonstrated the public`s extreme perceptions of risk and negative attitudes regarding nuclear power. This negativity is remarkable in light of the confidence most technical analysts have regarding the safety of this technology. Public fears and opposition to nuclear power can be seen as a crisis in confidence, a profound breakdown in trust in the scientific, governmental, and industrial managers of nuclear technologies. The problem is not due to public ignorance or irrationality, but is deeply rooted in individual psychology and the adversarial nature of our social, institutional, legal, and political systems of risk management. In the absence of revolutionary changes in the ways that risks are managed in our society, it is unlikely that public trust, confidence, and acceptance of nuclear power can be regained.

  1. Contracting in the national interest: Establishing the legal framework for the interaction of science, government, and industry at a nuclear weapons laboratory

    SciTech Connect

    Furman, N.S.

    1988-04-01

    Sandia National Laboratories, the nation's nuclear ordnance laboratory, is operated on a no-profit, no-fee basis by ATandT Technologies, Inc., as a prime contractor for the Department of Energy. This unique arrangement began in 1949 when President Harry Truman personally requested that ATandT assume management of the nuclear weapons laboratory as a service in the national interest. The story of how this unusual relationship came about makes for an interesting chapter in the annals of US legal and institutional history. This report describes the historical background, political negotiations, and prime contract provisos that established the legal framework for the Labs.

  2. Artificial intelligence program in a computer application supporting reactor operations

    SciTech Connect

    Stratton, R.C.; Town, G.G.

    1985-01-01

    Improving nuclear reactor power plant operability is an ever-present concern for the nuclear industry. The definition of plant operability involves a complex interaction of the ideas of reliability, safety, and efficiency. This paper presents observations concerning the issues involved and the benefits derived from the implementation of a computer application which combines traditional computer applications with artificial intelligence (AI) methodologies. A system, the Component Configuration Control System (CCCS), is being installed to support nuclear reactor operations at the Experimental Breeder Reactor II.

  3. Report Card on Nuclear Power

    ERIC Educational Resources Information Center

    Novick, Sheldon

    1974-01-01

    Problems facing the nuclear power industry include skyrocketing construction costs, technical failures, fuel scarcity, power plant safety, and the disposal of nuclear wastes. Possible solutions include: reductions in nuclear power plant construction, a complete moratorium on new plant construction, the construction of fast breeder reactors and the…

  4. Smart way out nuclear energy: Prospects for the 21st century. Research report, August 1992-April 1993

    SciTech Connect

    DePerro, P.J.

    1993-04-01

    Nuclear energy can be a premier national industry with a promising future if our government and the public 'wake up now and smell the coffee.' There are a number of key issues requiring action to get commercial nuclear power 'back on track' (waste management, regulatory fixes, public support, safety, plant design standardization, executive leadership and government focus). Each of these issues can be resolved in favor of the industry, if only our nation has the will and common sense to take the 'smart way out.' This research paper discusses the following: Nuclear energy as seen hypothetically from the year 2020, The Stagnant Facts pertaining to commercial nuclear power - power plant construction, demand, safety, waste management, public support. The prospects for our future in Nuclear Energy.

  5. Shipbuilding Industry

    DTIC Science & Technology

    2006-01-01

    vessels, the industry cannot compete internationally due to higher costs and prices . On the commercial side, based on information provided during...challenges. The defense sector, though producing the most advanced ships in the world, does so at exorbitant prices , limiting the number that the U.S...Navy can afford. Based on visits to twenty-four U.S. and Australian shipyards, the U.S. government should provide targeted support to the commercial

  6. Uranium industry annual 1996

    SciTech Connect

    1997-04-01

    The Uranium Industry Annual 1996 (UIA 1996) provides current statistical data on the US uranium industry`s activities relating to uranium raw materials and uranium marketing. The UIA 1996 is prepared for use by the Congress, Federal and State agencies, the uranium and nuclear electric utility industries, and the public. Data on uranium raw materials activities for 1987 through 1996 including exploration activities and expenditures, EIA-estimated reserves, mine production of uranium, production of uranium concentrate, and industry employment are presented in Chapter 1. Data on uranium marketing activities for 1994 through 2006, including purchases of uranium and enrichment services, enrichment feed deliveries, uranium fuel assemblies, filled and unfilled market requirements, uranium imports and exports, and uranium inventories are shown in Chapter 2. A feature article, The Role of Thorium in Nuclear Energy, is included. 24 figs., 56 tabs.

  7. Report of the Joint Industry - DoD Task Force on Computer Aided Logistic Support (CALS). Volume 5. Report of Technical Issues Subgroup.

    DTIC Science & Technology

    1985-06-01

    or for the mechanical interfaces on machine tools and industrial robots. One example concerns robot and effectors. Mounting surfaces and bolt hold...in the ANSI Standard for tool holderg on NC machining centers. Much of the new automation equipment being installed owes its success to embedded...of interfaces with the electronic controllers for numerical control of industrial machine tools and for industrial robots. 7 Areas of Worla

  8. Joint Industry/University Cooperation with Federally Supported Research Facilities. Hearing before the Subcommittee on Investigations and Oversight of the Committee on Science and Technology. U.S. House of Representatives, Ninety-Eighth Congress, First Session.

    ERIC Educational Resources Information Center

    Congress of the U.S., Washington, DC. House Committee on Science and Technology.

    These hearings focused on issues related to the joint use of federally-funded research facilities by industry and universities. Testimony of witnesses, prepared statements, and supporting documentation (including the Stevenson-Wydler Technology Innovation Act of 1980, Public Law 96-480) are provided. Witnesses presenting testimony included: Louis…

  9. Training related research and development conducted at Oak Ridge National Laboratory for the US Nuclear Regulatory Commission

    SciTech Connect

    Haas, P.M.

    1985-01-01

    For a number of years Oak Ridge National Laboratory (ORNL) has conducted a sizeable program of human factors research and development in support of the Office of Nuclear Regulatory Research of the US Nuclear Regulatory Commission (NRC). The history of this effort has in many ways paralleled the growth of human factors R and D throughout the nuclear industry and the program has contributed to advances in the industry as well as to NRC regulatory and research programs. This paper reviews the major projects and products of the program relevant to training and concludes with an identification of future R and D needs.

  10. Economic Conditions and Factors Affecting New Nuclear Power Deployment

    SciTech Connect

    Harrison, Thomas J.

    2014-10-01

    This report documents work performed in support of the US Department of Energy Office of Nuclear Energy’s Advanced Small Modular Reactor (AdvSMR) program. The report presents information and results from economic analyses to describe current electricity market conditions and those key factors that may impact the deployment of AdvSMRs or any other new nuclear power plants. Thus, this report serves as a reference document for DOE as it moves forward with its plans to develop advanced reactors, including AdvSMRs. For the purpose of this analysis, information on electricity markets and nuclear power plant operating costs will be combined to examine the current state of the nuclear industry and the process required to successfully move forward with new nuclear power in general and AdvSMRs in particular. The current electricity market is generally unfavorable to new nuclear construction, especially in deregulated markets with heavy competition from natural gas and subsidized renewables. The successful and profitable operation of a nuclear power plant (or any power plant) requires the rate at which the electricity is sold to be sufficiently greater than the cost to operate. The wholesale rates in most US markets have settled into values that provide profits for most operating nuclear power plants but are too low to support the added cost of capital recovery for new nuclear construction. There is a strong geographic dependence on the wholesale rate, with some markets currently able to support new nuclear construction. However, there is also a strong geographic dependence on pronuclear public opinion; the areas where power prices are high tend to have unfavorable views on the construction of new nuclear power plants. The use of government-backed incentives, such as subsidies, can help provide a margin to help justify construction projects that otherwise may not seem viable. Similarly, low interest rates for the project will also add a positive margin to the economic

  11. Cells, Agents, and Support Vectors in Interaction - Modeling Urban Sprawl based on Machine Learning and Artificial Intelligence Techniques in a Post-Industrial Region

    NASA Astrophysics Data System (ADS)

    Rienow, A.; Menz, G.

    2015-12-01

    Since the beginning of the millennium, artificial intelligence techniques as cellular automata (CA) and multi-agent systems (MAS) have been incorporated into land-system simulations to address the complex challenges of transitions in urban areas as open, dynamic systems. The study presents a hybrid modeling approach for modeling the two antagonistic processes of urban sprawl and urban decline at once. The simulation power of support vector machines (SVM), cellular automata (CA) and multi-agent systems (MAS) are integrated into one modeling framework and applied to the largest agglomeration of Central Europe: the Ruhr. A modified version of SLEUTH (short for Slope, Land-use, Exclusion, Urban, Transport, and Hillshade) functions as the CA component. SLEUTH makes use of historic urban land-use data sets and growth coefficients for the purpose of modeling physical urban expansion. The machine learning algorithm of SVM is applied in order to enhance SLEUTH. Thus, the stochastic variability of the CA is reduced and information about the human and ecological forces driving the local suitability of urban sprawl is incorporated. Subsequently, the supported CA is coupled with the MAS ReHoSh (Residential Mobility and the Housing Market of Shrinking City Systems). The MAS models population patterns, housing prices, and housing demand in shrinking regions based on interactions between household and city agents. Semi-explicit urban weights are introduced as a possibility of modeling from and to the pixel simultaneously. Three scenarios of changing housing preferences reveal the urban development of the region in terms of quantity and location. They reflect the dissemination of sustainable thinking among stakeholders versus the steady dream of owning a house in sub- and exurban areas. Additionally, the outcomes are transferred into a digital petri dish reflecting a synthetic environment with perfect conditions of growth. Hence, the generic growth elements affecting the future

  12. Fifty years with nuclear fission. Volume 1

    SciTech Connect

    Behrens, J.W.; Carlson, A.D.

    1989-12-31

    The news of the discovery of nuclear fission, by Otto Hahn and Fritz Strassmann in Germany, was brought to the United States by Niels Bohr in January 1939. Since its discovery, the United States, and the world for that matter, has never been the same. It therefore seemed appropriate to acknowledge the fifieth anniversary of its discovery by holding a topical meeting entitled, ``Fifty Years with Nuclear Fission,`` in the United States during the year 1989. The objective of the meeting was to bring together pioneers of the nuclear industry and other scientists and engineers to report on reminiscences of the past and on the more recent development in fission science and technology. The conference highlighted the early pioneers of the nuclear industry by dedicated a full day (April 26), consisting of two plenary sessions, at the National Academy of Sciences (NAS) in Washington, DC. More recent developments in fission science and technology in addition to historical reflections were topics for two fully days of sessions (April 27 and 28) at the main site of the NIST in Gaithersburg, Maryland. The wide range of topics covered in this Volume 1 by this topical meeting included plenary invited, and contributed sessions entitled: Preclude to the First Chain Reaction -- 1932 to 1942; Early Fission Research -- Nuclear Structure and Spontaneous Fission; 50 Years of Fission, Science, and Technology; Nuclear Reactors, Secure Energy for the Future; Reactors 1; Fission Science 1; Safeguards and Space Applications; Fission Data; Nuclear Fission -- Its Various Aspects; Theory and Experiments in Support of Theory; Reactors and Safeguards; and General Research, Instrumentation, and By-Product. The individual papers have been cataloged separately.

  13. Sister Lab Program Prospective Partner Nuclear Profile: Malaysia

    SciTech Connect

    Bissani, M; Tyson, S

    2006-12-14

    The Malaysian Deputy Prime Minister Tun Dr Ismail Abdul Rahman suggested in the early 1970s that Malaysia should have a role in the development of nuclear science and technology for peaceful purposes. Accordingly, the Center for the Application of Nuclear Energy (CRANE) was established, with a focus on the development of a scientific and technical pool critical to a national nuclear power program. The Malaysian Cabinet next established the Tun Ismail Atomic Research Center (TIARC) under the Ministry of Science, Technology and the Environment on 19 September 1972, at a site in Bangi, about 35 km south of Kuala Lampur. On 28 June 1982, the PUSPATI reactor, a 1-MW TRIGA MK-II research reactor, first reached criticality. On 10 August 1994, TIARC was officially renamed as the Malaysian Institute for Nuclear Technology Research (MINT). In addition to radioisotope production and neutron radiography conducted at the PUSPATI research reactor, MINT also supports numerous programs employing nuclear technology for medicine, agriculture and industry, and has been involved in both bilateral and multilateral technical cooperation to extend its capabilities. As an energy exporting country, Malaysia has felt little incentive to develop a nuclear energy program, and high level opposition within the government discouraged it further. A recent statement by Malaysia's Science, Technology and Innovation Minister supported this view, indicating that only a near-catastrophic jump in world oil prices might change the government's view. However, the rate at which Malaysia is using its natural gas and oil reserves is expected to force it to reassess the role of nuclear energy in the near future. In addition, the government does intend to construct a radioactive waste repository to dispose of naturally occurring radioactive materials (extracted during tin mining, in particular). Also, Malaysia's growing economy could encourage expansion in Malaysia's existing nuclear-applications programs

  14. Analysis of the Mortality Experience amongst U.S. Nuclear Power Industry Workers after Chronic Low-Dose Exposure to Ionizing Radiation

    SciTech Connect

    Howe, Geoffrey R.; Zablotska, Lydia B.; Fix, Jack J.; Egel, John N.; Buchanan, Jeffrey A.

    2004-11-01

    Workers employed in 15 utilities that generate nuclear power in the United States have been followed for up to 18 years between 1979 and 1997. Their cumulative dose from whole-body ionizing radiation has been determined from the dose records maintained by the facilities themselves and the REIRS and REMS systems maintained by the Nuclear Regulatory Commission and the Department of Energy, respectively. Mortality in the cohort from a number of causes has been analyzed with respect to individual radiation doses. The cohort displays a very substantial healthy worker effect, i.e. considerably lower cancer and noncancer mortality than the general population. Based on 26 and 368 deaths, respectively, positive though statistically nonsignificant associations were seen for mortality from leukemia (excluding chronic lymphocytic leukemia) and all solid cancers combined, with excess relative risks per sievert of 5.67 (95% confidence interval (CI) -2.56, 30.4) and 0.596 (95% CI -2.01, 4.64), respectively. These estimates are very similar to those from the atomic bomb survivors study, though the wide confidence intervals are also consistent with lower or higher risk estimates. A strong positive and statistically significant association between radiation dose and deaths from arteriosclerotic heart disease including coronary heart disease was also observed in the cohort, with an ERR of 8.78 (95% CI 2.10, 20.0). While associations with heart disease have been reported in some other occupational studies, the magnitude of the present association is not consistent with them and therefore needs cautious interpretation and merits further attention. At present, the relatively small number of deaths and the young age of the cohort (mean age at end of follow-up is 45 years) limit the power of the study, but further follow-up and the inclusion of the present data in an ongoing IARC combined analysis of nuclear workers from 15 countries will have greater power for testing the main hypotheses

  15. PREFACE: EPS Euroconference XIX Nuclear Physics Divisional Conference: New Trends in Nuclear Physics Applications and Technology

    NASA Astrophysics Data System (ADS)

    2006-06-01

    . Role of Nuclear Techniques in Environment Problems. Applications of Nuclear Techniques relevant for Civil Security (contraband and explosive detection, search for Weapons of Mass Destruction, Nuclear Safeguards). Nuclear Applications in Space Research. Material and Structure Testing in Research and Industry. New contributions of Nuclear Techniques to the solution of the Energy Production problems and Nuclear Waste Transmutation. Emerging experimental techniques, new detectors and new modeling tools. During the Monday morning Session of the Conference, the 2005 IBA-EUROPHYSICS PRIZE for Applied Nuclear Science and Nuclear Methods in Medicine, sponsored by the Belgian company IBA, was awarded to the two laureates Werner Heil (Mainz) and Pierre Jean Nacher (Paris) for the development of spin polarized 3He targets by optical pumping and their applications in nuclear science and medicine. The meeting was a real success, with 18 invited talks, 66 contributed talks and 31 posters and an overall participation, during five full days, of around 150 scientists from different European and non-European countries. It also hosted a three day industrial exhibition of a selection of Companies that sponsored the event. The Organisers take thos opportunity to thank the University of Pavia, the Amministrazione Comunale di Pavia and the Provincia di Pavia, as well as all exhibitors (Ametek, Ansaldo Superconduttori, Caen, Else, Hamamatsu, IBA, Micos, Micron Semiconductor), for their support of the Conference. The Organisers finally wish to thank the Scientific Secretary of the Conference, Dr Andrea Fontana of INFN Pavia, for the huge amount of work done in preparing the Conference, Mr Claudio Casella of the Department of Nuclear and Theoretical Physics of the University of Pavia for technical support and the Conference staff, Dr Gaia Boghen and the graduate students Federica Devecchi and Silvia Franchino, for their invaluable help. The very effective and professional work of the staff of

  16. Long-Term Support for High-Volume Manufacturing Industry: The Centre for Achievement in Manufacturing and Management, University of Sunderland, UK.

    ERIC Educational Resources Information Center

    Wilcock, Dennis; Terry, Brian

    1996-01-01

    A unique partnership of industry, government, and the University of Sunderland involves a holistic approach to manufacturing, integrating efficiency with quality of life for a profitable and sustainable competitive advantage. (SK)

  17. ADVANCED CERAMIC MATERIALS FOR NEXT-GENERATION NUCLEAR APPLICATIONS

    SciTech Connect

    Marra, J.

    2010-09-29

    Rising global energy demands coupled with increased environmental concerns point to one solution; they must reduce their dependence on fossil fuels that emit greenhouse gases. As the global community faces the challenge of maintaining sovereign nation security, reducing greenhouse gases, and addressing climate change nuclear power will play a significant and likely growing role. In the US, nuclear energy already provides approximately one-fifth of the electricity used to power factories, offices, homes, and schools with 104 operating nuclear power plants, located at 65 sites in 31 states. Additionally, 19 utilities have applied to the US Nuclear Regulatory Commission (NRC) for construction and operating licenses for 26 new reactors at 17 sites. This planned growth of nuclear power is occurring worldwide and has been termed the 'nuclear renaissance.' As major industrial nations craft their energy future, there are several important factors that must be considered about nuclear energy: (1) it has been proven over the last 40 years to be safe, reliable and affordable (good for Economic Security); (2) its technology and fuel can be domestically produced or obtained from allied nations (good for Energy Security); and (3) it is nearly free of greenhouse gas emissions (good for Environmental Security). Already an important part of worldwide energy security via electricity generation, nuclear energy can also potentially play an important role in industrial processes and supporting the nation's transportation sector. Coal-to-liquid processes, the generation of hydrogen and supporting the growing potential for a greatly increased electric transportation system (i.e. cars and trains) mean that nuclear energy could see dramatic growth in the near future as we seek to meet our growing demand for energy in cleaner, more secure ways. In order to address some of the prominent issues associated with nuclear power generation (i.e., high capital costs, waste management, and

  18. Historical civilian nuclear accident based Nuclear Reactor Condition Analyzer

    NASA Astrophysics Data System (ADS)

    McCoy, Kaylyn Marie

    There are significant challenges to successfully monitoring multiple processes within a nuclear reactor facility. The evidence for this observation can be seen in the historical civilian nuclear incidents that have occurred with similar initiating conditions and sequences of events. Because there is a current lack within the nuclear industry, with regards to the monitoring of internal sensors across multiple processes for patterns of failure, this study has developed a program that is directed at accomplishing that charge through an innovation that monitors these systems simultaneously. The inclusion of digital sensor technology within the nuclear industry has appreciably increased computer systems' capabilities to manipulate sensor signals, thus making the satisfaction of these monitoring challenges possible. One such manipulation to signal data has been explored in this study. The Nuclear Reactor Condition Analyzer (NRCA) program that has been developed for this research, with the assistance of the Nuclear Regulatory Commission's Graduate Fellowship, utilizes one-norm distance and kernel weighting equations to normalize all nuclear reactor parameters under the program's analysis. This normalization allows the program to set more consistent parameter value thresholds for a more simplified approach to analyzing the condition of the nuclear reactor under its scrutiny. The product of this research provides a means for the nuclear industry to implement a safety and monitoring program that can oversee the system parameters of a nuclear power reactor facility, like that of a nuclear power plant.

  19. Thermodynamics of nuclear transport

    NASA Astrophysics Data System (ADS)

    Wang, Ching-Hao; Mehta, Pankaj; Elbaum, Michael

    Molecular transport across the nuclear envelope is important for eukaryotes for gene expression and signaling. Experimental studies have revealed that nuclear transport is inherently a nonequilibrium process and actively consumes energy. In this work we present a thermodynamics theory of nuclear transport for a major class of nuclear transporters that are mediated by the small GTPase Ran. We identify the molecular elements responsible for powering nuclear transport, which we term the ``Ran battery'' and find that the efficiency of transport, measured by the cargo nuclear localization ratio, is limited by competition between cargo molecules and RanGTP to bind transport receptors, as well as the amount of NTF2 (i.e. RanGDP carrier) available to circulate the energy flow. This picture complements our current understanding of nuclear transport by providing a comprehensive thermodynamics framework to decipher the underlying biochemical machinery. Pm and CHW were supported by a Simons Investigator in the Mathematical Modeling in Living Systems grant (to PM).

  20. Russia's nuclear elite on rampage

    SciTech Connect

    Popova, L.

    1993-04-01

    In July 1992, the Russian Ministry of Nuclear Industry began pressing the Russian government to adopt a plan to build new nuclear power plants. In mid-January 1993 the government announced that it will build at least 30 new nuclear power plants, and that the second stage of the building program will include construction of three fast-breeder reactors. In this article, the author addresses the rationale behind this massive building program, despite the country's economic condition and public dread of another Chernobyl-type accident. The viewpoints of both the Russian Ministry of Nuclear Industry and opposing interests are discussed.

  1. Nuclear Energy Research Initiative. Risk Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants. Annual Report

    SciTech Connect

    Ritterbusch, S.E.

    2000-08-01

    The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-informed approach for the design and regulation of nuclear power plants. This approach will include the development and.lor confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRs) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go farther by focusing on the design of new plants.

  2. Uranium industry annual 1994

    SciTech Connect

    1995-07-05

    The Uranium Industry Annual 1994 (UIA 1994) provides current statistical data on the US uranium industry`s activities relating to uranium raw materials and uranium marketing during that survey year. The UIA 1994 is prepared for use by the Congress, Federal and State agencies, the uranium and nuclear electric utility industries, and the public. It contains data for the 10-year period 1985 through 1994 as collected on the Form EIA-858, ``Uranium Industry Annual Survey.`` Data collected on the ``Uranium Industry Annual Survey`` (UIAS) provide a comprehensive statistical characterization of the industry`s activities for the survey year and also include some information about industry`s plans and commitments for the near-term future. Where aggregate data are presented in the UIA 1994, care has been taken to protect the confidentiality of company-specific information while still conveying accurate and complete statistical data. A feature article, ``Comparison of Uranium Mill Tailings Reclamation in the United States and Canada,`` is included in the UIA 1994. Data on uranium raw materials activities including exploration activities and expenditures, EIA-estimated resources and reserves, mine production of uranium, production of uranium concentrate, and industry employment are presented in Chapter 1. Data on uranium marketing activities, including purchases of uranium and enrichment services, and uranium inventories, enrichment feed deliveries (actual and projected), and unfilled market requirements are shown in Chapter 2.

  3. The Nuclear Renaissance in the U.S.

    ScienceCinema

    Jacopo Buongiorno

    2016-07-12

    Nuclear power currently provides 20% of the electricity generation in the U.S. and about 16% worldwide.  As a carbon-free energy source, nuclear is receiving a lot of attention by industry, lawmakers and environmental groups, as they attempt to resolve the issue of man-made climate change.  For the first time in 30 years several U.S. electric utilities have applied for construction and operation licenses of new nuclear power plants.  This talk will review the safety, operational and economic record of the existing U.S. commercial reactor fleet, will provide an overview of the reactor designs considered for the new wave of plant construction, and will discuss several research projects being conducted at the Massachusetts Institute of Technology to support the expansion of nuclear power in the U.S. and overseas.

  4. The Nuclear Renaissance in the U.S.

    SciTech Connect

    Jacopo Buongiorno

    2008-07-30

    Nuclear power currently provides 20% of the electricity generation in the U.S. and about 16% worldwide.  As a carbon-free energy source, nuclear is receiving a lot of attention by industry, lawmakers and environmental groups, as they attempt to resolve the issue of man-made climate change.  For the first time in 30 years several U.S. electric utilities have applied for construction and operation licenses of new nuclear power plants.  This talk will review the safety, operational and economic record of the existing U.S. commercial reactor fleet, will provide an overview of the reactor designs considered for the new wave of plant construction, and will discuss several research projects being conducted at the Massachusetts Institute of Technology to support the expansion of nuclear power in the U.S. and overseas.

  5. Nuclear rights - nuclear wrongs

    SciTech Connect

    Paul, E.F.; Miller, F.D.; Paul, J.; Ahrens, J.

    1986-01-01

    This book contains 11 selections. The titles are: Three Ways to Kill Innocent Bystanders: Some Conundrums Concerning the Morality of War; The International Defense of Liberty; Two Concepts of Deterrence; Nuclear Deterrence and Arms Control; Ethical Issues for the 1980s; The Moral Status of Nuclear Deterrent Threats; Optimal Deterrence; Morality and Paradoxical Deterrence; Immoral Risks: A Deontological Critique of Nuclear Deterrence; No War Without Dictatorship, No Peace Without Democracy: Foreign Policy as Domestic Politics; Marxism-Leninism and its Strategic Implications for the United States; Tocqueveille War.

  6. Nonconventional applications of nuclear technology to space

    SciTech Connect

    Woodall, D.M.; Dolan, T.J. )

    1991-01-01

    The application of nuclear energy to power and propulsion to support President Bush's Space Exploration Initiative (SEI) has received considerable technical attention. This paper discusses the application of other nuclear technologies in space, including nuclear fusion, advanced accelerator research, antimatter research, nuclear technologies for exploration and mining, and nuclear astronomy.

  7. U.S. Job Creation Due to Nuclear Power Resurgence in The United States — Volumes 1 and 2

    SciTech Connect

    Catherine M. Plowman

    2004-11-01

    The recent revival of interest in nuclear power is causing a reexamination of the role of nuclear power in the United States. This renewed interest has led to questions regarding the capability and capacity of current U.S. industries to support a renewal of nuclear power plant deployment. This study was conducted to provide an initial estimate of jobs to be gained in the U.S. through the repatriation of the nuclear manufacturing industry. In the course of the study, related job categories were also modeled to provide an additional estimate of the potential expansion of existing industries (i.e., plant construction and operations) in conjunction with the repatriation of manufacturing jobs.

  8. 2015 Summary Report on Industrial and Regulatory Engagement Activities

    SciTech Connect

    Thomas, Kenneth David

    2015-09-01

    The Advanced Instrumentation, Information, and Control (II&C) Systems Technologies pathway of the Light Water Reactor Sustainability(LWRS) Program conducts a vigorous engagement strategy with the U.S. nuclear power industry, including the nuclear operating companies, major support organizations, the Nuclear Regulatory Commission (NRC), and suppliers. The goal of this engagement strategy is to develop a shared vision and common understanding across the nuclear industry of the need for II&C modernization, the performance improvement that can be obtained, and the opportunities for collaboration to enact this vision. The primary means of engaging the nuclear operating companies is through a Utility Working Group (UWG), composed of utility representatives that participate in formal meetings and bi-monthly phone calls to provide input on nuclear plant needs and priorities for II&C technologies. Two working groups were initiated during FY 2015 to provide a means for UWG members to focus on particular technologies of interest. The Outage Improvement Working Group consists of eight utilities that participate in periodic conference calls and have access to a share-point web page for acccess to project materials developed in the Advanced Outage Control Center pilot project. In the area of computer-based procedures and automated work packages, the II&C Pathway has worked with the Nuclear Information Technology Strategic Leadership (NITSL) to set up a monthly conference call with interested utility members to discuss various aspects of mobile worker technologies. Twenty one technical and project reports were delivered to the UWG during FY 2015, reflecting the work of the II&C Pathway pilot projects during the year. Distribution of these reports is one of the primary means of transferring to the nuclear industry the knowledge and experience gained during the development of advanced II&C technologies in support of LWR sustainability. Site visits to discuss pilot project

  9. NIMBY, CLAMP, and the location of new nuclear-related facilities: U.S. national and 11 site-specific surveys.

    PubMed

    Greenberg, Michael R

    2009-09-01

    Public and political opposition have made finding locations for new nuclear power plants, waste management, and nuclear research and development facilities a challenge for the U.S. government and the nuclear industry. U.S. government-owned properties that already have nuclear-related activities and commercial nuclear power generating stations are logical locations. Several studies and utility applications to the Nuclear Regulatory Commission suggest that concentrating locations at major plants (CLAMP) has become an implicit siting policy. We surveyed 2,101 people who lived within 50 miles of 11 existing major nuclear sites and 600 who lived elsewhere in the United States. Thirty-four percent favored CLAMP for new nuclear power plants, 52% for waste management facilities, and 50% for new nuclear laboratories. College educated, relatively affluent male whites were the strongest CLAMP supporters. They disproportionately trusted those responsible for the facilities and were not worried about existing nuclear facilities or other local environmental issues. Notably, they were concerned about continuing coal use. Not surprisingly, CLAMP proponents tended to be familiar with their existing local nuclear site. In short, likely CLAMP sites have a large and politically powerful core group to support a CLAMP policy. The challenge to proponents of nuclear technologies will be to sustain this support and expand the base among those who clearly are less connected and receptive to new nearby sites.

  10. Nuclear Fuels & Materials Spotlight Volume 4

    SciTech Connect

    I. J. van Rooyen,; T. M. Lillo; Y. Q. WU; P.A. Demkowicz; L. Scott; D.M. Scates; E. L. Reber; J. H. Jackson; J. A. Smith; D.L. Cottle; B.H. Rabin; M.R. Tonks; S.B. Biner; Y. Zhang; R.L. Williamson; S.R. Novascone; B.W. Spencer; J.D. Hales; D.R. Gaston; C.J. Permann; D. Anders; S.L. Hayes; P.C. Millett; D. Andersson; C. Stanek; R. Ali; S.L. Garrett; J.E. Daw; J.L. Rempe; J. Palmer; B. Tittmann; B. Reinhardt; G. Kohse; P. Ramuhali; H.T. Chien; T. Unruh; B.M. Chase; D.W. Nigg; G. Imel; J. T. Harris

    2014-04-01

    As the nation's nuclear energy laboratory, Idaho National Laboratory brings together talented people and specialized nuclear research capability to accomplish our mission. This edition of the Nuclear Fuels and Materials Division Spotlight provides an overview of some of our recent accomplishments in research and capability development. These accomplishments include: • The first identification of silver and palladium migrating through the SiC layer in TRISO fuel • A description of irradiation assisted stress corrosion testing capabilities that support commercial light water reactor life extension • Results of high-temperature safety testing on coated particle fuels irradiated in the ATR • New methods for testing the integrity of irradiated plate-type reactor fuel • Description of a 'Smart Fuel' concept that wirelessly provides real time information about changes in nuclear fuel properties and operating conditions • Development and testing of ultrasonic transducers and real-time flux sensors for use inside reactor cores, and • An example of a capsule irradiation test. Throughout Spotlight, you'll find examples of productive partnerships with academia, industry, and government agencies that deliver high-impact outcomes. The work conducted at Idaho National Laboratory helps to spur innovation in nuclear energy applications that drive economic growth and energy security. We appreciate your interest in our work here at INL, and hope that you find this issue informative.

  11. Robotics and nuclear power. Report by the Technology Transfer Robotics Task Team

    SciTech Connect

    Not Available

    1985-06-01

    A task team was formed at the request of the Department of Energy to evaluate and assess technology development needed for advanced robotics in the nuclear industry. The mission of these technologies is to provide the nuclear industry with the support for the application of advanced robotics to reduce nuclear power generating costs and enhance the safety of the personnel in the industry. The investigation included robotic and teleoperated systems. A robotic system is defined as a reprogrammable, multifunctional manipulator designed to move materials, parts, tools, or specialized devices through variable programmed motions for the performance of a variety of tasks. A teleoperated system includes an operator who remotely controls the system by direct viewing or through a vision system.

  12. Environmental assessment for DOE permission for off-loading activities to support the movement of commercial low level nuclear waste across the Savannah River Site

    SciTech Connect

    1995-02-01

    This environmental assessment investigates the potential environmental and safety effects which could result from the land transport of low level radioactive wastes across the Savannah River Plant. Chem-Nuclear Systems operates a low level radioactive waste burial facility adjacent to the Savannah River Plant and is seeking permission from the DOE to transport the waste across Savannah River Plant.

  13. Industrial Radiography Manual.

    ERIC Educational Resources Information Center

    Richardson, Harry D.

    This text was developed for use by students in an 80-hour course for industrial radiographers. Chapter headings are: (1) The Structure of Matter, (2) Radiation and Radiation Machines, (3) Nuclear Reactions and Radioisotopes, (4) Interaction of Radiation with Matter, (5) Radiation Detection and Measurement, (6) The Nature and Consequences of…

  14. Industrial Radiography Instructor's Guide.

    ERIC Educational Resources Information Center

    Richardson, Harry D.

    The curriculum guide was developed for teacher use in an 80-hour course for industrial radiographers. The units include: (1) The Structure of Matter and Radiation, (2) Nuclear Reactions and Radioisotopes, (3) The Nature and Consequences of Radiation Exposure, (4) Radiation Attenuation, (5) Absorption of Radiation, (6) Radiation Detection and…

  15. Nuclear reactor apparatus

    DOEpatents

    Wade, Elman E.

    1978-01-01

    A lifting, rotating and sealing apparatus for nuclear reactors utilizing rotating plugs above the nuclear reactor core. This apparatus permits rotation of the plugs to provide under the plug refueling of a nuclear core. It also provides a means by which positive top core holddown can be utilized. Both of these operations are accomplished by means of the apparatus lifting the top core holddown structure off the nuclear core while stationary, and maintaining this structure in its elevated position during plug rotation. During both of these operations, the interface between the rotating member and its supporting member is sealingly maintained.

  16. Comprehensive Nuclear Materials

    SciTech Connect

    Konings, Dr. Rudy J. M.; Allen, Todd R.; Stoller, Roger E; Yamanaka, Prof. Shinsuke

    2012-01-01

    This book encompasses a rich seam of current information on the vast and multidisciplinary field of nuclear materials employed in fission and prototype fusion systems. Discussion includes both historical and contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds leading scientists and engineers. Synthesizes pertinent current science to support the selection, assessment, validation and engineering of materials in extreme nuclear environments. The work discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials.

  17. Incomplete data on the Canadian cohort may have affected the results of the study by the International Agency for Research on Cancer on the radiogenic cancer risk among nuclear industry workers in 15 countries.

    PubMed

    Ashmore, J Patrick; Gentner, Norman E; Osborne, Richard V

    2010-06-01

    In 1995 the International Agency for Research on Cancer (IARC) completed a study that involved nuclear workers from facilities in the USA, UK and Canada. The only significant, though weak, dose-related associations found were for leukaemia and multiple myeloma. The results for the Canadian cohort, which comprised workers from the facilities of Atomic Energy of Canada Limited (AECL), were compatible with those for the other national cohorts. In 2005, IARC completed a further study, involving nuclear workers from 15 countries, including Canada. In these results, the dose-related risk for leukaemia was not significant but the prominent finding was a statistically significant excess relative risk per sievert (ERR Sv(-1)) for 'all cancers excluding leukaemia'. Surprisingly, the risk ascribed to the Canadian cohort for all cancers excluding leukaemia, driven by the AECL sub-cohort, was significantly higher than the risk estimate for the 15-country cohort as a whole. We have attempted to identify why the results for the AECL cohort were so discrepant and had such a remarkable influence on the 15-country risk estimate. When considering the issues associated with data on the AECL cohorts and their handling, we noted a striking feature: a major change in outcome of studies that involved Canadian nuclear workers occurred concomitantly with the shift to when data from the National Dose Registry (NDR) of Canada were used directly rather than data from records at AECL. We concluded that an important contributor to the considerable upward shift in apparent risk in the 15-country and other Canadian studies that have been based on the NDR probably relates to pre-1971 data and, in particular, the absence from the NDR of the person-years of workers who had zero doses in the calendar years 1956 to 1970. Our recommendation was for there to be a comprehensive evaluation of the risks from radiation in nuclear industry workers in Canada, organisation by organisation, in which some of the

  18. Industrial diamond

    USGS Publications Warehouse

    Olson, D.W.

    2001-01-01

    An overview of the industrial diamond industry is provided. More than 90 percent of the industrial diamond consumed in the U.S. and the rest of the world is manufactured diamond. Ireland, Japan, Russia, and the U.S. produce 75 percent of the global industrial diamond output. In 2000, the U.S. was the largest market for industrial diamond. Industrial diamond applications, prices for industrial diamonds, imports and exports of industrial diamonds, the National Defense Stockpile of industrial diamonds, and the outlook for the industrial diamond market are discussed.

  19. Forecast of criticality experiments and experimental programs needed to support nuclear operations in the United States of America: 1994--1999

    SciTech Connect

    Rutherford, D.

    1994-03-01

    This Forecast is generated by the Chair of the Experiment Needs Identification Workgroup (ENIWG), with input from Department of Energy and the nuclear community. One of the current concerns addressed by ENIWG was the Defense Nuclear Facilities Safety Board`s Recommendation 93-2. This Recommendation delineated the need for a critical experimental capability, which includes (1) a program of general-purpose experiments, (2) improving the information base, and (3) ongoing departmental programs. The nuclear community also recognizes the importance of criticality theory, which, as a stepping stone to computational analysis and safety code development, needs to be benchmarked against well-characterized critical experiments. A summary project of the Department`s needs with respect to criticality information includes (1) hands-on training, (2) criticality and nuclear data, (3) detector systems, (4) uranium- and plutonium-based reactors, and (5) accident analysis. The Workgroup has evaluated, prioritized, and categorized each proposed experiment and program. Transportation/Applications is a new category intended to cover the areas of storage, training, emergency response, and standards. This category has the highest number of priority-1 experiments (nine). Facilities capable of performing experiments include the Los Alamos Critical Experiment Facility (LACEF) along with Area V at Sandia National Laboratory. The LACEF continues to house the most significant collection of critical assemblies in the Western Hemisphere. The staff of this facility and Area V are trained and certified, and documentation is current. ENIWG will continue to work with the nuclear community to identify and prioritize experiments because there is an overwhelming need for critical experiments to be performed for basic research and code validation.

  20. Education and Training Policies and Programmes To Support Industrial Restructuring in the Republic of Korea, Japan, Singapore and the United States. Training Discussion Paper No. 18.

    ERIC Educational Resources Information Center

    Hilowitz, Janet

    This literature survey analyzes the process of industrial restructuring as it is occurring in the Republic of Korea, Japan, Singapore, and the United States. It looks in particular at how various agents of education and training in these countries--the school system, public and private education and training institutions and firms--are responding…

  1. Manufacturing Technology Support (MATES). Task Order 0021: Air Force Technology and Industrial Base Research and Analysis, Subtask Order 06: Direct Digital Manufacturing

    DTIC Science & Technology

    2011-08-01

    inspection and scanning the part for internal defects. Through the online survey MLPC asked participants to provided feedback on the diagnostic tools...industry, which included additive, subtractive, and hybrid manufacturing. The review also included reverse engineering, part information data...most promise on direct part fabrication but also requires additional development in materials qualification, machine to machine consistency, inline

  2. An Update on NiCE Support for BISON

    SciTech Connect

    McCaskey, Alex; Billings, Jay Jay; Deyton, Jordan H.; Wojtowicz, Anna

    2015-09-01

    The Nuclear Energy Advanced Modeling and Simulation program (NEAMS) from the Department of Energy s Office of Nuclear Energy has funded the development of a modeling and simulation workflow environment to support the various codes in its nuclear energy scientific computing toolkit. This NEAMS Integrated Computational Environment (NiCE) provides extensible tools and services that enable efficient code execution, input generation, pre-processing visualizations, and post-simulation data analysis and visualization for a large portion of the NEAMS Toolkit. A strong focus for the NiCE development team throughout FY 2015 has been support for the Multiphysics Object Oriented Simulation Environment (MOOSE) and the NEAMS nuclear fuel performance modeling application built on that environment, BISON. There is a strong desire in the program to enable and facilitate the use of BISON throughout nuclear energy research and industry. A primary result of this desire is the need for strong support for BISON in NiCE. This report will detail improvements to NiCE support for BISON. We will present a new and improved interface for interacting with BISON simulations in a variety of ways: (1) improved input model generation, (2) embedded mesh and solution data visualizations, and (3) local and remote BISON simulation launch. We will also show how NiCE has been extended to provide support for BISON code development.

  3. ANSTO: Australian Nuclear Science and Technology Organization

    NASA Astrophysics Data System (ADS)

    The Australian Nuclear Science and Technology Organization conducts or is engaged in collaborative research and development in the application of nuclear science and associated technology. Through its Australian radio-isotopes unit, it markets radioisotopes, their products and other services for the nuclear medicine industry and research. It also operates national nuclear facilities (HIFAR and Moata research reactors), promotes training, provides advice and disseminates information on nuclear science and technology. The booklet briefly outlines these activities.

  4. Innovations in Nuclear Infrastructure and Education

    SciTech Connect

    Gutteridge, John

    2002-09-30

    This PowerPoint presentation was given at the Nuclear Energy Research Advisory Committee meeting held in Crystal City, VA, 30 Sept - 1 Oct 2002. The talk addresses activities in the area of Innovations in Nuclear Infrastructure and Education (INIE) meant to counter declines in the nuclear workforce and prepare for the future in the nuclear industry. Three INIE programs are described: The Western Nuclear Science Alliance, the Big-10 Consortium, and Southwest Consortium.

  5. Nuclear Medicine.

    ERIC Educational Resources Information Center

    Badawi, Ramsey D.

    2001-01-01

    Describes the use of nuclear medicine techniques in diagnosis and therapy. Describes instrumentation in diagnostic nuclear medicine and predicts future trends in nuclear medicine imaging technology. (Author/MM)

  6. Progress of teaching and learning of nuclear engineering courses at College of Engineering, Universiti Tenaga Nasional (UNITEN)

    SciTech Connect

    Hamid, Nasri A. Mohamed, Abdul Aziz; Yusoff, Mohd. Zamri

    2015-04-29

    Developing human capital in nuclear with required nuclear background and professional qualifications is necessary to support the implementation of nuclear power projects in the near future. Sufficient educational and training skills are required to ensure that the human resources needed by the nuclear power industry meets its high standard. The Government of Malaysia has made the decision to include nuclear as one of the electricity generation option for the country, post 2020 in order to cater for the increasing energy demands of the country as well as to reduce CO{sub 2} emission. The commitment by the government has been made clearer with the inclusion of the development of first NPP by 2021 in the Economic Transformation Program (ETP) which was launched by the government in October 2010. The In tandem with the government initiative to promote nuclear energy, Center for Nuclear Energy, College of Engineering, Universiti Tenaga Nasional (UNITEN) is taking the responsibility in developing human capital in the area of nuclear power and technology. In the beginning, the College of Engineering has offered the Introduction to Nuclear Technology course as a technical elective course for all undergraduate engineering students. Gradually, other nuclear technical elective courses are offered such as Nuclear Policy, Security and Safeguards, Introduction to Nuclear Engineering, Radiation Detection and Nuclear Instrumentation, Introduction to Reactor Physics, Radiation Safety and Waste Management, and Nuclear Thermal-hydraulics. In addition, another course Advancement in Nuclear Energy is offered as one of the postgraduate elective courses. To enhance the capability of teaching staffs in nuclear areas at UNITEN, several junior lecturers are sent to pursue their postgraduate studies in the Republic of Korea, United States and the United Kingdom, while the others are participating in short courses and workshops in nuclear that are conducted locally and abroad. This paper

  7. Progress of teaching and learning of nuclear engineering courses at College of Engineering, Universiti Tenaga Nasional (UNITEN)

    NASA Astrophysics Data System (ADS)

    Hamid, Nasri A.; Mohamed, Abdul Aziz; Yusoff, Mohd. Zamri

    2015-04-01

    Developing human capital in nuclear with required nuclear background and professional qualifications is necessary to support the implementation of nuclear power projects in the near future. Sufficient educational and training skills are required to ensure that the human resources needed by the nuclear power industry meets its high standard. The Government of Malaysia has made the decision to include nuclear as one of the electricity generation option for the country, post 2020 in order to cater for the increasing energy demands of the country as well as to reduce CO2 emission. The commitment by the government has been made clearer with the inclusion of the development of first NPP by 2021 in the Economic Transformation Program (ETP) which was launched by the government in October 2010. The In tandem with the government initiative to promote nuclear energy, Center for Nuclear Energy, College of Engineering, Universiti Tenaga Nasional (UNITEN) is taking the responsibility in developing human capital in the area of nuclear power and technology. In the beginning, the College of Engineering has offered the Introduction to Nuclear Technology course as a technical elective course for all undergraduate engineering students. Gradually, other nuclear technical elective courses are offered such as Nuclear Policy, Security and Safeguards, Introduction to Nuclear Engineering, Radiation Detection and Nuclear Instrumentation, Introduction to Reactor Physics, Radiation Safety and Waste Management, and Nuclear Thermal-hydraulics. In addition, another course Advancement in Nuclear Energy is offered as one of the postgraduate elective courses. To enhance the capability of teaching staffs in nuclear areas at UNITEN, several junior lecturers are sent to pursue their postgraduate studies in the Republic of Korea, United States and the United Kingdom, while the others are participating in short courses and workshops in nuclear that are conducted locally and abroad. This paper describes

  8. Nuclear Science References Database

    SciTech Connect

    Pritychenko, B.; Běták, E.; Singh, B.; Totans, J.

    2014-06-15

    The Nuclear Science References (NSR) database together with its associated Web interface, is the world's only comprehensive source of easily accessible low- and intermediate-energy nuclear physics bibliographic information for more than 210,000 articles since the beginning of nuclear science. The weekly-updated NSR database provides essential support for nuclear data evaluation, compilation and research activities. The principles of the database and Web application development and maintenance are described. Examples of nuclear structure, reaction and decay applications are specifically included. The complete NSR database is freely available at the websites of the National Nuclear Data Center (http://www.nndc.bnl.gov/nsr) and the International Atomic Energy Agency (http://www-nds.iaea.org/nsr)

  9. Conceptual design report: Nuclear materials storage facility renovation. Part 5, Structural/seismic investigation. Section B, Renovation calculations/supporting data

    SciTech Connect

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This report is organized according to the sections and subsections. It is organized into seven parts. This document, Part V, Section B - Structural/Seismic Information provides a description of the seismic and structural analyses performed on the NMSF and their results.

  10. Conceptual design report: Nuclear materials storage facility renovation. Part 5, Structural/seismic investigation. Section A report, existing conditions calculations/supporting information

    SciTech Connect

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. Based upon US Department of Energy (DOE) Albuquerque Operations (DOE/Al) Office and LANL projections, storage space limitations/restrictions will begin to affect LANL`s ability to meet its missions between 1998 and 2002.

  11. Industrial garnet

    USGS Publications Warehouse

    Olson, D.W.

    2001-01-01

    A general overview of the industrial garnet industry is provided. About 20 percent of global industrial garnet production takes place in the U.S. During 2000, an estimated 300 kt of industrial garnets were produced worldwide. The U.S. is the world's largest consumer of industrial garnet, consuming 56.9 kt in 2000.

  12. Navajos and National Nuclear Policy.

    ERIC Educational Resources Information Center

    Barry, Tom

    1979-01-01

    Describes the history of nuclear development in New Mexico, notes the cumulative detrimental effect on the Navajo Nation, and emphasizes federal inaction regarding health and safety standards and regulation in the nuclear power industry. Journal availability: see RC 503 522. (SB)

  13. Nuclear pumped gas laser research

    NASA Technical Reports Server (NTRS)

    Thom, K.

    1976-01-01

    Nuclear pumping of lasers by fission-fragments from nuclear chain reactions is discussed. Application of the newly developed lasers to spacecraft propulsion or onboard power, to lunar bases for industrial processing, and to earth for utilization of power without pollution and hazards is envisioned. Emphasis is placed on the process by which the fission-fragement kinetic energy is converted into laser light.

  14. Manufacturing Technology Support (MATES) II Task Order 0006: Air Force Technology and Industrial Base Research and Analysis. Subtask Order 0004: Study on Supply Chains and Social Media

    DTIC Science & Technology

    2013-10-01

    tapping into the volume and tone of conversations within the ESN platform as well as across the internet . Finally, current industrial base analysis...preferred method of connection, conversation and collaboration for millions of people worldwide – and the number one use of the Internet by far. The...class performers are “…currently leveraging supplier B2B social efforts to improve intelligence and supply chain operations” (Aberdeen Group, 2012

  15. Assessment of the impact of petroleum and petrochemical industries to the surrounding areas in Malaysia using mosses as bioindicator supported by multivariate analysis.

    PubMed

    Abdullah, Mohd Zahari Bin; Saat, Ahmad Bin; Hamzah, Zaini Bin

    2012-06-01

    Biomonitoring of multi-element atmospheric deposition using terrestrial moss is a well-established technique in Europe. Although the technique is widely known, there were very limited records of using this technique to study atmospheric air pollution in Malaysia. In this present study, the deposition of 11 trace metals surrounding the main petroleum refinery plant in Kerteh Terengganu (eastern part of peninsular Malaysia) has been evaluated using two local moss species, namely Hypnum plumaeforme and Taxithelium instratum as bioindicators. The study was also done by means of observing whether these metals are attributed to work related to oil exploration in this area. The moss samples have been collected at 30 sampling stations in the vicinity of the petrochemical industrial area covering up to 15 km to the south, north, and west in radius. The contents of heavy metal in moss samples were analyzed by energy dispersive x-ray fluorescence technique. Distribution of heavy metal content in all mosses is portrayed using Surfer software. Areas of the highest level of contaminations are highlighted. The results obtained using the principal components analysis revealed that the elements can be grouped into three different components that indirectly reflected three different sources namely anthropogenic factor, vegetation factor, and natural sources (soil dust or substrate) factor. Heavy metals deposited mostly in the distance after 9 km onward to the western part (the average direction of wind blow). V, Cr, Cu, and Hg are believed to have originated from local petrochemical-based industries operated around petroleum industrial area.

  16. Nuclear Power in Japan.

    ERIC Educational Resources Information Center

    Powell, John W.

    1983-01-01

    Energy consumption in Japan has grown at a faster rate than in any other major industrial country. To maintain continued prosperity, the government has embarked on a crash program for nuclear power. Current progress and issues/reactions to the plan are discussed. (JN)

  17. Industrial diamond

    USGS Publications Warehouse

    Olson, D.W.

    2003-01-01

    Statistics on the production, consumption, cost, trade, and government stockpile of natural and synthetic industrial diamond are provided. The outlook for the industrial diamond market is also considered.

  18. NATO Allied Joint Medical Publication 7: Allied Joint Medical Doctrine for Support to Chemical, Biological, Radiological, and Nuclear (CBRN) Defensive Operations, Final Draft

    DTIC Science & Technology

    2014-07-31

    assets such as RDOIT and MRIIT c. Utilization of national outreach, reach back and fusion, and forensic capabilities d. Availability and utilization...hazards can be naturally occurring, including those related to air, water, soil quality and entomology , and man-made, including industrial sites...soil and water quality, entomological hazards, and TIMs encountered during operations. 5. NATO has recently undertaken a number of initiatives

  19. A Strategy for Nuclear Energy Research and Development

    SciTech Connect

    Ralph G. Bennett

    2008-12-01

    The United States is facing unprecedented challenges in climate change and energy security. President-elect Obama has called for a reduction of CO2 emissions to 1990 levels by 2020, with a further 80% reduction by 2050. Meeting these aggressive goals while gradually increasing the overall energy supply requires that all non-emitting technologies must be advanced. The development and deployment of nuclear energy can, in fact, help the United States meet several key challenges: 1) Increase the electricity generated by non-emitting sources to mitigate climate change, 2) Foster the safe and proliferation-resistant use of nuclear energy throughout the world, 3) Reduce the transportation sector’s dependence on imported fossil fuels, and 4) Reduce the demand on natural gas for process heat and hydrogen production. However, because of the scale, cost, and time horizons involved, increasing nuclear energy’s share will require a coordinated research effort—combining the efforts of industry and government, supported by innovation from the research community. This report outlines the significant nuclear energy research and development (R&D) necessary to create options that will allow government and industrial decision-makers to set policies and create nuclear energy initiatives that are decisive and sustainable. The nuclear energy R&D strategy described in this report adopts the following vision: Safe and economical nuclear energy in the United States will expand to address future electric and non-electric needs, significantly reduce greenhouse gas emissions and provide energy diversity, while providing leadership for safe, secure and responsible expansion of nuclear energy internationally.

  20. Background studies in support of a feasibility assessment on the use of copper-base materials for nuclear waste packages in a repository in tuff

    SciTech Connect

    Van Konynenburg, R.A.; Kundig, K.J.A.; Lyman, W.S.; Prager, M.; Meyers, J.R.; Servi, I.S.

    1990-06-01

    This report combines six work units performed in FY`85--86 by the Copper Development Association and the International Copper Research Association under contract with the University of California. The work includes literature surveys and state-of-the-art summaries on several considerations influencing the feasibility of the use of copper-base materials for fabricating high-level nuclear waste packages for the proposed repository in tuff rock at Yucca Mountain, Nevada. The general conclusion from this work was that copper-base materials are viable candidates for inclusion in the materials selection process for this application. 55 refs., 48 figs., 22 tabs.