Science.gov

Sample records for licence permitting dismantling

  1. Dismantling techniques

    SciTech Connect

    Wiese, E.

    1998-03-13

    Most of the dismantling techniques used in a Decontamination and Dismantlement (D and D) project are taken from conventional demolition practices. Some modifications to the techniques are made to limit exposure to the workers or to lessen the spread of contamination to the work area. When working on a D and D project, it is best to keep the dismantling techniques and tools as simple as possible. The workers will be more efficient and safer using techniques that are familiar to them. Prior experience with the technique or use of mock-ups is the best way to keep workers safe and to keep the project on schedule.

  2. Stockpile Dismantlement Database Training Materials

    SciTech Connect

    Not Available

    1993-11-01

    This document, the Stockpile Dismantlement Database (SDDB) training materials is designed to familiarize the user with the SDDB windowing system and the data entry steps for Component Characterization for Disposition. The foundation of information required for every part is depicted by using numbered graphic and text steps. The individual entering data is lead step by step through generic and specific examples. These training materials are intended to be supplements to individual on-the-job training.

  3. Recommendations for improving the home office project licence abstracts.

    PubMed

    Hudson, Michelle

    2006-05-01

    The Freedom of Information Act 2000 prompted the Government to evaluate how public understanding about the use of animals in scientific research can be improved and how animal experimentation is regulated within the UK. This resulted in the publication of anonymous project licence abstracts. Here, the abstracts published between December 2004 and October 2005 have been evaluated, by using a scoring system which takes into account their content and format, in order to assess whether they provide information that will facilitate the increased implementation of reduction, refinement and replacement strategies. The potential impact of freely-available Home Office project licence abstracts on public attitudes to animal testing and on the quality of animal-based research, is also discussed. Although some abstracts scored well, in general, the abstracts were found to be severely lacking in detail about the welfare of experimental animals. Thus, the abstracts tend to present a distorted picture of animal-based research. Many abstracts lack the details which would reveal how the licensing criteria had been met. It is concluded that, in their current form, the project abstracts are not sufficiently informative. A number of recommendations are made, which address this problem. PMID:16704294

  4. First time description of dismantling phenomenon

    PubMed Central

    Barrer, Laurence; Gimenez, Guy

    2015-01-01

    Dismantling is a complex psychic phenomenon, which is not easy to define, and little interest has been shown in the subject. The authors of this paper want to demonstrate that dismantling is the main defense mechanism in autism, bringing about de-consensus of senses. The effects perceived in a child with autistic disorder are passivity and lack of thought. The authors’ purpose here is to define the dismantled state and reveal its underlying process. This paper will therefore describe for the first time in literature, the dismantling phenomenon and will submit a metapsychological approach of this defense mechanism. PMID:25999871

  5. Method for dismantling a natural gas holder

    SciTech Connect

    Settlemier, B.R.; Bone, S.R.; Tolivaisa, J.; Nugent, J.E.

    1990-10-30

    This patent describes a method of dismantling a natural gas holder. The holder has vertical support columns disposed around the periphery of the holder to which the enclosure shell of the holder is attached.

  6. Weapons dismantlement issues in independent Ukraine

    SciTech Connect

    Zack, N.R.; Kirk, E.J.

    1994-07-01

    The American Association for the Advancement of Science sponsored a seminar during September 1993, in Kiev, Ukraine, entitled ``Toward a Nuclear Free Future -- Barriers and Problems.`` It brought together Ukrainians, Belarusians, and Americans to discuss the legal, political, safeguards and security, economic, and technical dimensions of nuclear weapons dismantlement and destruction. US representatives initiated discussions on legal and treaty requirements and constraints, safeguards and security issues surrounding dismantlement, storage and disposition of nuclear materials, warhead transportation, and economic considerations. Ukrainians gave presentations on arguments for and against the Ukraine keeping nuclear weapons, Ukrainian Parliament non-approval of START I, alternative strategies for dismantling silos and launchers, and economic and security implications of nuclear weapons removal from the Ukraine. Participants from Belarus discussed proliferation and control regime issues, This paper will highlight and detail the issues, concerns, and possible impacts of the Ukraine`s dismantlement of its nuclear weapons.

  7. The social licence for research: why care.data ran into trouble

    PubMed Central

    Carter, Pam; Laurie, Graeme T; Dixon-Woods, Mary

    2015-01-01

    In this article we draw on the concept of a social licence to explain public concern at the introduction of care.data, a recent English initiative designed to extract data from primary care medical records for commissioning and other purposes, including research. The concept of a social licence describes how the expectations of society regarding some activities may go beyond compliance with the requirements of formal regulation; those who do not fulfil the conditions for the social licence (even if formally compliant) may experience ongoing challenge and contestation. Previous work suggests that people's cooperation with specific research studies depends on their perceptions that their participation is voluntary and is governed by values of reciprocity, non-exploitation and service of the public good. When these conditions are not seen to obtain, threats to the social licence for research may emerge. We propose that care.data failed to adequately secure a social licence because of: (i) defects in the warrants of trust provided for care.data, (ii) the implied rupture in the traditional role, expectations and duties of general practitioners, and (iii) uncertainty about the status of care.data as a public good. The concept of a social licence may be useful in explaining the specifics of care.data, and also in reinforcing the more general lesson for policy-makers that legal authority does not necessarily command social legitimacy. PMID:25617016

  8. The social licence for research: why care.data ran into trouble.

    PubMed

    Carter, Pam; Laurie, Graeme T; Dixon-Woods, Mary

    2015-05-01

    In this article we draw on the concept of a social licence to explain public concern at the introduction of care.data, a recent English initiative designed to extract data from primary care medical records for commissioning and other purposes, including research. The concept of a social licence describes how the expectations of society regarding some activities may go beyond compliance with the requirements of formal regulation; those who do not fulfil the conditions for the social licence (even if formally compliant) may experience ongoing challenge and contestation. Previous work suggests that people's cooperation with specific research studies depends on their perceptions that their participation is voluntary and is governed by values of reciprocity, non-exploitation and service of the public good. When these conditions are not seen to obtain, threats to the social licence for research may emerge. We propose that care.data failed to adequately secure a social licence because of: (i) defects in the warrants of trust provided for care.data, (ii) the implied rupture in the traditional role, expectations and duties of general practitioners, and (iii) uncertainty about the status of care.data as a public good. The concept of a social licence may be useful in explaining the specifics of care.data, and also in reinforcing the more general lesson for policy-makers that legal authority does not necessarily command social legitimacy. PMID:25617016

  9. Switching from deferred dismantling to immediate dismantling: the example of Chooz A, a French PWR

    SciTech Connect

    Grenouillet, Jean-Jacques

    2007-07-01

    Located in the north of France, close to Belgian border, Chooz A is the first PWR that was built in France from 1962 to 1967. When it was shutdown in 1991, a deferred dismantling strategy was selected. Further to an evolution of EDF decommissioning strategy in 2001, the decommissioning of the plant was accelerated by reducing the safe enclosure period to only a few years. Thus Chooz A will be the first PWR to be fully dismantled in France and it gives a good insight of what is needed to reactivate a plant for final dismantling after a safe enclosure period. (author)

  10. Nonfatal firearm misuse: licence status of perpetrators and legality of the firearms.

    PubMed

    Gardiner, J; Norton, R; Alpers, P

    1996-10-01

    The primary aim of this study was to identify the licence status of those involved in incidents of nonfatal firearm-related misuse and to determine the involvement of legal firearms in such incidents. Firearm-related attempted suicides were excluded. The study also sought to identify the types of firearms most likely to be misused. Over a three-month period in early 1994, all nonfatal firearm-related incidents reported in any New Zealand newspaper were identified by a commercial clipping bureau. Data pertaining to the licence status and the legality of the firearm involved in these incidents were obtained from the police who completed a standardized questionnaire under the Official Information Act (1982). Over the study period, 78 incidents yielded information on 97 perpetrators and 100 firearms. Of the 97 perpetrators, 66 per cent were unlicensed, 20 per cent were licensed, the licence status of 8 per cent of the perpetrators was unknown and the remaining 7 per cent were using air guns and therefore a licence was not required. Half of the perpetrators involved in domestic disputes were licensed. Of the 100 firearms, 44 per cent were classified as "legal firearms' and 56 per cent were classified as "illegal firearms'. These findings suggest that strategies aimed at reducing or preventing injury due to firearm misuse must focus on both licensed and unlicensed individuals and both legal and illegal firearms. PMID:8987216

  11. A European Computer Driving Licence: Integrating Computer Literacy in the New Social Work Degree

    ERIC Educational Resources Information Center

    Gregor, Claire

    2008-01-01

    "Informacy", the learning of information technology skills, is now a key element of all Social Work curricula in the U.K. following the General Social Care Council's accreditation requirements. These stipulate that all undergraduates acquire computer literacy skills to the level of the European Computer Driving Licence (ECDL) or its equivalence…

  12. The AREVA NC Cadarache Plant Dismantling Plan

    SciTech Connect

    Sainte Marie, Noel de

    2008-01-15

    The AREVA NC Cadarache Plant has manufactured MOX fuel (mixed uranium and plutonium oxides fuel assemblies) for forty years. The plant was first dedicated to fast neutrons reactors fuels. Then, it produced 345 tons of MOX fuel for light water reactors for French and European customers. 50 tons of plutonium was recycled. In July 2003 the manufacturing of commercial fuel stopped and the plant has entered a double process plan : - conditioning production scraps issued from former fabrications in order to send them to the AREVA NC La Hague Plant for treatment and recycling process, - carrying out of the dismantling operations of these facilities. In conclusion: In a social context and with a bi-activity, AREVA NC Cadarache knows how to adapt itself and answer the increasing challenge of the dismantling activity, with very satisfactory results. After the final stop of the scraps conditioning in 2008, AREVA NC Cadarache plant is going to reach its rhythm of 80 equipments dismantled per year and to end the operations on equipments in active zone in 2013. As a consequence, new challenges begin : - adapt the organisation to integrate an increasing number of outside companies while guaranteeing a high level of safety-security, - consolidate the good radiation protection results of the staff, - respect the costs and delays of the project by putting the priority on the critical path of the schedule, - absorb the increase of waste flows, while maintaining low level of waste intended for deep storage, - improve dismantling performances and implement new techniques by integrating the experience feedback and innovation development.

  13. Advanced robotics for decontamination and dismantlement

    SciTech Connect

    Hamel, W.R.; Haley, D.C.

    1994-06-01

    The decontamination and dismantlement (D&D) robotics technology application area of the US Department of Energy`s Robotics Technology Development Program is explained and described. D&D robotic systems show real promise for the reduction of human exposure to hazards, for improvement of productivity, and for the reduction of secondary waste generation. Current research and development pertaining to automated floor characterization, robotic equipment removal, and special inspection is summarized. Future research directions for these and emerging activities is given.

  14. Capacitive tool standoff sensor for dismantlement tasks

    SciTech Connect

    Schmitt, D.J.; Weber, T.M.; Liu, J.C.

    1996-12-31

    A capacitive sensing technology has been applied to develop a Standoff Sensor System for control of robotically deployed tools utilized in Decontamination and Dismantlement (D and D) activities. The system combines four individual sensor elements to provide non-contact, multiple degree-of-freedom control of tools at distances up to five inches from a surface. The Standoff Sensor has been successfully integrated to a metal cutting router and a pyrometer, and utilized for real-time control of each of these tools. Experiments demonstrate that the system can locate stationary surfaces with a repeatability of 0.034 millimeters.

  15. Cold Trap Dismantling and Sodium Removal at a Fast Breeder Reactor - 12327

    SciTech Connect

    Graf, A.; Petrick, H.; Stutz, U.; Hosking, P.

    2012-07-01

    The first German prototype Fast Breeder Nuclear Reactor (KNK) is currently being dismantled after being the only operating Fast Breeder-type reactor in Germany. As this reactor type used sodium as a coolant in its primary and secondary circuit, seven cold traps containing various amounts of partially activated sodium needed to be disposed of as part of the dismantling. The resulting combined difficulties of radioactive contamination and high chemical reactivity were handled by treating the cold traps differently depending on their size and the amount of sodium contained inside. Six small cold traps were processed onsite by cutting them up into small parts using a band saw under a protective atmosphere. The sodium was then converted to sodium hydroxide by using water. The remaining large cold trap could not be handled in the same way due to its dimensions (2.9 m x 1.1 m) and the declared amount of sodium inside (1,700 kg). It was therefore manually dismantled inside a large box filled with a protective atmosphere, while the resulting pieces were packaged for later burning in a special facility. The experiences gained by KNK during this process may be advantageous for future dismantling projects in similar sodium-cooled reactors worldwide. The dismantling of a prototype fast breeder reactor provides the challenge not only to dismantle radioactive materials but also to handle sodium-contaminated or sodium-containing components. The treatment of sodium requires additional equipment and installations to ensure a safe handling. Since it is not permitted to bring sodium into a repository, all sodium has to be neutralized either through a controlled reaction with water or by incinerating. The resulting components can be disposed of as normal radioactive waste with no further conditions. The handling of sodium needs skilled and experienced workers to minimize the inherent risks. And the example of the disposal of the large KNK cold trap shows the interaction with others and

  16. Autoradiography Using OSL for Monitoring Warhead Dismantlement

    SciTech Connect

    Tanner, Jennifer E.; Miller, Steven D.; Conrady, Matthew M.; Benz, Jacob M.

    2010-08-11

    The use of radiation imaging techniques to provide increased confidence in a dismantlement verification regime is still under investigation. Currently, radiation measurements can be used to confirm attributes such as the presence, quality, and mass of containerized nuclear material. However, imaging techniques can be used to confirm the shape, size, and/or symmetry of the object being interrogated. Imaging can be used as a complementary technique to radiation measurements to confirm a declaration or as a chain of custody measure to confirm that an item has not been tampered with. As with other attribute measurements, the image data must be protected behind an information barrier and analyzed to give an unclassified result when compared to an agreed upon threshold. This paper will discuss the use of Optically Stimulated Luminescence to perform autoradiography of sources using coded apertures to differentiate between point sources and various distributed sources. The coded aperture chosen for this application is based on modified uniform redundant arrays (mURAs) which resulted in the design and manufacture of an efficient, high-resolution mURA mask/antimask system. The potential use of the autoradiography technique with the coded aperture as an intrinsic information barrier and the required protection of the mask and unfolding algorithm will also be discussed. This project has been supported by the US Department of Energy’s National Nuclear Security Administration’s Office of Dismantlement and Transparency (DOE/NNSA/NA-241).

  17. Shielded Cells D&D and Dismantlement System Requirements

    SciTech Connect

    Witherspoon, R.L.

    1995-03-27

    This document describes the basis for the development of the System for Highly Radioactive Equipment Dismantlement or SHRED. It is the result of a thorough investigation into current and past dismantlement practices at shielded cell facilities around the DOE complex. This information has been used to formulate the development requirements for the SHRED.

  18. Drive to dismantle commerce department rolls on

    NASA Astrophysics Data System (ADS)

    Carlowicz, Michael

    Late on November 7, Republican leaders of the House of Representatives tacked a measure to abolish the U.S. Department of Commerce onto a continuing resolution that keeps the federal government running and solvent while the fiscal 1996 budget debate continues. With the existing temporary funding measure expiring on November 13, congressional leaders were working to extend the budget again and to raise the national debt ceiling.The fate of the effort to terminate Commerce—which would eliminate the position of the Secretary of Commerce and shut down or transfer the department's programs to other departments—remained unclear at press time because Senate Republicans had not yet voiced support for the measure. The Clinton Administration has stated that the president would veto any attempt to shut down the Commerce Department; however, the link between the current dismantling measure and the continuing resolution to avert a government shutdown and financial default has further complicated the Administration's position.

  19. Environmental Assessment for decontamination and dismantlement, Pinellas Plant

    SciTech Connect

    1995-06-01

    The US Department of Energy (DOE) has prepared an Environmental Assessment (EA) (DOE/EA-1092) of the proposed decontamination and dismantlement of the Pinellas Plant in Largo, Florida. Under the Decontamination and Dismantlement EA, the DOE proposes to clean up facilities, structures, and utilities; dismantle specific structures; and mitigate or eliminate any environmental impacts associated with the cleanup, dismantlement, and related activities. Related activities include utilization of specific areas by new tenants prior to full-scale cleanup. Based on the analyses in the EA, the DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment, within the meaning of the National Environmental Policy Act of 1969. Therefore, the preparation of an environmental impact statement is not required. This report contains the Environmental Assessment, as well as the Finding of No Significant Impact (FONSI).

  20. 72. VIEW SHOWING THE CONTINUAL DISMANTLING OF M STREET BRIDGE, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    72. VIEW SHOWING THE CONTINUAL DISMANTLING OF M STREET BRIDGE, LOOKING SOUTHWEST, February 9, 1935 - Sacramento River Bridge, Spanning Sacramento River at California State Highway 275, Sacramento, Sacramento County, CA

  1. Pollution from EOLV dismantling and the corresponding countermeasures.

    PubMed

    Zhang, Hu

    2016-05-15

    There are problems associated with dismantling vessels that have reached the end of their life, when pollution problems associated with the process need to be addressed. The first problem in "end-of-life vessels" (EOLV) is to define their legal frameworks. The second problem is their dismantlement for recycling of ships. In order to reduce the effects of pollution caused by EOLV dismantling, the International Maritime Organization (IMO) adopted the Hong Kong Convention on 15 May 2009. While preparing for implementing the obligations under the Hong Kong Convention, China shall make effort on five aspects: (i) establish an ISRT for the safe and environmentally sound recycling of ships, (ii) improve the competitiveness of ship dismantling plants, (iii) strengthen international exchanges, (iv) amend the domestic laws and regulations, and (v) support from the China Classification Society. PMID:27039959

  2. POWER HOUSE, DISMANTLED TURBOGENERATOR IN RIGHT FOREGROUND WITH TURBOGENERATOR AND ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    POWER HOUSE, DISMANTLED TURBO-GENERATOR IN RIGHT FOREGROUND WITH TURBO-GENERATOR AND OFFICE BEYOND. RAILED AREA IS A STAIRWELL. VIEW FROM NORTHWEST - Kekaha Sugar Company, Sugar Mill Building, 8315 Kekaha Road, Kekaha, Kauai County, HI

  3. 14. VIEW TO NORTHWEST, SMALL ROASTER (DISMANTLED). Vanadium Corporation ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    14. VIEW TO NORTHWEST, SMALL ROASTER (DISMANTLED). - Vanadium Corporation of America (VCA) Naturita Mill, 3 miles Northwest of Naturita, between Highway 141 & San Miguel River, Naturita, Montrose County, CO

  4. DISMANTLING OF THE FUEL CELL LABORATORY AT RESEARCH CENTRE JUELICH

    SciTech Connect

    Stahn, B.; Matela, K.; Bensch, D.; Ambos, Frank

    2003-02-27

    The fuel cell laboratory was constructed in three phases and taken into operation in the years 1962 to 1966. The last experimental work was carried out in 1996. After all cell internals had been disassembled, the fuel cell laboratory was transferred to shutdown operation in 1997. Three cell complexes, which differed, in particular, by the type of shielding (lead, cast steel, concrete), were available until then for activities at nuclear components. After approval by the regulatory authority, the actual dismantling of the fuel cell laboratory started in March 2000. The BZ I laboratory area consisted of 7 cells with lead shieldings of 100 to 250 mm thickness. This area was dismantled from April to September 2000. Among other things, approx. 30,000 lead bricks with a total weight of approx. 300 Mg were dismantled and disposed of. The BZ III laboratory area essentially consisted of cells with concrete shieldings of 1200 to 1400 mm thickness. The dismantling of this area started in the fir st half of 2001 and was completed in November 2002. Among other things, approx. 900 Mg of concrete was dismantled and disposed of. Since more than 90 % of the dismantled materials was measurable for clearance, various clearance measurement devices were used during dismantling. The BZ II laboratory area essentially consists of cells with cast steel shieldings of 400 to 460 mm thickness. In September 2002 it was decided to continue using this laboratory area for future tasks. The dismantling of the fuel cell laboratory was thus completed. After appropriate refurbishment, the fuel cell laboratory will probably take up operation again in late 2003.

  5. Iraq nuclear facility dismantlement and disposal project

    SciTech Connect

    Cochran, J.R.; Danneels, J.; Kenagy, W.D.; Phillips, C.J.; Chesser, R.K.

    2007-07-01

    The Al Tuwaitha nuclear complex near Baghdad contains a significant number of nuclear facilities from Saddam Hussein's dictatorship. Because of past military operations, lack of upkeep and looting there is now an enormous radioactive waste problem at Al Tuwaitha. Al Tuwaitha contains uncharacterised radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals. The current security situation in Iraq hampers all aspects of radioactive waste management. Further, Iraq has never had a radioactive waste disposal facility, which means that ever increasing quantities of radioactive waste and material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS has funded the International Atomic Energy Agency (IAEA) to provide technical assistance to the GOI via a Technical Cooperation Project. Program coordination will be provided by the DOS, consistent with U.S. and GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and for providing waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for the vast majority of the implementation of the NDs Program. (authors)

  6. Mobile worksystems for decontamination and dismantlement

    SciTech Connect

    Osborn, J.; Bares, L.C.; Thompson, B.R.

    1995-12-01

    Many DOE nuclear facilities have aged beyond their useful lifetimes. They need to be decommissioned in order to be safe for human presence in the short term, to eventually recover valuable materials they contain, and ultimately to be transitioned to alternative uses or green field conditions. Decontamination and dismantlement are broad classes of activities that will enable these changes to occur. Most of these facilities - uranium enrichment plants, weapons assembly plants, research and production reactors, and fuel recycling facilities - are dormant, though periodic inspection, surveillance and maintenance activities within them are on-going. DOE estimates that there are over 5000 buildings that require deactivation to reduce the costs of performing such work with manual labor. In the long term, 1200 buildings will be decommissioned, and millions of metric tons of metal and concrete will have to be recycled or disposed of The magnitude of the problem calls for new approaches that are far more cost effective than currently available techniques. This paper describes two technologies that are viable solutions for facility D&D.

  7. Mobile worksystems for decontamination and dismantlement

    SciTech Connect

    Osborn, J.; Bares, L.C.; Thompson, B.R.

    1995-10-01

    Many DOE nuclear facilities have aged beyond their useful lifetimes. They need to be decommissioned in order to be safe for human presence in the short term, to eventually recover valuable materials they contain, and ultimately to be transitioned to alternative uses or green field conditions. Decontamination and dismantlement are broad classes of activities that will enable these changes to occur. Most of these facilities - uranium enrichment plants, weapons assembly plants, research and production reactors, and fuel recycling facilities - are dormant, though periodic inspection, surveillance and maintenance activities within them are on-going. DOE estimates that there are over 5000 buildings that require deactivation to reduce the costs of performing such work with manual labor. In the long term, 1200 buildings will be decommissioned, and millions of metric tons of metal and concrete will have to be recycled or disposed of. The magnitude of the problem calls for new approaches that are far more cost effective than currently available techniques. This paper describes a mobile workstation termed ROSIE, which provides remote work capabilities for D&D activities.

  8. A study on driving status in 98 epileptic patients with driving licences.

    PubMed

    Hashimoto, K; Fukushima, Y; Saito, F; Wada, K

    1991-06-01

    As to the driving status in the period between January 1984 and December 1988, 98 epileptic patients with driving licences were examined, paying regard to their clinical conditions. Sixty-one (62%) of the patients were seizure-free for the last five years or more in December 1988. Eighty-one (83%) were actually driving motor vehicles at the time of this study, and 27 (33%) of the 81 drivers still had fits during the past five years. Nine patients (9%) had caused traffic accidents, but no accident had occurred due to seizures. The type of the nine accidents was as follows: One case of a slight physical injury to the other person, four cases of the driver's own car damage without other material damage, and four of the accidents involving other cars. PMID:1762210

  9. Concepts and Tests for the Remote-Controlled Dismantling of the Biological Shield and Form work of the KNK Reactor - 13425

    SciTech Connect

    Neff, Sylvia; Graf, Anja; Petrick, Holger; Rothschmitt, Stefan; Klute, Stefan

    2013-07-01

    The compact sodium-cooled nuclear reactor facility Karlsruhe (KNK), a prototype Fast Breeder, is currently in an advanced stage of dismantling. Complete dismantling is based on 10 partial licensing steps. In the frame of the 9. decommissioning permit, which is currently ongoing, the dismantling of the biological shield is foreseen. The biological shield consists of heavy reinforced concrete with built-in steel fitments, such as form-work of the reactor tank, pipe sleeves, ventilation channels, and measuring devices. Due to the activation of the inner part of the biological shield, dismantling has to be done remote-controlled. During a comprehensive basic design phase a practical dismantling strategy was developed. Necessary equipment and tools were defined. Preliminary tests revealed that hot wire plasma cutting is the most favorable cutting technology due to the geometrical boundary conditions, the varying distance between cutter and material, and the heavy concrete behind the steel form-work. The cutting devices will be operated remotely via a carrier system with an industrial manipulator. The carrier system has expandable claws to adjust to the varying diameter of the reactor shaft during dismantling progress. For design approval of this prototype development, interaction between manipulator and hot wire plasma cutting was tested in a real configuration. For the demolition of the concrete structure, an excavator with appropriate tools, such as a hydraulic hammer, was selected. Other mechanical cutting devices, such as a grinder or rope saw, were eliminated because of concrete containing steel spheres added to increase the shielding factor of the heavy concrete. Dismantling of the biological shield will be done in a ring-wise manner due to static reasons. During the demolition process, the excavator is positioned on its tripod in three concrete recesses made prior to the dismantling of the separate concrete rings. The excavator and the manipulator carrier system

  10. Dismantlement and Radioactive Waste Management of DPRK Nuclear Facilities

    SciTech Connect

    Jooho, W.; Baldwin, G. T.

    2005-04-01

    One critical aspect of any denuclearization of the Democratic People’s Republic of Korea (DPRK) involves dismantlement of its nuclear facilities and management of their associated radioactive wastes. The decommissioning problem for its two principal operational plutonium facilities at Yongbyun, the 5MWe nuclear reactor and the Radiochemical Laboratory reprocessing facility, alone present a formidable challenge. Dismantling those facilities will create radioactive waste in addition to existing inventories of spent fuel and reprocessing wastes. Negotiations with the DPRK, such as the Six Party Talks, need to appreciate the enormous scale of the radioactive waste management problem resulting from dismantlement. The two operating plutonium facilities, along with their legacy wastes, will result in anywhere from 50 to 100 metric tons of uranium spent fuel, as much as 500,000 liters of liquid high-level waste, as well as miscellaneous high-level waste sources from the Radiochemical Laboratory. A substantial quantity of intermediate-level waste will result from disposing 600 metric tons of graphite from the reactor, an undetermined quantity of chemical decladding liquid waste from reprocessing, and hundreds of tons of contaminated concrete and metal from facility dismantlement. Various facilities for dismantlement, decontamination, waste treatment and packaging, and storage will be needed. The shipment of spent fuel and liquid high level waste out of the DPRK is also likely to be required. Nuclear facility dismantlement and radioactive waste management in the DPRK are all the more difficult because of nuclear nonproliferation constraints, including the call by the United States for “complete, verifiable and irreversible dismantlement,” or “CVID.” It is desirable to accomplish dismantlement quickly, but many aspects of the radioactive waste management cannot be achieved without careful assessment, planning and preparation, sustained commitment, and long

  11. Licence to be active: parental concerns and 10–11-year-old children's ability to be independently physically active

    PubMed Central

    Jago, Russell; Thompson, Janice L.; Page, Angie S.; Brockman, Rowan; Cartwright, Kim; Fox, Kenneth R.

    2009-01-01

    Background Physical activity independent of adult supervision is an important component of youth physical activity. This study examined parental attitudes to independent activity, factors that limit licence to be independently active and parental strategies to facilitate independent activity. Methods In-depth phone interviews were conducted with 24 parents (4 males) of 10–11-year-old children recruited from six primary schools in Bristol. Results Parents perceived that a lack of appropriate spaces in which to be active, safety, traffic, the proximity of friends and older children affected children's ability to be independently physically active. The final year of primary school was perceived as a period when children should be afforded increased licence. Parents managed physical activity licence by placing time limits on activity, restricting activity to close to home, only allowing activity in groups or under adult supervision. Conclusions Strategies are needed to build children's licence to be independently active; this could be achieved by developing parental self-efficacy to allow children to be active and developing structures such as safe routes to parks and safer play areas. Future programmes could make use of traffic-calming programmes as catalysts for safe independent physical activity. PMID:19505927

  12. 49 CFR 1242.42 - Administration, repair and maintenance, machinery repair, equipment damaged, dismantling retired...

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 49 Transportation 9 2010-10-01 2010-10-01 false Administration, repair and maintenance, machinery repair, equipment damaged, dismantling retired property, fringe benefits, other casualties and insurance... maintenance, machinery repair, equipment damaged, dismantling retired property, fringe benefits,...

  13. Vehicle impoundments improve drinking and driving licence suspension outcomes: Large-scale evidence from Ontario.

    PubMed

    Byrne, Patrick A; Ma, Tracey; Elzohairy, Yoassry

    2016-10-01

    Although vehicle impoundment has become a common sanction for various driving offences, large-scale evaluations of its effectiveness in preventing drinking and driving recidivism are almost non-existent in the peer-reviewed literature. One reason is that impoundment programs have typically been introduced simultaneously with other countermeasures, rendering it difficult to disentangle any observed effects. Previous studies of impoundment effectiveness conducted when such programs were implemented in isolation have typically been restricted to small jurisdictions, making high-quality evaluation difficult. In contrast, Ontario's "long-term" and "seven-day" impoundment programs were implemented in relative isolation, but with tight relationships to already existing drinking and driving suspensions. In this work, we used offence data produced by Ontario's population of over 9 million licensed drivers to perform interrupted time series analysis on drinking and driving recidivism and on rates of driving while suspended for drinking and driving. Our results demonstrate two key findings: (1) impoundment, or its threat, improves compliance with drinking and driving licence suspensions; and (2) addition of impoundment to suspension reduces drinking and driving recidivism, possibly through enhanced suspension compliance. PMID:27434801

  14. The new licencing examination for human medicine: from concept to implementation.

    PubMed

    Guttormsen, Sissel; Beyeler, Christine; Bonvin, Raphael; Feller, Sabine; Schirlo, Christian; Schnabel, Kai; Schurter, Tina; Berendonk, Christoph

    2013-01-01

    A new Swiss federal licencing examination for human medicine (FLE) was developed and released in 2011. This paper describes the process from concept design to the first results obtained on implementation of the new examination. The development process was based on the Federal Act on University Medical Professions and involved all national stakeholders in this venture. During this process questions relating to the assessment aims, the assessment formats, the assessment dimensions, the examination content and necessary trade-offs were clarified. The aims were to create a feasible, fair, valid and psychometrically sound examination in accordance with international standards, thereby indicating the expected knowledge and skills level at the end of undergraduate medical education. Finally, a centrally managed and locally administered examination comprising a written multiple-choice element and a practical “clinical skills” test in the objective structured clinical examination (OSCE) format was developed. The first two administrations of the new FLE show that the examination concept could be implemented as intended. The anticipated psychometric indices were achieved and the results support the validity of the examination. Possible changes to the format or content in the future are discussed. PMID:24301323

  15. 47. DISMANTLING OF ROOF. Removal of the first truss with ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    47. DISMANTLING OF ROOF. Removal of the first truss with crane and cradle. Note the reinforcing plates at the panel points. The rear of the PSFS building is beyond. Note that the face bricks of the entire Meeting House have been stripped off for reuse at the new George School site. - Twelfth Street Meeting House, 20 South Twelfth Street, Philadelphia, Philadelphia County, PA

  16. Nuclear-weapons dismantlement: Identifying a hidden warhead

    NASA Astrophysics Data System (ADS)

    Finney, John; Acton, James M.

    2014-06-01

    A means of verifying that nuclear warheads to be dismantled are genuine items has been proposed that potentially reveals no information to an inspector about the design of the weapons. Two experts explain the ins and outs of the method and its implications for arms-control policy. See Article p.497

  17. Concept for Dismantling the Reactor Vessel and the Biological Shield of the Compact Sodium-Cooled Nuclear Reactor Facility (KNK)

    SciTech Connect

    Hillebrand, I.; Benkert, J.

    2002-02-27

    The Compact Sodium-cooled Nuclear Reactor Facility (KNK) was an experimental nuclear power plant of 20 MW electric power erected on the premises of the Karlsruhe Research Center. The plant was initially run as KNK I with a thermal core between 1971 and 1974 and then, between 1977 and 1991, with a fast core as the KNK II fast breeder plant. Under the decommissioning concept, the plant is to be decommissioned completely to green field conditions at the end of 2005 in ten steps, i.e. under the corresponding ten decommissioning permits. To this day, nine decommissioning permits have been issued, the first one in 1993 and the most recent one, number nine, in 2001. The decommissioning and demolition activities covered by decommissioning permits 1 to 7 have been completed. Under the 8th Decommissioning Permit, the components of the primary system and the rotating reactor top shield are to be removed by late 2001. Under the 9th Decommissioning Permit, the reactor vessel with its internals, the primary shield, and the biological shield are to be dismantled. The residual sodium volume in the reactor vessel was estimated to amount to approx. 30 l. The maximum Co-60 activation is on the order of 107-108 Bq/g; the maximum dose rate in the middle of the vessel was measured in April 1997 to be 55 Sv/h. The difficulty involved especially in dismantling KNK, on the one hand, is posed by the residual sodium in the plant, which determines the choice of neither wet nor thermical techniques to be used in disassembly. Another difficulty is caused by the depth of activation by fast neutrons, as a result of which not only the reactor vessel proper, but also the entire primary shield (60 cm of grey cast iron) and large parts of the biological shield must be disassembled and disposed of under remote control.

  18. Pollution profiles and health risk assessment of VOCs emitted during e-waste dismantling processes associated with different dismantling methods.

    PubMed

    An, Taicheng; Huang, Yong; Li, Guiying; He, Zhigui; Chen, Jiangyao; Zhang, Chaosheng

    2014-12-01

    Pollution profiles of typical volatile organic compounds (VOCs) emitted during dismantling of various printed circuit board assemblies (PCBAs) of e-wastes using different methods were comparatively investigated in the real e-waste dismantling workshops in South China in April 2013. Similar pollution profiles and concentrations of VOCs were observed between dismantling mobile phone and hard disk PCBAs by using electric blowers and between dismantling television and power supplier PCBAs using electric heating furnaces. Aromatic hydrocarbons (accounting for >60% of the sum of VOCs) were the dominant group during using electric blowers, while aromatic (accounting for >44% of the sum of VOCs) and halogenated hydrocarbons (accounting for >48% of the sum of VOCs) were the two dominant groups which contributed equally using electric heating furnaces. However, the distribution profiles of VOCs emitted during dismantling of televisions, hard disks and micro motors using rotary incinerators varied greatly, though aromatic hydrocarbons were still the dominant group. The combustion of e-wastes led to the most severe contamination of VOCs, with total VOCs (3.3×10(4) μg m(-3)) using rotary incinerators about 190, 180, 139, and 40 times higher than those using mechanical cutting, electric soldering iron, electric blower, and electric heating furnace, respectively. Both cancer and non-cancer risks existed for workers due to exposure to on-site emitted VOCs in all workshops especially in those using rotary incinerators according to the USEPA methodology, whereas only cancer risks existed in rotary incinerator workshops according to the American Conference of Industrial Hygienists methodology. PMID:25129414

  19. Seismic experiments, nuclear dismantlement go hand in hand in Kazakhstan

    NASA Astrophysics Data System (ADS)

    Leith, William; Kluchko, Luke J.

    Unique seismic experiments involving large chemical explosions at different depths have been conducted in Kazakhstan, thanks to nuclear dismantlement activity there. Collaborative efforts of several bodies have provided this creative, cost-efficient extension of the dismantling work, improving technical monitoring and verification of the Comprehensive Test Ban Treaty (CTBT).For the past several years, the Defense Special Weapons Agency (DSWA) has been closing the nuclear test tunnels and bore-holes at the former Soviet nuclear test site nearSemipalatinsk, eastern Kazakhstan, as part of the Nunn-Lugar Cooperative Threat Reduction (CTR) Program. The existence of this program and the infrastructure that was in place to implement it made it possible to conduct the seismic experiments. As a result, benchmark data have been collected on the variations in seismic signals from explosions at different burial depths.

  20. Systems and methods for dismantling a nuclear reactor

    DOEpatents

    Heim, Robert R; Adams, Scott Ryan; Cole, Matthew Denver; Kirby, William E; Linnebur, Paul Damon

    2014-10-28

    Systems and methods for dismantling a nuclear reactor are described. In one aspect the system includes a remotely controlled heavy manipulator ("manipulator") operatively coupled to a support structure, and a control station in a non-contaminated portion of a workspace. The support structure provides the manipulator with top down access into a bioshield of a nuclear reactor. At least one computing device in the control station provides remote control to perform operations including: (a) dismantling, using the manipulator, a graphite moderator, concrete walls, and a ceiling of the bioshield, the manipulator being provided with automated access to all internal portions of the bioshield; (b) loading, using the manipulator, contaminated graphite blocks from the graphite core and other components from the bioshield into one or more waste containers; and (c) dispersing, using the manipulator, dust suppression and contamination fixing spray to contaminated matter.

  1. Dismantled weapons fuel burning in molten salt reactors

    SciTech Connect

    Gat, U.; Engel, J.R.

    1993-10-01

    The advantages of burning fissile material from dismantled weapons in molten salt reactors (MSRs) are described. The fluid fuel MSRs with some, or full, processing are nondedicated reactors that generate energy and completely burn the fissile material on a continuous basis. No fuel fabrication is needed, and the entire dismantling can be done in a secure facility. Shipments are made in small, safe, and secure quantities. Denaturing, spiking, or mixing can be done at the source for added safety. MSRs are very safe reactors that help close the fuel cycle and simplify waste treatment, thereby contributing to acceptability. Additionally, MSRs are expected to be economically competitive as electric power stations. The safety, security, simplicity, economy, and proliferation resistant properties support the deployment in countries that have the need.

  2. Remote dismantlement activities for the Argonne CP-5 Research Reactor

    SciTech Connect

    Noakes, M.W.

    1996-12-31

    The Department of Energy`s (DOE`s) Robotics Technology Development Program (RTDP) is participating in the dismantlement of a mothballed research reactor, Chicago Pile Number 5 (CP-5), at Argonne National Laboratory (ANL) to demonstrate technology developed by the program while assisting Argonne with their remote system needs. Equipment deployed for CP-5 activities includes the dual-arm work platform (DAWP), which will handle disassembly of reactor internals, and the RedZone Robotics-developed `Rosie` remote work vehicle, which will perform size reduction of shield plugs, demolition of the biological shield, and waste packaging. Remote dismantlement tasks are scheduled to begin in February of 1997 and to continue through 1997 and beyond.

  3. Contaminated Metal Components in Dismantling by Hot Cutting Processes

    SciTech Connect

    Cesari, Franco G.; Conforti, Gianmario; Rogante, Massimo; Giostri, Angelo

    2006-07-01

    During the preparatory dismantling activities of Caorso's Nuclear Power Plant (NPP), an experimental campaign using plasma and oxyacetylene metal cutting processes has been performed and applied to plates and tubes exposed to the coolant steam of the reactor. The plant (Boiling Water Reactor, 870 MWe) was designed and built in the 70's, and it was fully operating by 1981 to 1986 being shut down after 1987 Italy's poll that abrogated nuclear power based on U235 fission. The campaign concerns no activated materials, even if the analyses have been performed of by use contaminated components under the free release level, not yet taking into account radioactivity. In this paper, the parameters related to inhalable aerosol, solid and volatile residuals production have been, studied during hot processes which applies the same characteristics of the cutting in field for the dismantling programs of Caorso NPP. The technical parameters such as cutting time and cutting rate vs. pipe diameter/thickness/schedule or plate thickness for ferritic alloys and the emissions composition coming from the sectioning are also reported. The results underline the sort of trouble that can emerge in the cutting processes, in particular focusing on the effects comparison between the two cutting processes and the chemical composition of powders captured by filtering the gaseous emission. Some preliminary considerations on methodology to be used during the dismantling have been presented. (authors)

  4. GLOVEBOX DISMANTLEMENT AND EQUIPMENT PROTECTION IN CONTAMINATED ENVIRONMENTS

    SciTech Connect

    Kitamura, Akihiro; Stallings, Ellen; Wilburn, Dianne W.

    2003-02-27

    It has been revealed from the experiences of Decontamination and Decommissioning (D&D) activities that even a small improvement in performance can result in significant risk reduction and cost savings. For example, Race Scan Ear Mic System, which was originally developed for communications between racecar drivers and crews in loud environments, has been successfully applied to D&D work and proved to enhance worker safety and communications. Glovebox dismantlement is an important and costly process in D&D activities of nuclear facilities. Adequate decontamination and size reduction of the gloveboxes are especially important in this activity because they have the potential to reduce risks and costs significantly. This paper presents some simple approaches to support D&D tasks and discusses their potential advantages. Examples discussed include: Repeated shear wiping of large pipes and ducts; Application of thin layers on radiological counters for uninterrupted use; and Partial use of robotics for glovebox dismantling. The paper also discusses schematics for protecting equipment interiors and/or glovebox inner surfaces from contamination, which may result in significant savings and waste minimization upon future dismantlement. Examples discussed include: Smart coating for contamination prevention; and Protecting equipment by geometrically simple cover.

  5. Implementing robotics in the Department of Energy Dismantlement Program

    SciTech Connect

    Jones, A.T.

    1997-12-31

    Since the end of the cold war, as our nuclear stockpile has decreased, the Department of Energy (DOE) has been working rapidly to safely dismantle weapons returned by the military. In order to be retired, weapons must be returned to the Pantex Plant in Amarillo, Texas. There they are reduced to their component parts. Although many of these parts are not hazardous, some, including certain explosive assemblies and radioactive materials, are sufficiently hazardous so that special handling systems are necessary. This paper will describe several of these systems developed by Sandia for Pantex and their technical basis.

  6. Remote Fiber Laser Cutting System for Dismantling Glass Melter - 13071

    SciTech Connect

    Mitsui, Takashi; Miura, Noriaki; Oowaki, Katsura; Kawaguchi, Isao; Miura, Yasuhiko; Ino, Tooru

    2013-07-01

    Since 2008, the equipment for dismantling the used glass melter has been developed in High-level Liquid Waste (HLW) Vitrification Facility in the Japanese Rokkasho Reprocessing Plant (RRP). Due to the high radioactivity of the glass melter, the equipment requires a fully-remote operation in the vitrification cell. The remote fiber laser cutting system was adopted as one of the major pieces of equipment. An output power of fiber laser is typically higher than other types of laser and so can provide high-cutting performance. The fiber laser can cut thick stainless steel and Inconel, which are parts of the glass melter such as casings, electrodes and nozzles. As a result, it can make the whole of the dismantling work efficiently done for a shorter period. Various conditions of the cutting test have been evaluated in the process of developing the remote fiber cutting system. In addition, the expected remote operations of the power manipulator with the laser torch have been fully verified and optimized using 3D simulations. (authors)

  7. 48 CFR 46.313 - Contracts for dismantling, demolition, or removal of improvements.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Contracts for dismantling, demolition, or removal of improvements. 46.313 Section 46.313 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION CONTRACT MANAGEMENT QUALITY ASSURANCE Contract Clauses 46.313 Contracts for dismantling, demolition, or removal...

  8. Mock-up Test of Remote Controlled Dismantling Apparatus for Large-sized Vessels

    SciTech Connect

    Kimura, M.; Myodo, M.; Okane, S.; Miyajima, K.

    2002-02-26

    The remote dismantling apparatus, which is equipped with multi-units for functioning of washing, cutting, collection of cut pieces and so on, has been constructed to dismantle the large-sized vessels in the JAERI's Reprocessing Test Facility (JRTF). The apparatus has five-axis movement capability and its operation is performed remotely. The mock-up tests were performed to evaluate the applicability of the apparatus to actual dismantling activities by using the mock-ups of LV-3 and LV-5 in the facility. It was confirmed that each unit was satisfactory functioned by remote operation. Efficient procedure for dismantling the large-sized vessel was studied and various data were obtained from the mock-up tests. This apparatus was found to be applicable for the actual dismantling activity in JRTF.

  9. Auditing Clinical Outcomes after Introducing Off-Licence Prescribing of Atypical Antipsychotic Melperone for Patients with Treatment Refractory Schizophrenia

    PubMed Central

    Röhricht, Frank; Gadhia, Seema; Alam, Rinku; Willis, Melissa

    2012-01-01

    Aims and Method. To evaluate the practical utility of off-licence prescribing and clinical outcomes of treatment with atypical antipsychotic Melperone. Method: Prospective data collection on patient's clinical characteristics and outcomes. Results. 17 patients with a diagnosis of refractory schizophrenia were identified as suitable for off-license prescribing of Melperone and commenced treatment (13 were previously treated with Clozapine). Seven of those currently remain on Melperone (41%), and for six patents, the BPRS symptom scores reduced significantly over time (24–61%) additionally patients displayed improvements of their quality of life. Six patients were discontinued due to noncompliance and/or side effects. Melperone was ineffective in the other four patients. Clinical Implications. The example of a small group of patients responding well to a comparably safe and inexpensive atypical antipsychotic with favourable side effect profile should encourage clinicians to use this tool as third-line treatment and to conduct more systematic clinical research. PMID:22566771

  10. Dismantling of Evaporators by Laser Cutting Measurement of Secondary Emissions

    SciTech Connect

    Pilot, Guy; Fauvel, Sylvain; Gosse, Xavier; De Dinechin, Guillaume

    2006-07-01

    In order to dismantle the evaporators of an obsolete reprocessing plant in Marcoule, studies were carried out by IRSN (Institut de Radioprotection et de Surete Nucleaire) / DSU/SERAC in cooperation with CEA (power laser group) on the laser cutting of steel structures, on the request of COGEMA (now AREVA NC) /Marcoule (UP1 dismantling project manager) and CEA/UMODD (UP1 dismantling owner). The aim of these studies was: - to quantify and to characterize the secondary emissions produced by Nd-YAG laser cutting of Uranus 65 steel pieces representative of UP1 evaporator elements and to examine the influence of different parameters, - to qualify a pre-filtration technique and particularly an electrostatic precipitator, - to compare the Nd-YAG used with other cutting tools previously studied. The experiments, which took place in a 35 m{sup 3} ventilated cutting cell, allow to underline the following points: for the Uranus 65 steel, the sedimented dross, the deposits on the walls of the cutting cell and the aerosols drawn in the ventilation exhaust duct ({approx} 275 m{sup 3}/h), represent respectively between 92% and 99%, between 0.01% and 0.25% and between 1% and 8% of the total collected mass, the attached slag varies much from one configuration to the other and can sometimes amount to a relatively important fraction of the total mass, the kerves vary from 2 mm up to 7 mm for the Uranus 65 steel plates (thickness: 13.8 mm for the single plate and 12.8 + 3.5 mm for the double plate), the exhausted aerosol mass per cut length (g/m) decreases with the cutting speed, varies neither with the stand-off nor with the gas pressure, is dependent upon the gas nature (for the double plate), increases with the laser power, is strongly affected by the nature of the steel (stainless steel or mild steel) and is independent upon the plate position, the size distribution of aerosols is multimodal with a main mode often around 0.45 {mu}m, the electrostatic precipitator has been a

  11. Cost Savings through Innovation in Decontamination, Decommissioning, and Dismantlement

    SciTech Connect

    Neal A. Yancey

    2003-02-27

    The United States Department of Energy (DOE) continually seeks safer and more cost effective technologies for the decontamination and decommissioning (D&D) of nuclear facilities. The Deactivation and Decommissioning Focus Area (DDFA) of the DOE's Office of Science and Technology (OST) sponsored large-scale demonstration and deployment projects (LSDDPs) to help bring new technologies into the D&D programs. The Idaho National Engineering and Environmental Laboratory (INEEL) LSDDP generated a list of needs defining specific problems where improved technologies could be incorporated into ongoing D&D tasks. The needs fell into 5 major categories--characterization, dismantlement, safety, material dispositioning, and decontamination. Technologies were carefully selected that provide a large benefit for a small investment. The technologies must provide significant improvements in cost, safety, radiation exposure, waste volume reduction, or schedule savings and widely applicable throughout the DOE complex. The LSDDP project provided training for the new technologies and worked with technology suppliers to resolve any questions that arose. Since 1998, 26 technologies have been demonstrated or deployed through the LSDDP for the D&D program at the INEEL. Of the 26 demonstrated and deployed technologies, 14 were in characterization, 3 were in decontamination, 4 were in dismantlement, 3 were in safety, and 2 were in material dispositioning. To promote the use of these technologies at other sites within the DOE complex, the LSDDP team published fact sheets, videos, technology summary reports, articles in INEEL star newspaper, posters, and maintained an internet home page on the project. As a result, additional deployments have taken place at the Hanford, Mound, Fernald, Oak Ridge, Ashtabula, and West Valley. Eight of the 26 technologies evaluated were developed in foreign countries. The technologies demonstrated have been shown to be faster, less expensive, and/or safer. The

  12. Decommissioning and Dismantling of the Floating Maintenance Base 'Lepse' - 13316

    SciTech Connect

    Field, D.; Mizen, K.

    2013-07-01

    The Lepse was built in Russia in 1934 and commissioned as a dry cargo ship. In 1961 she was re-equipped for use as a nuclear service ship (NSS), specifically a floating maintenance base (FMB), to support the operation of the civilian nuclear fleet (ice-breakers) of the USSR. In 1988 Lepse was taken out of service and in 1990 she was re-classified as a 'berth connected ship', located at a berth near the port of Murmansk under the ownership of Federal State Unitary Enterprise (FSUE) Atomflot. Lepse has special storage facilities for spent nuclear fuel assemblies (SFA) that have been used to store several hundred SFAs for nearly 40 years. High and intermediate-level liquid radioactive waste (LRW) is also present in the spent nuclear fuel assembly storage channels, in special tanks and also in the SFA cooling circuit. Many of the SFAs stored in Lepse are classified as damaged and cannot be removed using standard procedures. The removal of the SFA and LRW from the Lepse storage facilities is a hazardous task and requires specially designed tools, equipment and an infrastructure in which these can be deployed safely. Lepse is a significant environmental hazard in the North West of Russia. Storing spent nuclear fuel and high-level liquid radioactive waste on board Lepse in the current conditions is not acceptable with respect to Russian Federation health, safety and environmental standards and with international best practice. The approved concept design for the removal of the SFA and LRW and dismantling of Lepse requires that the ship be transported to Nerpa shipyard where specialist infrastructure will be constructed and equipment installed. One of the main complexities of the Project lies within the number of interested stakeholders involved in the Project. The Lepse project has been high focus on the international stage for many years with previous international efforts failing to make significant progress towards the objective of decommissioning Lepse. The Northern

  13. The 'Room within a Room' Concept for Monitored Warhead Dismantlement

    SciTech Connect

    Tanner, Jennifer E.; Benz, Jacob M.; White, Helen; McOmish, Sarah; Allen, Keir; Tolk, Keith; Weeks, George E.

    2014-12-01

    Over the past 10 years, US and UK experts have engaged in a technical collaboration with the aim of improving scientific and technological abilities in support of potential future nuclear arms control and non-proliferation agreements. In 2011 a monitored dismantlement exercise provided an opportunity to develop and test potential monitoring technologies and approaches. The exercise followed a simulated nuclear object through a dismantlement process and looked to explore, with a level of realism, issues surrounding device and material monitoring, chain of custody, authentication and certification of equipment, data management and managed access. This paper focuses on the development and deployment of the ‘room-within-a-room’ system, which was designed to maintain chain of custody during disassembly operations. A key challenge for any verification regime operating within a nuclear weapon complex is to provide the monitoring party with the opportunity to gather sufficient evidence, whilst protecting sensitive or proliferative information held by the host. The requirement to address both monitoring and host party concerns led to a dual function design which: • Created a controlled boundary around the disassembly process area which could provide evidence of unauthorised diversion activities. • Shielded sensitive disassembly operations from monitoring party observation. The deployed room-within-a-room was an integrated system which combined a number of chain of custody technologies (i.e. cameras, tamper indicating panels and enclosures, seals, unique identifiers and radiation portals) and supporting deployment procedures. This paper discusses the bounding aims and constraints identified by the monitoring and host parties with respect to the disassembly phase, the design of the room-within-a-room system, lessons learned during deployment, conclusions and potential areas of future work. Overall it was agreed that the room-within-a-room approach was effective but

  14. Dismantlement of the TSF-SNAP Reactor Assembly

    SciTech Connect

    Peretz, Fred J

    2009-01-01

    This paper describes the dismantlement of the Tower Shielding Facility (TSF)?Systems for Nuclear Auxiliary Power (SNAP) reactor, a SNAP-10A reactor used to validate radiation source terms and shield performance models at Oak Ridge National Laboratory (ORNL) from 1967 through 1973. After shutdown, it was placed in storage at the Y-12 National Security Complex (Y-12), eventually falling under the auspices of the Highly Enriched Uranium (HEU) Disposition Program. To facilitate downblending of the HEU present in the fuel elements, the TSF-SNAP was moved to ORNL on June 24, 2006. The reactor assembly was removed from its packaging, inspected, and the sodium-potassium (NaK) coolant was drained. A superheated steam process was used to chemically react the residual NaK inside the reactor assembly. The heat exchanger assembly was removed from the top of the reactor vessel, and the criticality safety sleeve was exchanged for a new safety sleeve that allowed for the removal of the vessel lid. A chain-mounted tubing cutter was used to separate the lid from the vessel, and the 36 fuel elements were removed and packaged in four U.S. Department of Transportation 2R/6M containers. The fuel elements were returned to Y-12 on July 13, 2006. The return of the fuel elements and disposal of all other reactor materials accomplished the formal objectives of the dismantlement project. In addition, a project model was established for the handling of a fully fueled liquid-metal?cooled reactor assembly. Current criticality safety codes have been benchmarked against experiments performed by Atomics International in the 1950s and 1960s. Execution of this project provides valuable experience applicable to future projects addressing space and liquid-metal-cooled reactors.

  15. PERMIT COMPLIANCE SYSTEM (PCS)

    EPA Science Inventory

    The Permit Compliance System (PCS) is a computerized management information system which contains data on National Pollutant Discharge Elimination System (NPDES) permit-holding facilities. PCS keeps extensive records on more than 65,000 active water-discharge permits on sites loc...

  16. GENERAL PERMITS DATABASE

    EPA Science Inventory

    Resource Purpose:This database was used to provide permit writers with a library of examples for writing general permits. It has not been maintained and is outdated and will be removed. Water Permits Division is trying to determine whether or not to recreate this databas...

  17. Decision Analysis Science Modeling for Application and Fielding Selection Applied to Equipment Dismantlement Technologies

    SciTech Connect

    Ebadian, M.A.; Lagos, L.E.

    1998-01-01

    The dismantlement of radioactively contaminated process equipment is a major concern during the D and D process. As buildings undergo the D and D process, metallic equipment contaminated with radionuclides such as uranium and plutonium must be dismantled before final disposal.The primary objective for equipment dismantlement is to reduce the potential for personnel and environmental exposure to contaminants during the decommissioning of the nuclear facility. The selection of the appropriate technologies to meet the dismantlement objectives for a given site is a difficult process in the absence of comprehensive and comparable data. Choosing the wrong technology could result in increased exposure of personnel to contaminants and an increase in D and D project costs. Innovative technologies are being developed with the goal of providing safer and more cost-effective alternatives that generate less secondary waste, thereby decreasing the operating costs for dismantlement. During the development and implementation process, performance indicators for the success of these technologies must be reviewed to ensure that these aims are being met. This project provides a mechanism for the assessment of innovative and commercially available nuclear and non-nuclear technologies for equipment dismantlement.

  18. DIRECT DISMANTLING OF REPROCESSING PLANT CELLS THE EUREX PLANT EXPERIENCEe2d12c

    SciTech Connect

    Gili, M.; Troiani, F.; Risoluti, P.

    2003-02-27

    After finishing the reprocessing campaigns in 1970-1983, the EUREX pilot reprocessing plant of ENEA Saluggia Research Center started into a new phase, aiming to materials and irradiated fuel systemation and radioactive wastes conditioning. In 1997 the project ''CORA'' for a vitrification plant for the high and intermediate liquid radioactive wastes started. The ''CORA'' plant will be hosted in some dismantled cells of the EUREX plant, reusing many of the EUREX plant auxiliary systems, duly refurbished, saving money and construction time and avoiding a new nuclear building in the site. Two of the cells that will be reused were part of the EUREX chemical process (solvent recovery and 2nd extraction cycle) and the components were obviously internally contaminated. In 2000 the direct (hands-on) dismantling of one of them started and has been completed in summer 2002; the second one will be dismantled in the next year and then the ''CORA'' plant will be assembled inside the cells. Special care w as taken to avoid spread of contamination in the cells, where ''CORA'' installation activities will start in the next years, during the dismantling process The analysis of data and results collected during the dismantling of the first cell shows that direct dismantling can be achieved with careful choice of tools, procedures and techniques, to reduce volumes of wastes to be disposed and radiological burden.

  19. Iraq nuclear facility dismantlement and disposal project (NDs Project).

    SciTech Connect

    Cochran, John Russell

    2010-06-01

    The Al Tuwaitha nuclear complex near Baghdad contains a number of facilities from Saddam Hussan's nuclear weapons program. Past military operations, lack of upkeep and looting have created an enormous radioactive waste problem at the Al Tuwaitha complex, which contains various, uncharacterized radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals that must be constantly guarded. Iraq has never had a radioactive waste disposal facility and the lack of a disposal facility means that ever increasing quantities of radioactive material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS is funding the IAEA to provide technical assistance via Technical Cooperation projects. Program coordination will be provided by the DOS, consistent with GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for implementation of the NDs Program.

  20. 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)

  1. Rosie: A mobile workstation for decontamination and dismantlement operations

    SciTech Connect

    1994-12-31

    RedZone Robotics, Inc. and Carnegie Mellon University`s Field Robotics Center have undertaken a contract to develop a next-generation worksystem for decommissioning and dismantlement tasks in Department of Energy (DOE) facilities. Currently, the authors are in the second phase of this three phase effort and are completing the design of the worksystem. Within this project RedZone is designing and fabricating a worksystem: Rosie. Rosie will include a locomotor, heavy manipulator, control center, and control system for robot operation. The locomotor is an omni-directional platform with tether management and hydraulic power capabilities. The heavy manipulator is a high-payload, long-reach system to deploy tools into the work area. The heavy manipulator will be capable of deploying systems such as the Dual-Arm Work Module--a five degree-of-freedom platform supporting two highly dexterous manipulators--or a single manipulator for performing simpler, less dexterous tasks. Rosie will be telerobotic to the point of having servo-controlled motions which can be operated and coordinated through the control center. This report describes the design of the systems. In phase three Rosie will be radiation-hardened and perform a demonstration in a contaminated facility.

  2. Rosie: A mobile worksystem for decontamination and dismantlement operations

    SciTech Connect

    Thompson, B.R.; Conley, L.

    1996-05-01

    RedZone Robotics, Inc. and Carnegie Mellon University`s Field Robotics Center have undertaken a contract to develop a next-generation worksystem for decommissioning and dismantlement tasks in Department of Energy (DOE) facilities. Currently, the authors are closing the second phase of this three phase effort and have completed the design and fabrication of the worksystem: Rosie. Rosie includes a locomotor, heavy manipulator, control center, and control system for robot operation. The locomotor is an omni-directional platform with tether management and hydraulic power capabilities. The heavy manipulator is a high-payload, long-reach system intended to deploy tools into the work area. The heavy manipulator is capable of deploying systems such as the Dual-Arm Work Module--a five degree-of-freedom platform supporting two highly dexterous manipulators--or a single manipulator for performing simpler, less dexterous tasks. Rosie is telerobotic to the point of having servo-controlled motions which can be operated and coordinated through the control center.

  3. Experience making mixed oxide fuel with plutonium from dismantled weapons

    SciTech Connect

    Blair, H.T.; Ramsey, K.B.

    1995-12-31

    Mixed depleted UO{sub 2} and PuO{sub 2} (MOX) pellets prototypic of fuel proposed for use in commercial power reactors were made with plutonium recovered from dismantled weapons. We characterized plutonium dioxide powders that were produced at the Los Alamos and Lawrence Livermore National Laboratories (LANL and LLNL) using various methods to recover the plutonium from weapons parts and to convert It to oxide. The gallium content of the PUO{sub 2} prepared at LANL was the same as in the weapon alloy while the content of that prepared at LLNL was less. The MOX was prepared with a five weight percent plutonium content. We tested various MOX powders milling methods to improve homogeneity and found vibratory milling superior to ball milling. The sintering behavior of pellets made with the PuO{sub 2} from the two laboratories was similar. We evaluated the effects of gallium and of erbium and gadolinium, that are added to the MOX fuel as deplorable neutron absorbers, on the pellet fabrication process and an the sintered pellets. The gallium content of the sintered pellets was <10 ppm, suggesting that the gallium will not be an issue in the reactor, but that it will be an Issue in the operation of the fuel fabrication processing equipment unless it is removed from the PuO{sub 2} before it is blended with the UO{sub 2}.

  4. Microglia: Dismantling and rebuilding circuits after acute neurological injury

    PubMed Central

    Ziebell, Jenna M.; Adelson, P. David; Lifshitz, Jonathan

    2014-01-01

    The brain is comprised of neurons and its support system including astrocytes, glial cells and microglia, thereby forming neurovascular units. Neurons require support from glial cells to establish and maintain functional circuits, but microglia are often overlooked. Microglia function as the immune cell of the central nervous system, acting to monitor the microenvironment for changes in signaling, pathogens and injury. More recently, other functional roles for microglia within the healthy brain have been identified, including regulating synapse formation, elimination and function. This review aims to highlight and discuss these alternate microglial roles in the healthy and in contrast, diseased brain with a focus on two acute neurological diseases, traumatic brain injury and epilepsy. In these conditions, microglial roles in synaptic stripping and stabilization as part of neuronal:glial interactions may position them as mediators of the transition between injury-induced circuit dismantling and subsequent reorganization. Increased understanding of microglia roles could identify therapeutic targets to mitigate the consequences of neurological disease. PMID:24733573

  5. DISMANTLING OF THE REACTOR BLOCK OF THE FRJ-1 RESEARCH REACTOR (MERLIN)

    SciTech Connect

    Stahn, B.; Matela, K.; Zehbe, C.; Poeppinghaus, J.; Cremer, J.

    2003-02-27

    This report describes the past procedure in dismantling the reactor block of the FRJ-1 research reactor (MERLIN). Furthermore, it gives an outlook on future activities up to the final removal of the reactor block. MERLIN is an abbreviation for Medium Energy Research Light Water Moderated Industrial Nuclear Reactor. The FRJ-1 (MERLIN) was shut down in 1985 and the fuel elements removed from the facility. After dismantling the coolant loops and removing the reactor tank internals with subsequent draining of the reactor tank water, the first activities for dismantling the reactor block were carried out in summer 2001. The relevant license was granted in late July 2001 by the licensing authority specifying 8 incidental provisions. After dismantling the reactor extension (gates of the thermal columns and steel platforms surrounding the reactor block), a heavy-load platform including a casing around the reactor block was constructed. Two ventilation systems with a volume flow of 10,000 and 2 ,000 m3/h will, moreover, serve to avoid a spread of contamination. The reactor block will be dismantled in three phases divided according to upper, central and bottom sections. Dismantling the upper section started in August 2002. This section as well as the bottom section can probably be completely measured for clearance. For this reason, the activities have so far been carried out manually using mechanical and thermal techniques. The central section will probably have to be largely disposed of as radioactive waste. This is the region of the former reactor core in which the experimental devices are also integrated. Most of this work will probably have to be carried out by remote handling. More than 80 % of the dismantled materials of the reactor block can probably be measured for clearance. For this purpose, a clearance measurement device was taken into operation in the FRJ-1. On this occasion, the limits of clearance measurement have become evident. For concrete, which constitutes

  6. CCS Project Permit Acquisition Protocols

    SciTech Connect

    Lee, Si-Yong; Zaluski, Wade; Matthews, Vince; McPherson, Brian

    2013-06-30

    Geologic carbon storage projects require a vast range of permits prior to deployment. These include land-access permits, drilling permits, seismic survey permits, underground injection control permits, and any number of local and state permits, depending on the location of the project. For the “Characterization of Most Promising Sequestration Formations in the Rocky Mountain Region” (RMCCS) project in particular, critical permits included site access permits, seismic survey permits, and drilling permits for the characterization well. Permits for these and other activities were acquired either prior to or during the project.

  7. A Rinsing Effluent Evaporator for Dismantling Operations - 13271

    SciTech Connect

    Rives, Rachel

    2013-07-01

    Between 1958 and 1997, the UP1 plant at Marcoule - located in the south of France - reprocessed and recycled nearly 20,000 MT of used fuel from special defense applications reactors, as well as fuel from the first generation of electricity generating reactors in France (natural uranium fuel, CO{sub 2}-cooled, graphite-moderated). Decommissioning and Dismantling of the UP1 plant and its associated units started in 1998. Since 2005, the UP1 facility has been operated by AREVA as the Marcoule Management and Operation contractor for French Atomic Energy Commission (CEA). An important part of this decommissioning program deals with the vitrification facility of Marcoule. This facility includes 20 tanks devoted to interim storage of highly active solutions, prior to vitrification. In 2006, a rinsing program was defined as part of the tank cleanup strategy. The main objective of the rinsing phases was to decrease activity in order to limit the volume of 'long-life active' waste produced during the decommissioning operations, so the tanks can be dismantled without the need of remote operations. To enable this rinsing program, and anticipating large volumes of generated effluent, the construction of an evaporation unit proved to be essential. The main objective of this unit was to concentrate the effluent produced during tank rinsing operations by a factor of approximately 10, prior to it being treated by vitrification. The evaporator design phase was launched in September 2006. The main challenge for the Project team was the installation of this new unit within a nuclear facility still in operation and in existing compartments not initially designed for this purpose. Cold operating tests were completed in 2008, and in May 2009, the final connections to the process were activated to start the hot test phase. During the first hot test operations performed on the first batches of clean-up effluent, the evaporator had a major operating problem. Extremely large quantities of

  8. Working in tandem: The contribution of remedial programs and roadside licence suspensions to drinking and driving deterrence in Ontario.

    PubMed

    Ma, Tracey; Byrne, Patrick A; Haya, Maryam; Elzohairy, Yoassry

    2015-12-01

    In 1998, Ontario implemented a remedial program called "Back On Track" (BOT) for individuals convicted of alcohol-impaired driving. Drivers convicted before October 2000 were exposed to a single-component program ("Edu BOT"); those convicted after participated in a multi-component program ("Full BOT"). We evaluated the impact of BOT, and the preceding 90-day roadside licence suspension, on drinking and driving recidivism, an outcome yet to be examined, using population-wide driver records. A Chi Square Test was used to compare the three-year cumulative incidence of recidivism between three historically-defined cohorts: No BOT, Edu BOT, and Full BOT. Stratified analyses by completion status and by age were also conducted. Analyses of the roadside suspension were conducted using an interrupted time series approach based on segmented Poisson/negative binomial regression. The roadside suspension was associated with a 65.2% reduction in drinking driving recidivism. In combination with indefinite suspensions for non-completion, the BOT program was also associated with a 21% decrease in drinking and driving recidivism in the three years following a CCC driving prohibition, from 8.5% to 6.7%. This reduction cannot be explained by pre-existing trends in recidivism. Conversion of the BOT program from the single-component version to the multi-component program further reduced the three-year cumulative incidence of recidivism to 5.5% (a total reduction of 35% from pre-BOT). Results provide strong converging evidence that remedial alcohol education/treatment programs in combination with other sanctions can produce substantial increases in road safety. PMID:26476575

  9. The CAA Permit Review Process

    SciTech Connect

    Hyre, R.A.

    1995-06-01

    In the near future, all existing major sources will be required to submit an air permit application to the state or the Environmental Protection Agency (EPA) for review. This report details the permit review process, including information on state, EPA, affected states, judicial, and public review. It will also describe permit renewal, operational flexibility, off-permit changes, permit revisions, and permit reopenings.

  10. Licence to stun

    NASA Astrophysics Data System (ADS)

    Wilkinson, David

    2011-09-01

    In the hands of police officers all over the world, less-lethal weapons are increasingly filling the gap between shouting "Stop!" at suspects and shooting them dead. But do they work? And are they safe?

  11. Cutting by a high power laser at a long distance without an assist gas for dismantling

    NASA Astrophysics Data System (ADS)

    Tahmouch, G.; Meyrueis, P.; Grandjean, P.

    1997-09-01

    As the applications of laser processing progress, new fields of use are being investigated, including dismantling with power lasers. To fulfil our dismantling requirements we propose a new laser method that we have called the laser dismantling (LD) process. This cutting method uses a high-power laser at a long distance, without an assist gas, and with a focal length of the system of 1 m to 10 m. Precision and accuracy in the process are not the same as for laser cutting for production and assembly. The first application of the laser dismantling process, on which we demonstrate our method, is the dismantling of obsolete nuclear plants with remote controlled, or automatic, robots in irradiated environments. For our demonstrator, the beam from a Nd:YAG laser was focused by a multimode optical fibre. The objectives of this paper are: to discuss the criteria for determining the theoretical feasibility of LD; to discuss issues related to future industrial implementation by introducing the process's basic principles; and to compare LD with classical laser processing, which differs not only in the consideration of cutting quality and speed, but also in the cutting irregularities that could be accepted.

  12. DECISION ANALYSIS SCIENCE MODELING FOR APPLICATION AND FIELDING SELECTION APPLIED TO EQUIPMENT DISMANTLEMENT TECHNOLOGIES

    SciTech Connect

    M.A. Ebadian, Ph.D.

    1999-01-01

    The dismantlement of radioactively contaminated process equipment is a major concern during the D&D process. There are an estimated 1,200 buildings in the DOE-EM complex that will require the dismantlement of equipment and various metal structures. As buildings undergo the D&D process, this metallic equipment contaminated with radionuclides such as uranium and plutonium must be size-reduced before final disposal. A single information source comparing dismantlement technologies in the areas of safety, cost, and performance is needed by DOE managers and is not currently available. The selection of the appropriate technologies to meet the dismantlement objectives for a given site is a difficult process in the absence of comprehensive and comparable data. Choosing the wrong technology could result in increased exposure of personnel to contaminants and an increase in D&D project costs. The purpose of this investigation was to evaluate commercially available and innovative technologies for equipment dismantlement and provide a comprehensive source of information to the D&D community in the areas of technology performance, cost, and health and safety.

  13. Dismantling of alpha contaminated obsolete installations and glove boxes on the IRMM site in Geel (Belgium)

    SciTech Connect

    Cretskens, Pieter; Lenie, Koen; Melis, Gustaaf

    2007-07-01

    At the Institute for Reference Materials and Measurements (European commission, Joint Research Centre, IRMM) a dismantling campaign of obsolete installations and glove boxes has been carried out in 2005. There were various reasons for their removal. Some large installations did not meet modern safety standards, other installations were worn out and expected to cause a radioactive contamination risk in the future. The main goal was to create as less waste as possible by extensive contamination checks and by decontamination if necessary. For the glove boxes, decontamination was not possible. A controlled area was set up around the installation to be dismantled in order to prevent spreading of contamination from dust and dirt. This was only possible for the 'minor' contaminated installations. The dismantling campaign of the glove boxes was carried out by using tents of two types depending the contamination inside the glove boxes. The most common glove boxes were dismantled in a tent constructed with hard surfaced polycarbonate plates (ventilated cell). For glove boxes with higher contamination, the same principle was used but with a second 'glove box tent' inside (ventilated glove tent). The purpose of this project was to learn from the experience of this campaign which gave the ability to make estimates of future radioactive waste or classic waste that could be expected from dismantled installations. (authors)

  14. Experience with Dismantling of the Analytic Cell in the JRTF Decommissioning Program

    SciTech Connect

    Annoh, Akio; Nemoto, Koichi; Tajiri, Hideo; Saito, Keiichiro; Miyajima, Kazutoshi; Myodo, Masato

    2003-02-27

    The analytic cell was mainly used for process control analysis of the reprocessing process and for the measurement of fuel burn up ratio in JAERI's Reprocessing Test Facility (JRTF). The analytic cell was a heavy shielded one and equipped with a conveyor. The cell was alpha and beta(gamma)contaminated. For dismantling of analytic cells, it is very important to establish a method to remove the heavy shield safely and reduce the exposure. At first, a green house was set up to prevent the spread out of contamination, and next, the analytic cell was dismantled. Depending on the contamination condition, the workers wore protective suits such as air ventilated-suits for prevention of internal exposure and vinyl chloride aprons, lead aprons in order to reduce external exposure. From the work carried out, various data such as needed manpower for the activities, the collective dose of workers by external exposure, the amount of radioactive wastes and the relation between the weight of the shield and its dismantling efficiency were obtained and input for the database. The method of dismantling and the experience with the dismantling of the analytic cell in the JRTF, carried out during 2001 and 2002, are described in this paper.

  15. Rockwell International Hot Laboratory decontamination and dismantlement interim progress report 1987-1996

    SciTech Connect

    1997-05-06

    OAK A271 Rockwell International Hot Laboratory decontamination and dismantlement interim progress report 1987-1996. The Rockwell International Hot Laboratory (RIHL) is one of a number of former nuclear facilities undergoing decontamination and decommissioning (D&D) at the Santa Susana Field Laboratory (SSFL). The RIHL facility is in the later stages of dismantlement, with the final objective of returning the site location to its original natural state. This report documents the decontamination and dismantlement activities performed at the facility over the time period 1988 through 1996. At this time, the support buildings, all equipment associated with the facility, and the entire above-ground structure of the primary facility building (Building 020) have been removed. The basement portion of this building and the outside yard areas (primarily asphalt and soil) are scheduled for D&D activities beginning in 1997.

  16. Dismantling of Loop-Type Channel Equipment of MR Reactor in NRC 'Kurchatov Institute' - 13040

    SciTech Connect

    Volkov, Victor; Danilovich, Alexey; Zverkov, Yuri; Ivanov, Oleg; Kolyadin, Vyacheslav; Lemus, Alexey; Pavlenko, Vitaly; Semenov, Sergey; Fadin, Sergey; Shisha, Anatoly; Chesnokov, Alexander

    2013-07-01

    In 2009 the project of decommissioning of MR and RTF reactors was developed and approved by the Expert Authority of the Russian Federation (Gosexpertiza). The main objective of the decommissioning works identified in this project: - complete dismantling of reactor equipment and systems; - decontamination of reactor premises and site in accordance with the established sanitary and hygienic standards. At the preparatory stage (2008-2010) of the project the following works were executed: loop-type channels' dismantling in the storage pool; experimental fuel assemblies' removal from spent fuel repositories in the central hall; spent fuel assembly removal from the liquid-metal-cooled loop-type channel of the reactor core and its placement into the SNF repository; and reconstruction of engineering support systems to the extent necessary for reactor decommissioning. The project assumes three main phases of dismantling and decontamination: - dismantling of equipment/pipelines of cooling circuits and loop-type channels, and auxiliary reactor equipment (2011-2012); - dismantling of equipment in underground reactor premises and of both MR and RTF in-vessel devices (2013-2014); - decontamination of reactor premises; rehabilitation of the reactor site; final radiation survey of reactor premises, loop-type channels and site; and issuance of the regulatory authorities' de-registration statement (2015). In 2011 the decommissioning license for the two reactors was received and direct MR decommissioning activities started. MR primary pipelines and loop-type facilities situated in the underground reactor hall were dismantled. Works were also launched to dismantle the loop-type channels' equipment in underground reactor premises; reactor buildings were reconstructed to allow removal of dismantled equipment; and the MR/RTF decommissioning sequence was identified. In autumn 2011 - spring 2012 results of dismantling activities performed are: - equipment from underground rooms (No. 66, 66

  17. Remote dismantlement tasks for the CP5 reactor: Implementation, operations, and lessons learned

    SciTech Connect

    Noakes, M.W.

    1998-11-01

    This paper presents a developer`s perspective on lessons learned from one example of the integration of new prototype technology into a traditional operations environment. The dual arm work module was developed by the Robotics Technology Development Program as a research and development activity to examine manipulator controller modes and deployment options. It was later reconfigured for the dismantlement of the Argonne National Laboratory Chicago Pile {number_sign}5 reactor vessel as the crane-deployed dual arm work platform. Development staff worked along side operations staff during a significant part of the deployment to provide training, maintenance, and tooling support. Operations staff completed all actual remote dismantlement tasks. At the end of available development support funding, the Dual Arm Work Platform was turned over to the operations staff, who is still using it to complete their dismantlement tasks.

  18. RCRA post-closure permits

    SciTech Connect

    Not Available

    1993-05-01

    The Resource Conservation and Recovery Act (RCRA) requires that hazardous waste management facilities operate in accordance with permits granted by the US Environmental Protection Agency (EPA) or a State authorized to carry out the RCRA Subtitle C program. Several categories of permits (including treatment, storage, and disposal permits; research, development, and demonstration permits; post-closure permits; emergency permits; permits-by-rule; and trial burn and land treatment demonstration permits) are issued under the RCRA Subtitle C program. This Information Brief focuses on post-closure permitting requirements under 40 CFR 270.1(c).

  19. Health and Safety Considerations Associated with Sodium-Cooled Experimental Nuclear Fuel Dismantlement

    SciTech Connect

    Carvo, Alan E.

    2015-04-01

    Between the mid-1970s and the mid-1980s Sandia National Laboratory constructed eleven experimental assemblies to simulate debris beds formed in a sodium-cooled fast breeder reactor. All but one of the assemblies were irradiated. The experimental assemblies were transferred to the Idaho National Laboratory (INL) in 2007 and 2008 for storage, dismantlement, recovery of the uranium for reuse in the nuclear fuel cycle, and disposal of unneeded materials. This paper addresses the effort to dismantle the assemblies down to the primary containment vessel and repackage them for temporary storage until such time as equipment necessary for sodium separation is in place.

  20. Mechanism for coordination between the collector and the dismantler in a reverse supply chain

    NASA Astrophysics Data System (ADS)

    Pochampally, Kishore K.; Gupta, Surendra M.

    2005-11-01

    The growing desire of consumers to acquire the latest technology (both at home and in the workplace), along with the rapid technological development of new products, has led to a new environmental problem: waste. The only way to tackle this problem is design and implementation of reverse supply chains. Implementation of an efficient reverse supply chain requires coordination among a number of parties, such as the collector, the dismantler, the shredder, and the recycler. In this paper, we identify four different scenarios of homogeneous and heterogeneous products, and formulate some potential interactions between the collector and the dismantler, for each of those scenarios.

  1. Comparison of ship dismantling processes in India and the U.S.

    NASA Astrophysics Data System (ADS)

    Ahluwalia, Rashpal S.; Sibal, Pooja; Govindarajulu, Sriram

    2004-03-01

    This paper compares ship-dismantling processes in India and the U.S. The information for India was collected during an informal visit to the ship dismantling sites in Alang, India. The information for the U.S. was obtained from the MARAD report. For a 10,000-ton passenger ship, the Indian contractor makes a profit of about 24% compared to a loss of about 15% in the U.S. The loss in the US is primarily due to high labor costs, compliance to safety and health regulations and lack of market for used components and scrap metal.

  2. 49 CFR 1242.51 - Dismantling retired property and depreciation (accounts XX-27-39 and 62-27-00).

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 49 Transportation 9 2012-10-01 2012-10-01 false Dismantling retired property and depreciation (accounts XX-27-39 and 62-27-00). 1242.51 Section 1242.51 Transportation Other Regulations Relating to... FOR RAILROADS 1 Operating Expenses-Equipment § 1242.51 Dismantling retired property and...

  3. 49 CFR 1242.51 - Dismantling retired property and depreciation (accounts XX-27-39 and 62-27-00).

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 49 Transportation 9 2010-10-01 2010-10-01 false Dismantling retired property and depreciation (accounts XX-27-39 and 62-27-00). 1242.51 Section 1242.51 Transportation Other Regulations Relating to... FOR RAILROADS 1 Operating Expenses-Equipment § 1242.51 Dismantling retired property and...

  4. Louisiana Title V General Permits

    SciTech Connect

    Boyer, B.E.; Neal, T.L.

    1995-12-31

    Title V of the Federal Clean Air Act Amendments of 1990 requires federal operating permits for all major sources of air pollution. In 1992, Title 40, Part 70 of the Code of Federal Regulations (40 CFR Part 70) codified the law s requirements. These federal regulations, entitled Operating Permit Program, define the minimum requirements for state administered operating permit programs. The intent of Title V is to put into one document all requirements of an operating permit. General Permits for oil and gas facilities may be preferred if the facility can comply with all permit requirements. If greater flexibility than allowed by the General Permit is required, then the facility should apply for an individual Title V permit. General Permits are designed to streamline the permitting process, shorten the time it takes to obtain approval for initial and modified permits. The advantages of the General Permit include reduced paperwork and greater consistency because the permits are standardized. There should be less uncertainty because permit requirements will be known at the time of application. Approval times for Initial and modified General Permits should be reduced. Lengthy public notice procedures (and possible hearings) will be required for only the initial approval of the General Permit and not for each applicant to the permit. A disadvantage of General Permits is reduced flexibility since the facility must comply with the requirements of a standardized permit.

  5. Hanford Facility RCRA permit handbook

    SciTech Connect

    1996-03-01

    Purpose of this Hanford Facility (HF) RCRA Permit Handbook is to provide, in one document, information to be used for clarification of permit conditions and guidance for implementing the HF RCRA Permit.

  6. A novel dismantling process of waste printed circuit boards using water-soluble ionic liquid.

    PubMed

    Zeng, Xianlai; Li, Jinhui; Xie, Henghua; Liu, Lili

    2013-10-01

    Recycling processes for waste printed circuit boards (WPCBs) have been well established in terms of scientific research and field pilots. However, current dismantling procedures for WPCBs have restricted the recycling process, due to their low efficiency and negative impacts on environmental and human health. This work aimed to seek an environmental-friendly dismantling process through heating with water-soluble ionic liquid to separate electronic components and tin solder from two main types of WPCBs-cathode ray tubes and computer mainframes. The work systematically investigates the influence factors, heating mechanism, and optimal parameters for opening solder connections on WPCBs during the dismantling process, and addresses its environmental performance and economic assessment. The results obtained demonstrate that the optimal temperature, retention time, and turbulence resulting from impeller rotation during the dismantling process, were 250 °C, 12 min, and 45 rpm, respectively. Nearly 90% of the electronic components were separated from the WPCBs under the optimal experimental conditions. This novel process offers the possibility of large industrial-scale operations for separating electronic components and recovering tin solder, and for a more efficient and environmentally sound process for WPCBs recycling. PMID:23910241

  7. Chemical oxygen-iodine laser (COIL) for the dismantlement of nuclear facilities

    NASA Astrophysics Data System (ADS)

    Hallada, Marc R.; Seiffert, Stephan L.; Walter, Robert F.; Vetrovec, John

    2000-05-01

    The dismantlement of obsolete nuclear facilities is a major challenge for both the US Department of Energy and nuclear power utilities. Recent demonstrations have shown that lasers can be highly effective for size reduction cutting, especially for the efficient storage and recycling of materials. However, the full benefits of lasers can only be realized with high average power beams that can be conveniently delivered, via fiber optics, to remote and/or confined areas. Industrial lasers that can meet these requirements are not available now or for the foreseeable future. However, a military weapon laser, a Chemical Oxygen Iodine Laser (COIL), which has been demonstrated at over a hundred kilo Watts, could be adapted to meet these needs and enable entirely new industrial applications. An 'industrialized' COIL would enable rapid sectioning of thick and complex structures, such as glove boxes, reactor vessels, and steam generators, accelerating dismantlement schedules and reducing worker hazards. The full advantages of lasers in dismantlement could finally be realized with a portable COIL which is integrated with sophisticated robotics. It could be built and deployed in less than two years, breaking the paradigm of labor-intensive dismantlement operations and cutting processing times and costs dramatically.

  8. Dismantling Motivational Interviewing and Feedback for College Drinkers: A Randomized Clinical Trial

    ERIC Educational Resources Information Center

    Walters, Scott T.; Vader, Amanda M.; Harris, T. Robert; Field, Craig A.; Jouriles, Ernest N.

    2009-01-01

    Motivational interviewing (MI) is a counseling style that has been shown to reduce heavy drinking among college students. To date, all studies of MI among college students have used a format that includes a feedback profile delivered in an MI style. This study was a dismantling trial of MI and feedback among heavy-drinking college students. After…

  9. Logic and Feminist Argument: Yet Again, Can the Master's Tools Dismantle the Master's House?

    ERIC Educational Resources Information Center

    Lamb, Catherine E.

    If "logic" is defined as a means to create good reasons for accepting clear and unambiguous conclusions, then feminist instructors of composition should use it not only to dismantle traditional male notions of combative discussion, but also to build their own paradigms based on an acceptance of difference. Those feminists such as Sally Gearhart,…

  10. Deny, Distance, or Dismantle? How White Americans Manage a Privileged Identity.

    PubMed

    Knowles, Eric D; Lowery, Brian S; Chow, Rosalind M; Unzueta, Miguel M

    2014-11-01

    Social scientists have traditionally argued that whiteness-the attribute of being recognized and treated as a White person in society-is powerful because it is invisible. On this view, members of the racially dominant group have the unique luxury of rarely noticing their race or the privileges it confers. This article challenges this "invisibility thesis," arguing that Whites frequently regard themselves as racial actors. We further argue that whiteness defines a problematic social identity that confronts Whites with 2 psychological threats: the possibility that their accomplishments in life were not fully earned (meritocratic threat) and the association with a group that benefits from unfair social advantages (group-image threat). We theorize that Whites manage their racial identity to dispel these threats. According to our deny, distance, or dismantle (3D) model of White identity management, dominant-group members have three strategies at their disposal: deny the existence of privilege, distance their own self-concepts from the White category, or strive to dismantle systems of privilege. Whereas denial and distancing promote insensitivity and inaction with respect to racial inequality, dismantling reduces threat by relinquishing privileges. We suggest that interventions aimed at reducing inequality should attempt to leverage dismantling as a strategy of White identity management. PMID:26186110

  11. Exploring the Development and Dismantling of Equivalence Classes Involving Terrorist Stimuli

    ERIC Educational Resources Information Center

    Dixon, Mark R.; Rehfeldt, Ruth Anne; Zlomke, Kimberly R.; Robinson, Ashton

    2006-01-01

    The present paper describes 2 studies that present a conceptual interpretation and experimental findings involving the developing and dismantling of equivalence classes consisting of terrorist stimuli. In the first study, 8 United States citizen participants were trained to match nonterrorist stimuli to American and terrorist images. Afterwards,…

  12. 48 CFR 46.313 - Contracts for dismantling, demolition, or removal of improvements.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 48 Federal Acquisition Regulations System 1 2011-10-01 2011-10-01 false Contracts for dismantling, demolition, or removal of improvements. 46.313 Section 46.313 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION CONTRACT MANAGEMENT QUALITY ASSURANCE Contract Clauses 46.313 Contracts for...

  13. 47 CFR 63.500 - Contents of applications to dismantle or remove a trunk line.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... a trunk line. 63.500 Section 63.500 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED... Contents of Applications; Examples § 63.500 Contents of applications to dismantle or remove a trunk line... service area affected including population and general character of business of the community; (g) Name...

  14. Remotely-Controlled Shear for Dismantling Highly Radioactive Tools In Rokkasho Vitrification Facility - 12204

    SciTech Connect

    Mitsui, Takashi; Sawa, Shusuke; Sadaki, Akira; Awano, Toshihiko; Cole, Matt; Miura, Yasuhiko; Ino, Tooru

    2012-07-01

    A high-level liquid waste vitrification facility in the Japanese Rokkasho Reprocessing Plant (RRP) is right in the middle of hot commissioning tests toward starting operation in fall of 2012. In these tests, various tools were applied to address issues occurring in the vitrification cell. Because of these tools' unplanned placement in the cell it has been necessary to dismantle and dispose of them promptly. One of the tools requiring removal is a rod used in the glass melter to improve glass pouring. It is composed of a long rod made of Inconel 601 or 625 and has been highly contaminated. In order to dismantle these tools and to remotely put them in a designated waste basket, a custom electric shear machine was developed. It was installed in a dismantling area of the vitrification cell by remote cranes and manipulators and has been successfully operated. It can be remotely dismantled and placed in a waste basket for interim storage. This is a very good example of a successful deployment of a specialty remote tool in a hot cell environment. This paper also highlights how commissioning and operations are done in the Japanese Rokkasho Reprocessing Plant. (authors)

  15. Sustainable design for automotive products: dismantling and recycling of end-of-life vehicles.

    PubMed

    Tian, Jin; Chen, Ming

    2014-02-01

    The growth in automotive production has increased the number of end-of-life vehicles (ELVs) annually. The traditional approach ELV processing involves dismantling, shredding, and landfill disposal. The "3R" (i.e., reduce, reuse, and recycle) principle has been increasingly employed in processing ELVs, particularly ELV parts, to promote sustainable development. The first step in processing ELVs is dismantling. However, certain parts of the vehicle are difficult to disassemble and use in practice. The extended producer responsibility policy requires carmakers to contribute in the processing of scrap cars either for their own developmental needs or for social responsibility. The design for dismantling approach can be an effective solution to the existing difficulties in dismantling ELVs. This approach can also provide guidelines in the design of automotive products. This paper illustrates the difficulty of handling polymers in dashboards. The physical properties of polymers prevent easy separation and recycling by using mechanical methods. Thus, dealers have to rely on chemical methods such as pyrolysis. Therefore, car designers should use a single material to benefit dealers. The use of materials for effective end-of-life processing without sacrificing the original performance requirements of the vehicle should be explored. PMID:24326159

  16. Permit application modifications

    SciTech Connect

    1995-11-01

    This document contains the Permit Application Modifications for the Y-12 Industrial Landfill V site on the Oak Ridge Reservation. These modifications include the assessment of stability of the proposed Landfill V under static and loading conditions. Analyses performed include the general slope stability, veneer stability of the bottom liner and cover system, and a liquefaction potential assessment of the foundation soils.

  17. PERMITTING HAZARDOUS WASTE INCINERATORS

    EPA Science Inventory

    This publication is a compilation of information presented at a seminar series designed to address the issues that affect the issuance of hazardous waste incineration permits and to improve the overall understanding of trial burn testing. pecifically, the document provides guidan...

  18. An Evaluation of Dismantling Scenarios Using a Computer Simulation Technology for KRR-1 and 2

    SciTech Connect

    Kim, S.K.; Park, H.S.; Lee, K.W.; Oh, W.Z.; Park, J.H.

    2006-07-01

    A graphic simulation has been used to design and verify new equipment and has also been expanded to virtual prototyping technology [1{approx}5]. In the nuclear decommissioning field, this technology has been utilized to validate the design of dismantling processes and to check the interferences and collisions in dismantling scenarios. However, a graphic simulation only provides us with visible result it just provides us with illustrative information of the decommissioning process. A scenario evaluation program has been developed using the computer simulation technology to create an efficient decommissioning plan. In the D and D planning stage, it is important that the scenarios are evaluated from a engineering point of view because the decommissioning work has to be executed economically and safely following the best scenarios. Therefore, we need several modules to evaluate scenarios. We composed the systems like this: 1. Decommissioning DB module for managing the decommissioning activity information (nuclear facility data, worker's data, radioactive inventory date, etc.). Dismantling process evaluation module 3. Visualization module for a radioactive inventory and a dismantling process using 3D CAD and virtual reality technology. 4. Analysis module for the evaluation results of a dismantling process. The evaluation module's capabilities produce a dismantling schedule, quantify radioactive waste, visualize a radioactive inventory, estimate a decommissioning cost, estimate a worker's exposure, and check for interference/collisions. After using the simulation results, the expert ranking system to evaluate scenarios for economics and worker's safety are implemented. The expert ranking system is a powerful and flexible decision making process to help set priorities and make the best decisions when both the qualitative and quantitative aspects of a decision need to be considered. By reducing complex decisions to a series of one-on-one comparisons, then synthesizing the

  19. The Australian and New Zealand Haemostasis Registry: ten years of data on off-licence use of recombinant activated factor VII

    PubMed Central

    Zatta, Amanda; McQuilten, Zoe; Kandane-Rathnayake, Rangi; Isbister, James; Dunkley, Scott; McNeil, John; Cameron, Peter; Phillips, Louise

    2015-01-01

    Background Recombinant activated factor VII (rFVIIa) has been widely used as an off-licence pan-haemostatic agent in patients with critical bleeding. However, outside the trauma setting, there is relatively little high quality evidence on the risks and benefits of this agent. The Haemostasis Registry was established to investigate the extent of use, dosing, safety and outcomes of patients after off-licence rFVIIa treatment of critical bleeding. Materials and methods The Registry recruited non-haemophiliac patients treated with rFVIIa from 2000–2009 (inclusive) in Australia and New Zealand. Detailed information was gathered on patients’ demographics, context of bleeding, rFVIIa administration, laboratory results, blood component and other therapies, and outcomes. Outcome measures included subjectively assessed effect of rFVIIa on bleeding (response), adverse events (thromboembolic and other) and 28-day mortality. Results The registry included 3,446 cases in 3,322 patients (median [IQR] age 56 [33–70] years, 65% (n=2,147) male). Clinical indications included cardiac surgery (45%), other surgery (18%), trauma (13%), medical bleeding (6%), liver disease (6%), and obstetric haemorrhage (5%). The median [IQR] dose was 91 [72–103] μg/kg and 77% received a single dose. Reduction or cessation of bleeding was reported in 74% and 28-day survival was 71% but outcomes varied depending on clinical context. pH strongly correlated with outcome measures; 81% of patients with pH <7.1 died. Approximately 11% of patients had thromboembolic adverse events. In multivariate analysis, pH prior to administration and bleeding context were independently associated with reported response to rFVIIa and 28-day mortality. Discussion The Haemostasis Registry is the largest dataset of its kind and provides observational data on the off-licence use of rFVIIa over a 10-year period. It has been an invaluable resource for rigorously tracking adverse events and helping to inform clinical

  20. Dismantling of Radium-226 Coal Level Gauges: Encountered Problems and How to Solve

    SciTech Connect

    Punnachaiya, M.; Nuanjan, P.; Moombansao, K.; Sawangsri, T.; Pruantonsai, P.; Srichom, K.

    2006-07-01

    This paper describes the techniques for dismantling of disused-sealed Radium-226 (Ra-226) coal level gauges which the source specifications and documents were not available, including problems occurred during dismantling stage and the decision making in solving all those obstacles. The 2 mCi (20 pieces), 6 mCi (20 pieces) and 6.6 mCi (30 pieces) of Ra-226 hemi-spherically-shaped with lead-filled coal level gauges were used in industrial applications for electric power generation. All sources needed to be dismantled for further conditioning as requested by the International Atomic Energy Agency (IAEA). One of the 2 mCi Ra-226 source was dismantled under the supervision of IAEA expert. Before conditioning period, each of the 6 mCi and 6.6 mCi sources were dismantled and inspected. It was found that coal level gauges had two different source types: the sealed cylindrical source (diameter 2 cm x 2 cm length) locked with spring in lead housing for 2 mCi and 6.6 mCi; while the 6 mCi was an embedded capsule inside source holder stud assembly in lead-filled housing. Dismantling Ra-226 coal level gauges comprised of 6 operational steps: confirmation of the surface dose rate on each source activity, calculation of working time within the effective occupational dose limit, cutting the weld of lead container by electrical blade, confirmation of the Ra-226 embedded capsule size using radiation scanning technique and gamma radiography, automatic sawing of the source holder stud assembly, and transferring the source to store in lead safe box. The embedded length of 6 mCi Ra-226 capsule in its diameter 2 cm x 14.7 cm length stud assembly was identified, the results from scanning technique and radiographic film revealed the embedded source length of about 2 cm, therefore all the 6 mCi sources were safely cut at 3 cm using the automatic saw. Another occurring problem was one of the 6.6 mCi spring type source stuck inside its housing because the spring was deformed and there was

  1. Testing and Commissioning of a Multifunctional Tool for the Dismantling of the Activated Internals of the KNK Reactor Shaft - 13524

    SciTech Connect

    Rothschmitt, Stefan; Graf, Anja; Bauer, Stefan; Klute, Stefan; Koselowski, Eiko

    2013-07-01

    The Compact Sodium Cooled Reactor Facility Karlsruhe (KNK), a prototype reactor to demonstrate the Fast Breeder Reactor Technology in Germany, was in operation from 1971 to 1991. The dismantling activities started in 1991. The project aim is the green field in 2020. Most of the reactor internals as well as the primary and secondary cooling loops are already dismantled. The total contaminated sodium inventory has already been disposed of. Only the high activated reactor vessel shielding structures are remaining. Due to the high dose rates these structures must be dismantled remotely. For the dismantling of the primary shielding of the reactor vessel, 12 stacked cast iron blocks with a total mass of 90 Mg and single masses up to 15.5 Mg, a remote-controlled multifunctional dismantling device (HWZ) was designed, manufactured and tested in a mock-up. After successful approval of the test sequences by the authorities, the HWZ was implemented into the reactor building containment for final assembling of the auxiliary equipment and subsequent hot commissioning in 2012. Dismantling of the primary shielding blocks is scheduled for early 2013. (authors)

  2. Cleanup and Dismantling of Highly Contaminated Ventilation Systems Using Robotic Tools - 13162

    SciTech Connect

    Chambon, Frederic; CIZEL, Jean-Pierre

    2013-07-01

    The UP1 plant reprocessed nearly 20,000 tons of used natural uranium gas cooled reactor fuel coming from the first generation of civil nuclear reactors in France. Following operating incidents in the eighties, the ventilation system of the continuous dissolution line facility was shut down and replaced. Two types of remote controlled tool carriers were developed to perform the decontamination and dismantling operations of the highly contaminated ventilation duct network. The first one, a dedicated small robot, was designed from scratch to retrieve a thick powder deposit within a duct. The robot, managed and confined by two dedicated glove boxes, was equipped for intervention inside the ventilation duct and used for carrying various cleanup and inspection tools. The second type, consisting of robotic tools developed on the base of an industrial platform, was used for the clean-up and dismantling of the ventilation duct system. Depending on the type of work to be performed, on the shape constraints of the rooms and any equipment to be dismantled, different kinds of robotic tools were developed and installed on a Brokk 40 carrier. After more than ten years of ventilation duct D and D operations at the UP1 plant, a lot of experience was acquired about remote operations. The three main important lessons learned in terms of remote controlled operation are: characterizing the initial conditions as much as reasonably possible, performing non-radioactive full scale testing and making it as simple and modular as possible. (authors)

  3. Regulatory and Permitting Issues

    SciTech Connect

    Larry Myer

    2005-12-01

    As part of the West Coast Regional Carbon Sequestration Partnership (WESTCARB), Terralog Technologies USA, Inc., reviewed current state and federal regulations related to carbon dioxide capture and storage within geologic formations and enhanced carbon uptake in terrestrial ecosystems. We have evaluated and summarized the current and possible future permitting requirements for the six states that comprise the West Coast Regional Partnership. Four options exist for CO{sub 2} injection into appropriate geologic formations, including storage in: (1) oil and gas reservoirs, (2) saline formations, (3) unmineable coal beds, and (4) salt caverns. Terrestrial CO{sub 2} sequestration involves improved carbon conservation management (e.g. reduction of deforestation), carbon substitution (e.g., substitution for fossil fuel-based products, energy conservation through urban forestry, biomass for energy generation), and improved carbon storage management (e.g., expanding the storage of carbon in forest ecosystems). The primary terrestrial options for the West Coast Region include: (1) reforestation of under-producing lands (including streamside forest restoration), (2) improved forest management, (3) forest protection and conservation, and (4) fuel treatments for the reduction of risk of uncharacteristically severe fires (potentially with associated biomass energy generation). The permits and/or contracts required for any land-use changes/disturbances and biomass energy generation that may occur as part of WESTCARB's activities have been summarized for each state.

  4. Chooz A, First Pressurized Water Reactor to be Dismantled in France - 13445

    SciTech Connect

    Boucau, Joseph; Mirabella, C.; Nilsson, Lennart; Kreitman, Paul J.; Obert, Estelle

    2013-07-01

    Nine commercial nuclear power plants have been permanently shut down in France to date, of which the Chooz A plant underwent an extensive decommissioning and dismantling program. Chooz Nuclear Power Station is located in the municipality of Chooz, Ardennes region, in the northeast part of France. Chooz B1 and B2 are 1,500 megawatt electric (MWe) pressurized water reactors (PWRs) currently in operation. Chooz A, a 305 MWe PWR implanted in two caves within a hill, began operations in 1967 and closed in 1991, and will now become the first PWR in France to be fully dismantled. EDF CIDEN (Engineering Center for Dismantling and Environment) has awarded Westinghouse a contract for the dismantling of its Chooz A reactor vessel (RV). The project began in January 2010. Westinghouse is leading the project in a consortium with Nuvia France. The project scope includes overall project management, conditioning of the reactor vessel (RV) head, RV and RV internals segmentation, reactor nozzle cutting for lifting the RV out of the pit and seal it afterwards, dismantling of the RV thermal insulation, ALARA (As Low As Reasonably Achievable) forecast to ensure acceptable doses for the personnel, complementary vacuum cleaner to catch the chips during the segmentation work, needs and facilities, waste characterization and packaging, civil work modifications, licensing documentation. The RV and RV internals will be segmented based on the mechanical cutting technology that Westinghouse applied successfully for more than 13 years. The segmentation activities cover the cutting and packaging plan, tooling design and qualification, personnel training and site implementation. Since Chooz A is located inside two caves, the project will involve waste transportation from the reactor cave through long galleries to the waste buffer area. The project will end after the entire dismantling work is completed, and the waste storage is outside the caves and ready to be shipped either to the ANDRA (French

  5. 50 CFR 665.662 - Permits.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... coral MUS in any PRIA precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious Coral Permit... surrendering to the Regional Administrator any current permit for the precious coral fishery issued under §...

  6. 50 CFR 665.662 - Permits.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... coral MUS in any PRIA precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious Coral Permit... surrendering to the Regional Administrator any current permit for the precious coral fishery issued under §...

  7. 50 CFR 665.662 - Permits.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... coral MUS in any PRIA precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious Coral Permit... surrendering to the Regional Administrator any current permit for the precious coral fishery issued under §...

  8. 50 CFR 665.662 - Permits.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... coral MUS in any PRIA precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious Coral Permit... surrendering to the Regional Administrator any current permit for the precious coral fishery issued under §...

  9. 50 CFR 665.662 - Permits.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... coral MUS in any PRIA precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious Coral Permit... surrendering to the Regional Administrator any current permit for the precious coral fishery issued under §...

  10. The Dismantling of Nuclear Submarines in North-West Russia An Overview of two projects and the end products

    SciTech Connect

    Simmons, V.M.; Wells, D.A.; Field, D.P.; Crimp, C.D.H.

    2006-07-01

    This paper explains the background to the projects, and the setting up of the contracts to dismantle two Oscar-I submarines and one Victor-III submarine. As a pre -cursor to the dismantling, Russian documentation covering environmental, safety, operational and technical issues had to be prepared and submitted to the Russian regulatory bodies for approval, including a full Environmental Impact Assessment (EIA) of the projects. In addition to the dismantling projects, funds were also made available for shipyard infrastructure improvement projects necessary to ensure the safe and efficient completion of the projects. The paper describes these aspects as well as the submarines themselves and gives an overview of the dismantling process. It also describes the nature of the wastes produced, including handling and processing together with the safety and environmental issues. Project Management and monitoring contracted to RWE NUKEM by the U.K. Department of Trade and Industry (DTI) is described emphasizing the importance of strong working relationships between British and Russian teams. Finally the paper discusses the 'end products' of the Oscar-I and Victor-III dismantling and how the projects have provided a useful, high-profile platform on which to demonstrate the success of the DTI and their contractors in helping the U.K. meet its commitments under the Global Partnership Initiative. (authors)

  11. Dismantling of Highly Contaminated Process Installations of the German Reprocessing Facility (WAK) - Status of New Remote Handling Technology - 13287

    SciTech Connect

    Dux, Joachim; Friedrich, Daniel; Lutz, Werner; Ripholz, Martina

    2013-07-01

    Decommissioning and dismantling of the former German Pilot Reprocessing Plant Karlsruhe (WAK) including the Vitrification Facility (VEK) is being executed in different Project steps related to the reprocessing, HLLW storage and vitrification complexes /1/. While inside the reprocessing building the total inventory of process equipment has already been dismantled and disposed of, the HLLW storage and vitrification complex has been placed out of operation since vitrification and tank rinsing procedures where finalized in year 2010. This paper describes the progress made in dismantling of the shielded boxes of the highly contaminated laboratory as a precondition to get access to the hot cells of the HLLW storage. The major challenges of the dismantling of this laboratory were the high dose rates up to 700 mSv/h and the locking technology for the removal of the hot cell installations. In parallel extensive prototype testing of different carrier systems and power manipulators to be applied to dismantle the HLLW-tanks and other hot cell equipment is ongoing. First experiences with the new manipulator carrier system and a new master slave manipulator with force reflection will be reported. (authors)

  12. Avoiding Title V permitting pitfalls

    SciTech Connect

    Laswell, D.L.

    1993-04-01

    Title V of the 1990 Clean Air Act Amendments requires states to implement new air operating permit programs. States have a great deal of flexibility in developing their permit programs. Industry should work now to ensure that state programs contain the favorable aspects of the federal regulations and do not contain more stringent requirements that are not required under the Clean Air Act. This article outlines areas of the permit program that have the potential to handicap industry`s ability to expand.

  13. Development of Digital Mock-Up for the Assessment of Dismantling Scenarios

    SciTech Connect

    Kim, Sung-Kyun; Park, Hee-Sung; Lee, Kune-Woo; Jung, Chong-Hun

    2008-01-15

    As the number of superannuated research reactors and nuclear power plants increase, dismantling nuclear power facilities has become a big issue. However, decommissioning a nuclear facility is still a costly and possibly hazardous task. So prior to an actual decommission, what should be done foremost is to establish a proper procedure. Due to the fact that a significant difference in cost, exposure to a radiation, and safety might occur, a proper procedure is imperative for the entire engineering process. The purpose of this paper is to develop a system for evaluating the decommissioning scenarios logically and systematically. So a digital mockup system with functions such as a dismantling schedule, decommissioning costs, wastes, worker's exposure dose, and a radiation distribution was developed. Also on the basis of the quantitative information calculated from a DMU system and the data evaluated by decommissioning experts about qualitatively evaluating the items, the best decommissioning scenarios were established by using the analytic hierarchy process (AHP) method. Finally, the DMU was implemented in the thermal column of KRR-1 and adequate scenarios were provided after comparing and analyzing the two scenarios. In this paper, we developed the virtual environment of KRR-1 by using computer graphic technology and simulating the dismantling processes. The data-computing modules were also developed for quantitatively comparing the decommissioning scenarios. The decommissioning DMU system was integrated with both the VE system and the data-computing modules. In addition, we presented a decision-making method for selecting the best decommissioning scenario through the AHP. So the scenarios can be evaluated logically and quantitatively through the decommissioning DMU. As an implementation of the AHP, the plasma cutting scenario and the nibbler cutting scenario of the thermal column were prioritized. The fact that the plasma cutting scenario ranked the better than the

  14. Radiochemistry Lab Decommissioning and Dismantlement. AECL, Chalk River Labs, Ontario, Canada

    SciTech Connect

    Kenny, Stephen

    2008-01-15

    Atomic Energy of Canada (AECL) was originally founded in the mid 1940's to perform research in radiation and nuclear areas under the Canadian Defense Department. In the mid 50's The Canadian government embarked on several research and development programs for the development of the Candu Reactor. AECL was initially built as a temporary site and is now faced with many redundant buildings. Prior to 2004 small amounts of Decommissioning work was in progress. Many reasons for deferring decommissioning activities were used with the predominant ones being: 1. Reduction in radiation doses to workers during the final dismantlement, 2. Development of a long-term solution for the management of radioactive wastes in Canada, 3. Financial constraints presented by the number of facilities shutdown that would require decommissioning funds and the absence of an approved funding strategy. This has led to the development of a comprehensive decommissioning plan that is all inclusive of AECL's current and legacy liabilities. Canada does not have a long-term disposal site; therefore waste minimization becomes the driving factor behind decontamination for decommissioning before and during dismantlement. This decommissioning job was a great learning experience for decommissioning and the associated contractors who worked on this project. Throughout the life of the project there was a constant focus on waste minimization. This focus was constantly in conflict with regulatory compliance primarily with respect to fire regulations and protecting the facility along with adjacent facilities during the decommissioning activities. Discrepancies in historical documents forced the project to treat every space as a contaminated space until proven differently. Decommissioning and dismantlement within an operating site adds to the complexity of the tasks especially when it is being conducted in the heart of the plant. This project was very successful with no lost time accidents in over one hundred

  15. Waste Management Strategy for Dismantling Waste to Reduce Costs for Power Plant Decommissioning - 13543

    SciTech Connect

    Larsson, Arne; Lidar, Per; Bergh, Niklas; Hedin, Gunnar

    2013-07-01

    Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named 'ndcon' to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions. Bottle

  16. Decontamination and dismantlement of the old hot laundry, CFA-669. Final report

    SciTech Connect

    Smith, D.L.; Perry, E.F.

    1995-01-01

    This final report describes the decontamination and dismantlement (D&D) of the old hot laundry, located at the Idaho National Engineering Laboratory (INEL) Central Facilities Area (CFA). The report describes the site before and after D&D, processes used, cost and duration, and waste volume generated. In addition, lessons learned are presented. Pre-D&D characterization indicated gross alpha concentrations in the building ranged from 6 to 310 pCi/g and gross beta measurements from 6 to 15,000 pCi/g. Gamma spectrum analysis identified cobalt-60, cesium-137, antimony-125, europium-152, europium-154, and niobium-94.

  17. 50 CFR 622.50 - Permits, permit moratorium, and endorsements.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... OCEANIC AND ATMOSPHERIC ADMINISTRATION, DEPARTMENT OF COMMERCE FISHERIES OF THE CARIBBEAN, GULF OF MEXICO, AND SOUTH ATLANTIC Shrimp Fishery of the Gulf of Mexico § 622.50 Permits, permit moratorium, and... Fishery Management Plan for the Shrimp Fishery of the Gulf of Mexico (Gulf Shrimp FMP),......

  18. 50 CFR 622.50 - Permits, permit moratorium, and endorsements.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... OCEANIC AND ATMOSPHERIC ADMINISTRATION, DEPARTMENT OF COMMERCE FISHERIES OF THE CARIBBEAN, GULF OF MEXICO, AND SOUTH ATLANTIC Shrimp Fishery of the Gulf of Mexico § 622.50 Permits, permit moratorium, and... Fishery Management Plan for the Shrimp Fishery of the Gulf of Mexico (Gulf Shrimp FMP),......

  19. 50 CFR 665.462 - Permits.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... Permits. (a) Any vessel of the United States fishing for, taking, or retaining Mariana precious coral MUS in any Mariana Archipelago precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious...

  20. 50 CFR 665.262 - Permits.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ...) Any vessel of the United States fishing for, taking, or retaining Hawaii precious coral MUS in any Hawaiian Archipelago precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious Coral Permit...

  1. 50 CFR 665.162 - Permits.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... coral MUS in any American Samoa precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious Coral... upon surrendering to the Regional Administrator any current permit for the precious coral...

  2. 50 CFR 665.162 - Permits.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... coral MUS in any American Samoa precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious Coral... upon surrendering to the Regional Administrator any current permit for the precious coral...

  3. 50 CFR 665.262 - Permits.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ...) Any vessel of the United States fishing for, taking, or retaining Hawaii precious coral MUS in any Hawaiian Archipelago precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious Coral Permit...

  4. 50 CFR 665.462 - Permits.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... Permits. (a) Any vessel of the United States fishing for, taking, or retaining Mariana precious coral MUS in any Mariana Archipelago precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious...

  5. 50 CFR 665.262 - Permits.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ...) Any vessel of the United States fishing for, taking, or retaining Hawaii precious coral MUS in any Hawaiian Archipelago precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious Coral Permit...

  6. 50 CFR 665.462 - Permits.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... Permits. (a) Any vessel of the United States fishing for, taking, or retaining Mariana precious coral MUS in any Mariana Archipelago precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious...

  7. 50 CFR 665.262 - Permits.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ...) Any vessel of the United States fishing for, taking, or retaining Hawaii precious coral MUS in any Hawaiian Archipelago precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious Coral Permit...

  8. 50 CFR 665.162 - Permits.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... coral MUS in any American Samoa precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious Coral... upon surrendering to the Regional Administrator any current permit for the precious coral...

  9. 50 CFR 665.462 - Permits.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... Permits. (a) Any vessel of the United States fishing for, taking, or retaining Mariana precious coral MUS in any Mariana Archipelago precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious...

  10. 50 CFR 665.262 - Permits.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ...) Any vessel of the United States fishing for, taking, or retaining Hawaii precious coral MUS in any Hawaiian Archipelago precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious Coral Permit...

  11. 50 CFR 665.162 - Permits.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... coral MUS in any American Samoa precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious Coral... upon surrendering to the Regional Administrator any current permit for the precious coral...

  12. 50 CFR 665.462 - Permits.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... Permits. (a) Any vessel of the United States fishing for, taking, or retaining Mariana precious coral MUS in any Mariana Archipelago precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious...

  13. 50 CFR 665.162 - Permits.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... coral MUS in any American Samoa precious coral permit area must have a permit issued under § 665.13. (b) Each permit will be valid for fishing only in the permit area specified on the permit. Precious Coral... upon surrendering to the Regional Administrator any current permit for the precious coral...

  14. 40 CFR 72.85 - Permit reopenings.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Permit reopenings. 72.85 Section 72.85 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) PERMITS REGULATION Permit Revisions § 72.85 Permit reopenings. (a) The permitting authority shall reopen an Acid Rain permit for cause whenever: (1)...

  15. Interim storage of dismantled nuclear weapon components at the U.S. Department of Energy Pantex Plant

    SciTech Connect

    Guidice, S.J.; Inlow, R.O.

    1995-12-31

    Following the events of 1989 and the subsequent cessation of production of new nuclear weapons by the US, the mission of the Department of Energy (DOE) Nuclear Weapons Complex has shifted from production to dismantlement of retired weapons. The sole site in the US for accomplishing the dismantlement mission is the DOE Pantex Plant near Amarillo, Texas. Pending a national decision on the ultimate storage and disposition of nuclear components form the dismantled weapons, the storage magazines within the Pantex Plant are serving as the interim storage site for pits--the weapon plutonium-bearing component. The DOE has stipulated that Pantex will provide storage for up to 12,000 pits pending a Record of Decision on a comprehensive site-wide Environmental Impact Statement in November 1996.

  16. CP-5 reactor remote dismantlement activities: Lessons learned in the integration of new technology in an operations environment

    SciTech Connect

    Noakes, M.W.

    1998-06-01

    This paper presents the developer`s perspective on lessons learned from one example of the integration of new prototype technology into a traditional operations environment. The dual arm work module was developed by the Robotics Technology Development Program as a research and development activity to examine manipulator controller modes and deployment options. It was later reconfigured for the dismantlement of the Argonne National Laboratory Chicago Pile No. 5 reactor vessel as the crane-deployed dual arm work platform. Development staff worked along side operations staff during a significant part of the deployment to provide training, maintenance, and tooling support. Operations staff completed all actual remote dismantlement tasks. At the end of available development support funding, the Dual Arm Work Platform was turned over to the operations staff, who are still using it to complete their dismantlement tasks.

  17. Melter Dismantlement

    SciTech Connect

    Richardson, BS

    2000-10-01

    The U.S. Department of Energy (DOE) has been utilizing vitrification processes to convert high-level radioactive waste forms into a stable glass for disposal in waste repositories. Vitrification facilities at the Savannah River Site (SRS) and at the West Valley Demonstration Project (WVDP) are converting liquid high level waste (HLW) by combining it with a glass-forming media to form a borosilicate glass, which will ensure safe long-term storage. Large, slurry fed melters, which are utilized for this process, were anticipated to have a finite life, on the order of two to three years, at which time they would have to be replaced using remote methods, due to the high radiation fields. In actuality the melters useable life span has, to date, have exceeded original life span estimates. Initial plans called for the removal of failed melters by placing the melter assembly into a container and storing in a concrete vault on the vitrification plant site pending size reduction, segregation, containerization, and shipment to appropriate storage facilities. Separate facilities for the processing of the failed melters currently do not exist. Options for handling these melters include (1) locating a facility to conduct the size reduction, characterization, and containerization as originally planned; (2) long-term storage or disposal of the complete melter assembly; and (3) attempting to refurbish the melter and to reuse the melter assembly. The focus of this report is to look at methods and issues pertinent to size reduction and/or melter refurbishment. In particular, removal of glass as a part of a refurbishment or for the purposes of reducing contamination levels (allowing for disposal of a greater proportion of the melter as low level waste) will be addressed.

  18. F-actin dismantling through a redox-driven synergy between Mical and cofilin.

    PubMed

    Grintsevich, Elena E; Yesilyurt, Hunkar Gizem; Rich, Shannon K; Hung, Ruei-Jiun; Terman, Jonathan R; Reisler, Emil

    2016-08-01

    Numerous cellular functions depend on actin filament (F-actin) disassembly. The best-characterized disassembly proteins, the ADF (actin-depolymerizing factor)/cofilins (encoded by the twinstar gene in Drosophila), sever filaments and recycle monomers to promote actin assembly. Cofilin is also a relatively weak actin disassembler, posing questions about mechanisms of cellular F-actin destabilization. Here we uncover a key link to targeted F-actin disassembly by finding that F-actin is efficiently dismantled through a post-translational-mediated synergism between cofilin and the actin-oxidizing enzyme Mical. We find that Mical-mediated oxidation of actin improves cofilin binding to filaments, where their combined effect dramatically accelerates F-actin disassembly compared with either effector alone. This synergism is also necessary and sufficient for F-actin disassembly in vivo, magnifying the effects of both Mical and cofilin on cellular remodelling, axon guidance and Semaphorin-Plexin repulsion. Mical and cofilin, therefore, form a redox-dependent synergistic pair that promotes F-actin instability by rapidly dismantling F-actin and generating post-translationally modified actin that has altered assembly properties. PMID:27454820

  19. Proposed radiation hardened mobile vehicle for Chernobyl dismantlement and nuclear accident response

    SciTech Connect

    Rowland, M.S.; Holliday, M.A.; Karpachov, J.A.; Ivanov, A.

    1995-01-01

    Researchers are developing a radiation hardened, Telerobotic Dismantling System (TDS) to remediate the Chernobyl facility. To withstand the severe radiation fields, the robotic system, will rely on electrical motors, actuators, and relays proven in the Chernobyl power station. Due to its dust suppression characteristics and ability to cut arbitrary materials the authors propose using a water knife as the principle tool to slice up the large fuel containing masses. The front end of the robot will use a minimum number of moving parts by locating most of the susceptible and bulky components outside the work area. Hardened and shielded video cameras will be designed for remote control and viewing of the robotic functions. Operators will supervise and control robot movements based on feedback from a suite of sensory systems that would include vision systems, radiation detection and measurement systems and force reflection systems. A gripper will be instrumented with a variety of sensors (e.g. force, torque, or tactile), allowing varying debris surface properties to be grasped. The gripper will allow the operator to manipulate and segregate debris items without entering the radiologically and physically dangerous dismantlement operations area. The robots will initially size reduce the FCM`s to reduce the primary sources of the airborne radionuclides. The robot will then remove the high level waste for packaging or decontamination, and storage nearby.

  20. Life cycle assessment of hybrid vehicles recycling: Comparison of three business lines of dismantling.

    PubMed

    Belboom, Sandra; Lewis, Grégory; Bareel, Pierre-François; Léonard, Angélique

    2016-04-01

    This paper undertakes an environmental evaluation of hybrid vehicles recycling, using industrial data from Comet Traitement SA in Belgium. Three business lines have been modelled and analysed. The first one is relative to the business as usual with a dismantling to recover batteries and engines followed by shredding and post shredding treatments. The second one considers, in addition, the removal of electronic control units (ECU) before shredding followed by same steps than in the first line and the last one is relative to the additional removal of big plastic parts before shredding and business as usual post shredding treatments. Results show non-significant environmental benefits when ECU or large parts of plastics are recovered before shredding. Improvements in terms of environmental benefits are lower than the uncertainty of the results. Indeed, the performing usual process for end-of-life vehicles (ELV) treatment reaches 97% of the ELV which is valorised in terms of metal and energy recoveries. Post shredding treatment units include metals, plastics and energy recovery of residues. Comet business as usual route for ELV valorisation is in accordance with the requirements of the European directive and recommendations for further improvement with dismantling of other parts (ECU or plastics) before shredding are non-relevant in this case. PMID:26898478

  1. [Only 1 out of 1 000 patients with alcohol dependence problems are reported according to the Driver's Licence Act. Physicians estimate to increase the number of reports some 70 times with a two-year ignition interlock program].

    PubMed

    Bjerre, Bo; Heed, Birgitta; Kers, Sarah

    2004-05-13

    This poll, aimed at general practitioners and dependence specialists, shows that only one out of 1,000 patients diagnosed alcohol-dependent are reported to the county administrative board in accordance with the Swedish Driver's Licence Act. The anticipated negative effect on continued doctor-patient contact stands out as the predominant obstacle to filing a report. Among general practitioners an uncertainty about diagnosing alcohol dependence and alcohol abuse also was an important obstacle. Given the opportunity to participate in a two-year alcolock programme as an alternative to driver's licence revocation, doctors estimate that they would report some 70 times the number of patients. This estimation is obviously subject to considerable uncertainty, but does reflect an important attitude and an expectation that such a report constitutes a positive move from both an individual and a social perspective. PMID:15190769

  2. ENCOURAGING INNOVATION THROUGH UMBRELLA PERMITTING

    EPA Science Inventory

    The purpose of this project is to assess the behavioral, technical, economic, and environmental effects of removing disincentives to innovation in production and pollution management through more flexible environmental permitting. The study will examine the characteristics of tra...

  3. Dismantling the School Sport Partnership Infrastructure: Findings from a Survey of Physical Education and School Sport Practitioners

    ERIC Educational Resources Information Center

    Mackintosh, Chris

    2014-01-01

    This research examines the perceptions of education practitioners to the proposed changes to the school sport partnership (SSP) programme in England and in particular its implications for primary school physical education. It aims to explore insights into the dismantling of this partnership programme. The SSP system developed club links, increased…

  4. Dose reduction through automation of nuclear weapons dismantlement and storage procedures at the Department of Energy`s Pantex Facility

    SciTech Connect

    Thompson, D.A.; Poston, J.W.

    1996-06-01

    With the end of the Cold War and the subsequent break up of the Soviet Union, the number of weapons in the nuclear stockpile now greatly exceeds any foreseeable future need. To compensate for this excess an estimated 20,000 nuclear warheads have been earmarked for dismantlement and storage at the Department of Energy`s Pantex Plant near Amarillo, Texas. It is anticipated that the majority of these warheads will arrive at the Pantex facility by the year 2000. At that time, it is estimated that current dismantlement and inventory procedures will not be adequate to control worker radiation exposure within administrative and federal dose limits. To control these exposures alternate approaches to dismantlement and inventory must be developed. One attractive approach is to automate as many activities as possible, thus reducing worker exposure. To facilitate automation of dismantlement and storage procedures, current procedures were investigated in terms of collective dose to workers, time to completion, ease of completion, and cost of automation for each task. A cost-benefit comparison was then performed in order to determine which procedures would be most cost-effective to automate.

  5. 49 CFR 1242.37 - Dismantling retired property and depreciation (accounts XX-26-39 and 62-26-00).

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 49 Transportation 9 2010-10-01 2010-10-01 false Dismantling retired property and depreciation (accounts XX-26-39 and 62-26-00). 1242.37 Section 1242.37 Transportation Other Regulations Relating to... (accounts XX-26-39 and 62-26-00). Separate common expenses in each account in proportion to the...

  6. 48 CFR 52.249-3 - Termination for Convenience of the Government (Dismantling, Demolition, or Removal of Improvements).

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 48 Federal Acquisition Regulations System 2 2010-10-01 2010-10-01 false Termination for Convenience of the Government (Dismantling, Demolition, or Removal of Improvements). 52.249-3 Section 52.249-3 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION (CONTINUED) CLAUSES AND FORMS SOLICITATION PROVISIONS AND CONTRACT CLAUSES...

  7. 40 CFR 172.5 - The permit.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 40 Protection of Environment 24 2014-07-01 2014-07-01 false The permit. 172.5 Section 172.5... PERMITS Federal Issuance of Experimental Use Permits § 172.5 The permit. (a) Issuance. The Experimental Use Permit shall be issued when the Administrator determines that the conditions of section 5 of...

  8. 40 CFR 172.5 - The permit.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 40 Protection of Environment 25 2013-07-01 2013-07-01 false The permit. 172.5 Section 172.5... PERMITS Federal Issuance of Experimental Use Permits § 172.5 The permit. (a) Issuance. The Experimental Use Permit shall be issued when the Administrator determines that the conditions of section 5 of...

  9. 40 CFR 172.5 - The permit.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 40 Protection of Environment 23 2010-07-01 2010-07-01 false The permit. 172.5 Section 172.5... PERMITS Federal Issuance of Experimental Use Permits § 172.5 The permit. (a) Issuance. The Experimental Use Permit shall be issued when the Administrator determines that the conditions of section 5 of...

  10. 40 CFR 172.5 - The permit.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 40 Protection of Environment 25 2012-07-01 2012-07-01 false The permit. 172.5 Section 172.5... PERMITS Federal Issuance of Experimental Use Permits § 172.5 The permit. (a) Issuance. The Experimental Use Permit shall be issued when the Administrator determines that the conditions of section 5 of...

  11. 40 CFR 72.85 - Permit reopenings.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... REGULATION Permit Revisions § 72.85 Permit reopenings. (a) The permitting authority shall reopen an Acid Rain permit for cause whenever: (1) Any additional requirement under the Acid Rain Program becomes applicable... revoked to assure compliance with Acid Rain Program requirements. (b) In reopening an Acid Rain permit...

  12. 40 CFR 70.6 - Permit content.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 40 Protection of Environment 16 2014-07-01 2014-07-01 false Permit content. 70.6 Section 70.6 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) STATE OPERATING PERMIT PROGRAMS § 70.6 Permit content. (a) Standard permit requirements. Each permit issued...

  13. 40 CFR 70.6 - Permit content.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 40 Protection of Environment 15 2011-07-01 2011-07-01 false Permit content. 70.6 Section 70.6 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) STATE OPERATING PERMIT PROGRAMS § 70.6 Permit content. (a) Standard permit requirements. Each permit issued...

  14. 40 CFR 70.6 - Permit content.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 40 Protection of Environment 16 2013-07-01 2013-07-01 false Permit content. 70.6 Section 70.6 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) STATE OPERATING PERMIT PROGRAMS § 70.6 Permit content. (a) Standard permit requirements. Each permit issued...

  15. 40 CFR 70.6 - Permit content.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 40 Protection of Environment 15 2010-07-01 2010-07-01 false Permit content. 70.6 Section 70.6 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) STATE OPERATING PERMIT PROGRAMS § 70.6 Permit content. (a) Standard permit requirements. Each permit issued...

  16. 40 CFR 72.51 - Permit shield.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Permit shield. 72.51 Section 72.51 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) PERMITS REGULATION Acid Rain Permit Contents § 72.51 Permit shield. Each affected unit operated in accordance with the Acid Rain permit that governs the...

  17. 40 CFR 72.85 - Permit reopenings.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... REGULATION Permit Revisions § 72.85 Permit reopenings. (a) The permitting authority shall reopen an Acid Rain permit for cause whenever: (1) Any additional requirement under the Acid Rain Program becomes applicable... revoked to assure compliance with Acid Rain Program requirements. (b) In reopening an Acid Rain permit...

  18. 40 CFR 72.85 - Permit reopenings.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... REGULATION Permit Revisions § 72.85 Permit reopenings. (a) The permitting authority shall reopen an Acid Rain permit for cause whenever: (1) Any additional requirement under the Acid Rain Program becomes applicable... revoked to assure compliance with Acid Rain Program requirements. (b) In reopening an Acid Rain permit...

  19. 40 CFR 72.85 - Permit reopenings.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... REGULATION Permit Revisions § 72.85 Permit reopenings. (a) The permitting authority shall reopen an Acid Rain permit for cause whenever: (1) Any additional requirement under the Acid Rain Program becomes applicable... revoked to assure compliance with Acid Rain Program requirements. (b) In reopening an Acid Rain permit...

  20. 45 CFR 671.8 - Permit administration.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 45 Public Welfare 3 2010-10-01 2010-10-01 false Permit administration. 671.8 Section 671.8 Public... Permits § 671.8 Permit administration. (a) Issuance of permits. The Director may approve an application... permit, the Director shall publish notice of the issuance or denial in the Federal Register,...

  1. 21 CFR 1210.21 - Permit number.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... 21 Food and Drugs 8 2013-04-01 2013-04-01 false Permit number. 1210.21 Section 1210.21 Food and... IMPORT MILK ACT Permit Control § 1210.21 Permit number. Each permit issued under the Federal Import Milk Act, including each temporary permit, shall bear an individual number. The right to the use of...

  2. 21 CFR 1210.21 - Permit number.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Permit number. 1210.21 Section 1210.21 Food and... IMPORT MILK ACT Permit Control § 1210.21 Permit number. Each permit issued under the Federal Import Milk Act, including each temporary permit, shall bear an individual number. The right to the use of...

  3. 21 CFR 1210.21 - Permit number.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... 21 Food and Drugs 8 2011-04-01 2011-04-01 false Permit number. 1210.21 Section 1210.21 Food and... IMPORT MILK ACT Permit Control § 1210.21 Permit number. Each permit issued under the Federal Import Milk Act, including each temporary permit, shall bear an individual number. The right to the use of...

  4. 21 CFR 1210.21 - Permit number.

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... 21 Food and Drugs 8 2012-04-01 2012-04-01 false Permit number. 1210.21 Section 1210.21 Food and... IMPORT MILK ACT Permit Control § 1210.21 Permit number. Each permit issued under the Federal Import Milk Act, including each temporary permit, shall bear an individual number. The right to the use of...

  5. 21 CFR 1210.21 - Permit number.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... 21 Food and Drugs 8 2014-04-01 2014-04-01 false Permit number. 1210.21 Section 1210.21 Food and... IMPORT MILK ACT Permit Control § 1210.21 Permit number. Each permit issued under the Federal Import Milk Act, including each temporary permit, shall bear an individual number. The right to the use of...

  6. The National Solar Permitting Database

    Energy Science and Technology Software Center (ESTSC)

    2014-08-31

    "The soft costs of solar—costs not associated with hardware—remain stubbornly high. Among the biggest soft costs are those associated with inefficiencies in local permitting and inspection. A study by the National Renewable Energy Laboratory and Lawrence Berkeley National Laboratory estimates that these costs add an average of $0.22/W per residential installation. This project helps reduce non-hardware/balance of system (BOS) costs by creating and maintaining a free and available site of permitting requirements and solar systemmore » verification software that installers can use to reduce time, capital, and resource investments in tracking permitting requirements. Software tools to identify best permitting practices can enable government stakeholders to optimize their permitting process and remove superfluous costs and requirements. Like ""a Wikipedia for solar permitting"", users can add, edit, delete, and update information for a given jurisdiction. We incentivize this crowdsourcing approach by recognizing users for their contributions in the form of SEO benefits to their company or organization by linking back to users' websites."« less

  7. The National Solar Permitting Database

    SciTech Connect

    Gunderson, Renic

    2014-08-31

    "The soft costs of solar—costs not associated with hardware—remain stubbornly high. Among the biggest soft costs are those associated with inefficiencies in local permitting and inspection. A study by the National Renewable Energy Laboratory and Lawrence Berkeley National Laboratory estimates that these costs add an average of $0.22/W per residential installation. This project helps reduce non-hardware/balance of system (BOS) costs by creating and maintaining a free and available site of permitting requirements and solar system verification software that installers can use to reduce time, capital, and resource investments in tracking permitting requirements. Software tools to identify best permitting practices can enable government stakeholders to optimize their permitting process and remove superfluous costs and requirements. Like ""a Wikipedia for solar permitting"", users can add, edit, delete, and update information for a given jurisdiction. We incentivize this crowdsourcing approach by recognizing users for their contributions in the form of SEO benefits to their company or organization by linking back to users' websites."

  8. Decommissioning, Dismantling and Disarming: a Unique Information Showroom Inside the G2 Reactor at Marcoule Centre (France) - 12068

    SciTech Connect

    Volant, Emmanuelle; Garnier, Cedric

    2012-07-01

    The paper aims at presenting the new information showroom called 'Escom G2' (for 'Espace Communication') inaugurated by the French Atomic Energy and Alternative Energies Commission (CEA) in spring 2011. This showroom is settled directly inside the main building of the G2 nuclear reactor: a facility formerly dedicated to weapon-grade plutonium production since the late 1950's at the Marcoule nuclear centre, in south of France. After its shutdown, and reprocessing of the last spent fuels, a first dismantling step was successfully completed from 1986 to 1996. Unique in France and in Europe, Escom G2 is focused on France dismantling expertise and its action for disarmament. This showroom comprises of a 300-square meters permanent exhibition, organized around four themes: France strategy for disarmament, decommissioning and dismantling technical aspects, uranium and plutonium production cycles. Each of these topics is illustrated with posters, photos, models and technical pieces from the dismantled plants. It is now used to present France's action in disarmament to highly ranked audiences such as: state representatives, diplomats, journalists... The paper explains the background story of this original project. As a matter of fact, in 1996 France was the first nuclear state to decide to shut down and dismantle its fissile material production facilities for nuclear weapons. First, the paper presents the history of the G2 reactor in the early ages of Marcoule site, its operating highlights as well as its main dismantling operations, are presented. In Marcoule, where the three industrial-scale reactors G1, G2 and G3 used to be operated for plutonium production (to be then reprocessed in the nearby UP1 plant), the initial dismantling phase has now been completed (in 1980's for G1 and in 1996 for G2 and G3). The second phase, aimed at completely dismantling these three reactors, will restart in 2020, and is directly linked to the opening of a future national storage facility

  9. Radiation protection performance for the dismantling of the WWR-M primary cooling circuit.

    PubMed

    Lobach, Yu N; Luferenko, E D; Shevel, V N

    2014-12-01

    The WWR-M is a light-water-cooled and moderated heterogonous research reactor with a thermal output of 10 MW. The reactor has been in operation for >50 y and has had an excellent safety record. A non-hermeticity of the inlet line of the primary cooling circuit (PCC) was found, and the only reasonable technical solution was the complete replacement of the PCC inlet and outlet pipe lines. Such a replacement was a challenging technical task due to the necessity to handle large size components with complex geometries under conditions of high-level radiation fields, and therefore, it required detailed planning aiming to reduce staff exposure. This paper describes the dismantling and removal of the PCC components focusing on radiation protection issues. PMID:24277873

  10. Automatic Estimation of the Radiological Inventory for the Dismantling of Nuclear Facilities

    SciTech Connect

    Garcia-Bermejo, R.; Felipe, A.; Gutierrez, S.; Salas, E.; Martin, N.

    2008-01-15

    The estimation of the radiological inventory of Nuclear Facilities to be dismantled is a process that included information related with the physical inventory of all the plant and radiological survey. Estimation of the radiological inventory for all the components and civil structure of the plant could be obtained with mathematical models with statistical approach. A computer application has been developed in order to obtain the radiological inventory in an automatic way. Results: A computer application that is able to estimate the radiological inventory from the radiological measurements or the characterization program has been developed. In this computer applications has been included the statistical functions needed for the estimation of the central tendency and variability, e.g. mean, median, variance, confidence intervals, variance coefficients, etc. This computer application is a necessary tool in order to be able to estimate the radiological inventory of a nuclear facility and it is a powerful tool for decision taken in future sampling surveys.

  11. Decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East. Project final report

    SciTech Connect

    Fellhauer, C.R.; Clark, F.R.; Garlock, G.A.

    1997-10-01

    The decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East (ANL-E) was completed in October 1997. Descriptions and evaluations of the activities performed and analyses of the results obtained during the JANUS D and D Project are provided in this Final Report. The following information is included: objective of the JANUS D and D Project; history of the JANUS Reactor facility; description of the ANL-E site and the JANUS Reactor facility; overview of the D and D activities performed; description of the project planning and engineering; description of the D and D operations; summary of the final status of the JANUS Reactor facility based upon the final survey results; description of the health and safety aspects of the project, including personnel exposure and OSHA reporting; summary of the waste minimization techniques utilized and total waste generated by the project; and summary of the final cost and schedule for the JANUS D and D Project.

  12. Building dismantlement and site remediation at the Apollo Fuel Plant: When is technology the answer?

    SciTech Connect

    Walton, L.

    1995-01-01

    The Apollo fuel plant was located in Pennsylvania on a site known to have been used continuously for stell production from before the Civil War until after World War II. Then the site became a nuclear fuel chemical processing plants. Finally it was used to convert uranium hexafluoride to various oxide fuel forms. After the fuel manufacturing operations were teminated, the processing equipment was partially decontaminated, removed, packaged and shipped to a licensed low-level radioactive waste burial site. The work was completed in 1984. In 1990 a detailed site characterization was initiated to establishe the extent of contamination and to plan the building dismantlement and soil remediation efforts. This article discusses the site characterization and remedial action at the site in the following subsections: characterization; criticality control; mobile containment; soil washing; in-process measurements; and the final outcome of the project.

  13. Robotic dismantlement systems at the CP-5 reactor D&D project.

    SciTech Connect

    Seifert, L. S.

    1998-10-28

    The Chicago Pile 5 (CP-5) Research Reactor Facility is currently undergoing decontamination and decommissioning (D&D) at the Argonne National Laboratory (ANL) Illinois site. CP-5 was the principle nuclear reactor used to produce neutrons for scientific research at Argonne from 1954 to 1979. The CP-5 reactor was a heavy-water cooled and moderated, enriched uranium-fueled reactor with a graphite reflector. The CP-5 D&D project includes the disassembly, segmentation and removal of all the radioactive components, equipment and structures associated with the CP-5 facility. The Department of Energy's Robotics Technology Development Program and the Federal Energy Technology Center, Morgantown Office provided teleoperated, remote systems for use in the dismantlement of the CP-5 reactor assembly for tasks requiring remote dismantlement as part of the EM-50 Large-Scale Demonstration Program (LSDP). The teleoperated systems provided were the Dual Arm Work Platform (DAWP), the Rosie Mobile Teleoperated Robot Work System (ROSIE), and a remotely-operated crane control system with installed swing-reduction control system. Another remotely operated apparatus, a Brokk BM250, was loaned to ANL by the Princeton Plasma Physics Laboratory (PPPL). This machine is not teleoperated and was not part of the LSDP, but deserves some mention in this discussion. The DAWP is a robotic dismantlement system that includes a pair of Schilling Robotic Systems Titan III hydraulic manipulator arms mounted to a specially designed support platform: a hydraulic power unit (HPU) and a remote operator console. The DAWP is designed to be crane-suspended for remote positioning. ROSIE, developed by RedZone Robotics, Inc. is a mobile, electro-hydraulic, omnidirectional platform with a heavy-duty telescoping boom mounted to the platform's deck. The work system includes the mobile platform (locomotor), a power distribution unit (PDU) and a remote operator console. ROSIE moves about the reactor building floor

  14. Recovery and recycling of aluminum, copper, and precious metals from dismantled weapon components

    SciTech Connect

    Lutz, J.D.; Wheelis, W.T.; Gundiler, I.H.

    1995-02-01

    Sandia National Laboratories (SNL) is tasked to support the Department of Energy in the dismantlement and disposal of SNL designed weapon components. These components are sealed in a potting compound, and contain heavy metals, explosive, radioactive, and toxic materials in discrete sub-components. SNL developed and demonstrated a process to identify and remove the hazardous sub-components utilizing real-time radiography and abrasive water-jet cutting. The remaining components were then crushed, granulated, screened, and separated into an aluminum and a precious-and-base-metals fraction using air-tables. Plastics were further cleaned for disposal as non-hazardous waste. The New Mexico Bureau of Mines & Mineral Resources assisted SNL in investigation of size-reduction and separation technologies and in the development of a conceptual design for a mechanical separation system.

  15. Recovery and recycling of aluminum, copper, and precious metals from dismantled weapon components

    SciTech Connect

    Gundiler, I.H.; Lutz, J.D.; Wheelis, W.T.

    1994-03-03

    Sandia National Laboratories (SNL) is tasked to support The Department of Energy in the dismantlement and disposal of SNL designed weapon components. These components are sealed in a potting compound, and contain heavy metals, explosive, radioactive, and toxic materials. SNL developed a process to identify and remove the hazardous sub-components utilizing real-time radiography and abrasive water-jet cutting. The components were then crushed, granulated, screened, and separated into an aluminum and a precious-and-base-metals fraction using air-tables. Plastics were further cleaned for disposal as non-hazardous waste. New Mexico Bureau of Mines and Mineral Resources assisted SNL in investigation of size-reduction and separation technologies.

  16. Plutonium gamma-ray measurements for mutual reciprocal inspections of dismantled nuclear weapons

    SciTech Connect

    Koenig, Z.M.; Carlson, J.B.; Clark, D.; Gosnell, T.B.

    1995-07-01

    The O`Leary-Mikhailov agreement of March 1994 stated that the U.S. and the Russian Federation would engage in mutual reciprocal inspections (MRI) of fissile materials removed from dismantled nuclear weapons. It was decided to begin with the plutonium (Pu) removed from dismantled weapons and held in storage containers. Later discussions between U.S. and Russian technical experts led to the conclusion that, to achieve the O`Leary-Mikhailov objectives, Pu MRI would need to determine that the material in the containers has properties consistent with a nuclear-weapon component. Such a property is a {sup 240}Pu/{sup 239}Pu ratio consistent with weapons-grade material. One of the candidate inspection techniques under consideration for Pu MRI is to use a narrow region (630-670 keV) of the plutonium gamma-ray spectrum, taken with a high-purity germanium detector, to determine that it is weapons-grade plutonium as well as to estimate the minimum mass necessary to produce the observed gamma-ray intensity. We developed software (the Pu600 code) for instrument control and analysis especially for this purpose. In November 1994, U.S. and Russian scientists met at the Lawrence Livermore National Laboratory for joint experiments to evaluate candidate Pu MRI inspection techniques. In one of these experiments, gamma-ray intensities were measured from three unclassified weapons-grade plutonium source standards and one reactor-grade standard (21% {sup 240}pu). Using our software, we determined the {sup 240}Pu/{sup 239}Pu ratio of these standards to accuracies within {+-}10%, which is adequate for Pu MRI. The minimum mass estimates varied, as expected, directly with the exposed surface area of the standards.

  17. ICP0 Dismantles Microtubule Networks in Herpes Simplex Virus-Infected Cells

    PubMed Central

    Liu, Mingyu; Schmidt, Edward E.; Halford, William P.

    2010-01-01

    Infected-cell protein 0 (ICP0) is a RING finger E3 ligase that regulates herpes simplex virus (HSV) mRNA synthesis, and strongly influences the balance between latency and replication of HSV. For 25 years, the nuclear functions of ICP0 have been the subject of intense scrutiny. To obtain new clues about ICP0's mechanism of action, we constructed HSV-1 viruses that expressed GFP-tagged ICP0. To our surprise, both GFP-tagged and wild-type ICP0 were predominantly observed in the cytoplasm of HSV-infected cells. Although ICP0 is exclusively nuclear during the immediate-early phase of HSV infection, further analysis revealed that ICP0 translocated to the cytoplasm during the early phase where it triggered a previously unrecognized process; ICP0 dismantled the microtubule network of the host cell. A RING finger mutant of ICP0 efficiently bundled microtubules, but failed to disperse microtubule bundles. Synthesis of ICP0 proved to be necessary and sufficient to disrupt microtubule networks in HSV-infected and transfected cells. Plant and animal viruses encode many proteins that reorganize microtubules. However, this is the first report of a viral E3 ligase that regulates microtubule stability. Intriguingly, several cellular E3 ligases orchestrate microtubule disassembly and reassembly during mitosis. Our results suggest that ICP0 serves a dual role in the HSV life cycle, acting first as a nuclear regulator of viral mRNA synthesis and acting later, in the cytoplasm, to dismantle the host cell's microtubule network in preparation for virion synthesis and/or egress. PMID:20544015

  18. The use of non-destructive passive neutron measurement methods in dismantling and radioactive waste characterization

    SciTech Connect

    Jallu, F.; Allinei, P. G.; Bernard, P.; Loridon, J.; Soyer, P.; Pouyat, D.; Torreblanca, L.; Reneleau, A.

    2011-07-01

    The cleaning up and dismantling of nuclear facilities lead to a great volume of technological radioactive wastes which need to be characterized in order to be sent to the adequate final disposal or interim storage. The control and characterization can be performed with non-destructive nuclear measurements such as gamma-ray spectrometry. Passive neutron counting is an alternative when the alpha-gamma emitters cannot be detected due to the presence of a high gamma emission resulting from fission or activation products, or when the waste matrix is too absorbing for the gamma rays of interest (too dense and/or made of high atomic number elements). It can also be a complement to gamma-ray spectrometry when two measurement results must be confronted to improve the confidence in the activity assessment. Passive neutron assays involve the detection of spontaneous fission neutrons emitted by even nuclides ({sup 238}Pu, {sup 240}Pu, {sup 242}Pu, {sup 242}Cm, {sup 244}Cm...) and neutrons resulting from ({alpha}, n) reactions with light nuclides (O, F, Be...). The latter is conditioned by the presence of high {alpha}-activity radionuclides ({sup 234}U, {sup 238}Pu, {sup 240}Pu, {sup 241}Am...) and low-Z elements, which depends on the chemical form (metallic, oxide or fluorine) of the plutonium or uranium contaminant. This paper presents the recent application of passive neutron methods to the cleaning up of a nuclear facility located at CEA Cadarache (France), which concerns the Pu mass assessment of 2714 historic, 100 litre radioactive waste drums produced between 1980 and 1997. Another application is the dismantling and decommissioning of an uranium enrichment facility for military purposes, which involves the {sup 235}U and total uranium quantifications in about a thousand, large compressors employed in the gaseous diffusion enrichment process. (authors)

  19. 78 FR 43268 - Special Permit Applications

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-19

    ... Pipeline and Hazardous Materials Safety Administration Special Permit Applications AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice of actions on Special Permit..., special permits from the Department of Transportation's Hazardous Material Regulations (49 CFR Part...

  20. R2 PCS PERMITS GIS LAYER

    EPA Science Inventory

    The Region 2 PCS Permit Regulated Facility GIS layer contains identification (name, address, ID), and location (latitude, longitude, and locational metadata), attributes of facilities with National Polution Discharge Elimination Systems (NPDES) permit(s) in Region 2 that are reg...

  1. 40 CFR 72.62 - Draft permit.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... REGULATION Federal Acid Rain Permit Issuance Procedures § 72.62 Draft permit. (a) After the Administrator receives a complete Acid Rain permit application and any supplemental information, the Administrator...

  2. 40 CFR 72.62 - Draft permit.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... REGULATION Federal Acid Rain Permit Issuance Procedures § 72.62 Draft permit. (a) After the Administrator receives a complete Acid Rain permit application and any supplemental information, the Administrator...

  3. 40 CFR 72.62 - Draft permit.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... REGULATION Federal Acid Rain Permit Issuance Procedures § 72.62 Draft permit. (a) After the Administrator receives a complete Acid Rain permit application and any supplemental information, the Administrator...

  4. 40 CFR 72.62 - Draft permit.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... REGULATION Federal Acid Rain Permit Issuance Procedures § 72.62 Draft permit. (a) After the Administrator receives a complete Acid Rain permit application and any supplemental information, the Administrator...

  5. 30 CFR 736.25 - Permit fees.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... each acre of disturbed area or fraction thereof to be included in the permit area. (3) Permit issuance... review: Basic fee 1350.00 Fee per acre of disturbed area in permit area: First 1,000 acres...

  6. 40 CFR 52.1233 - Operating permits.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ...) APPROVAL AND PROMULGATION OF IMPLEMENTATION PLANS (CONTINUED) Minnesota § 52.1233 Operating permits. (a) Emission limitations and related provisions which are established in Minnesota permits as...

  7. 40 CFR 52.1233 - Operating permits.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ...) APPROVAL AND PROMULGATION OF IMPLEMENTATION PLANS (CONTINUED) Minnesota § 52.1233 Operating permits. (a) Emission limitations and related provisions which are established in Minnesota permits as...

  8. 40 CFR 52.1233 - Operating permits.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ...) APPROVAL AND PROMULGATION OF IMPLEMENTATION PLANS (CONTINUED) Minnesota § 52.1233 Operating permits. (a) Emission limitations and related provisions which are established in Minnesota permits as...

  9. 40 CFR 52.1233 - Operating permits.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ...) APPROVAL AND PROMULGATION OF IMPLEMENTATION PLANS (CONTINUED) Minnesota § 52.1233 Operating permits. (a) Emission limitations and related provisions which are established in Minnesota permits as...

  10. 40 CFR 52.872 - Operating permits.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ...) APPROVAL AND PROMULGATION OF IMPLEMENTATION PLANS Kansas § 52.872 Operating permits. Emission limitations and related provisions which are established in Kansas operating permits as Federally...

  11. 40 CFR 71.9 - Permit fees.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... revision, or permit renewal, including the development of an applicable requirement as part of the... administrative costs of the permit program, including transition planning, interagency coordination,...

  12. Calculation of the Activity Inventory for the TRIGA Reactor at the Medical University of Hannover (MHH) in Preparation for Dismantling the Facility

    SciTech Connect

    Hampel, G.; Scheller, F.; Bernnat, W.; Pfister, G.; Klaux, U.; Gerhards, E.

    2002-02-25

    It is planned to dismantle the TRIGA reactor facility at the Medical University of Hannover (MHH). Radioactive waste resulting from this dismantling will be disposed of externally, any remaining materials as well as the building structures will then be measured to ensure there is no residual activity. In preparation for this and to plan the techniques which will be used to dismantle the reactor, calculations were made in order to determine the amount of activity and the dose rates for the reactor tank and its inside components as well as for the biological shield and its radial beam tube.

  13. 41 CFR 102-74.500 - Can Federal agencies disapprove permit applications or cancel issued permits?

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... disapprove permit applications or cancel issued permits? 102-74.500 Section 102-74.500 Public Contracts and... Applications Or Cancellation of Permits § 102-74.500 Can Federal agencies disapprove permit applications or cancel issued permits? Yes, Federal agencies may disapprove any permit application or cancel an...

  14. 41 CFR 102-74.500 - Can Federal agencies disapprove permit applications or cancel issued permits?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... disapprove permit applications or cancel issued permits? 102-74.500 Section 102-74.500 Public Contracts and... Applications Or Cancellation of Permits § 102-74.500 Can Federal agencies disapprove permit applications or cancel issued permits? Yes, Federal agencies may disapprove any permit application or cancel an...

  15. 40 CFR 147.2906 - Emergency permits.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 40 Protection of Environment 22 2010-07-01 2010-07-01 false Emergency permits. 147.2906 Section...-Class II Wells § 147.2906 Emergency permits. (a) An emergency permit may be issued if: (1) There will be an imminent health hazard unless an emergency permit is issued; or (2) There will be a...

  16. 40 CFR 147.2906 - Emergency permits.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 40 Protection of Environment 23 2011-07-01 2011-07-01 false Emergency permits. 147.2906 Section...-Class II Wells § 147.2906 Emergency permits. (a) An emergency permit may be issued if: (1) There will be an imminent health hazard unless an emergency permit is issued; or (2) There will be a...

  17. 40 CFR 144.34 - Emergency permits.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 40 Protection of Environment 23 2011-07-01 2011-07-01 false Emergency permits. 144.34 Section 144...) UNDERGROUND INJECTION CONTROL PROGRAM Authorization by Permit § 144.34 Emergency permits. (a) Coverage... unless a temporary emergency permit is granted; or (2) A substantial and irretrievable loss of oil or...

  18. 40 CFR 144.34 - Emergency permits.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 40 Protection of Environment 22 2010-07-01 2010-07-01 false Emergency permits. 144.34 Section 144...) UNDERGROUND INJECTION CONTROL PROGRAM Authorization by Permit § 144.34 Emergency permits. (a) Coverage... unless a temporary emergency permit is granted; or (2) A substantial and irretrievable loss of oil or...

  19. 30 CFR 773.17 - Permit conditions.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 30 Mineral Resources 3 2011-07-01 2011-07-01 false Permit conditions. 773.17 Section 773.17 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR SURFACE COAL MINING AND RECLAMATION OPERATIONS PERMITS AND COAL EXPLORATION SYSTEMS UNDER REGULATORY PROGRAMS REQUIREMENTS FOR PERMITS AND PERMIT...

  20. 40 CFR 71.25 - Permit content.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 40 Protection of Environment 16 2013-07-01 2013-07-01 false Permit content. 71.25 Section 71.25 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) FEDERAL OPERATING PERMIT PROGRAMS Permits for Early Reductions Sources § 71.25 Permit content. (a) Standard...

  1. 40 CFR 71.25 - Permit content.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 40 Protection of Environment 15 2010-07-01 2010-07-01 false Permit content. 71.25 Section 71.25 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) FEDERAL OPERATING PERMIT PROGRAMS Permits for Early Reductions Sources § 71.25 Permit content. (a) Standard...

  2. 40 CFR 71.25 - Permit content.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 40 Protection of Environment 16 2012-07-01 2012-07-01 false Permit content. 71.25 Section 71.25 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) FEDERAL OPERATING PERMIT PROGRAMS Permits for Early Reductions Sources § 71.25 Permit content. (a) Standard...

  3. 40 CFR 71.25 - Permit content.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 40 Protection of Environment 15 2011-07-01 2011-07-01 false Permit content. 71.25 Section 71.25 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) FEDERAL OPERATING PERMIT PROGRAMS Permits for Early Reductions Sources § 71.25 Permit content. (a) Standard...

  4. 40 CFR 71.25 - Permit content.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 40 Protection of Environment 16 2014-07-01 2014-07-01 false Permit content. 71.25 Section 71.25 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) FEDERAL OPERATING PERMIT PROGRAMS Permits for Early Reductions Sources § 71.25 Permit content. (a) Standard...

  5. 10 CFR 50.23 - Construction permits.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 1 2012-01-01 2012-01-01 false Construction permits. 50.23 Section 50.23 Energy NUCLEAR... Description of Licenses § 50.23 Construction permits. A construction permit for the construction of a... part 52 of this chapter, the construction permit and operating license are deemed to be combined in...

  6. 10 CFR 50.23 - Construction permits.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Construction permits. 50.23 Section 50.23 Energy NUCLEAR... Description of Licenses § 50.23 Construction permits. A construction permit for the construction of a... part 52 of this chapter, the construction permit and operating license are deemed to be combined in...

  7. 10 CFR 50.23 - Construction permits.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 1 2014-01-01 2014-01-01 false Construction permits. 50.23 Section 50.23 Energy NUCLEAR... Description of Licenses § 50.23 Construction permits. A construction permit for the construction of a... part 52 of this chapter, the construction permit and operating license are deemed to be combined in...

  8. 10 CFR 50.23 - Construction permits.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 1 2013-01-01 2013-01-01 false Construction permits. 50.23 Section 50.23 Energy NUCLEAR... Description of Licenses § 50.23 Construction permits. A construction permit for the construction of a... part 52 of this chapter, the construction permit and operating license are deemed to be combined in...

  9. 40 CFR 72.62 - Draft permit.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Draft permit. 72.62 Section 72.62 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) PERMITS REGULATION Federal Acid Rain Permit Issuance Procedures § 72.62 Draft permit. (a) After the Administrator receives a complete Acid Rain...

  10. 40 CFR 71.9 - Permit fees.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 40 Protection of Environment 15 2010-07-01 2010-07-01 false Permit fees. 71.9 Section 71.9 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) FEDERAL OPERATING PERMIT PROGRAMS Operating Permits § 71.9 Permit fees. (a) Fee requirement. The owners or operators of part 71 sources shall pay annual fees,...

  11. 40 CFR 71.24 - Permit applications.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 40 Protection of Environment 16 2012-07-01 2012-07-01 false Permit applications. 71.24 Section 71.24 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) FEDERAL OPERATING PERMIT PROGRAMS Permits for Early Reductions Sources § 71.24 Permit applications. (a) Where to file. To apply for a...

  12. 40 CFR 71.24 - Permit applications.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 40 Protection of Environment 16 2014-07-01 2014-07-01 false Permit applications. 71.24 Section 71.24 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) FEDERAL OPERATING PERMIT PROGRAMS Permits for Early Reductions Sources § 71.24 Permit applications. (a) Where to file. To apply for a...

  13. 40 CFR 71.24 - Permit applications.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 40 Protection of Environment 16 2013-07-01 2013-07-01 false Permit applications. 71.24 Section 71.24 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) FEDERAL OPERATING PERMIT PROGRAMS Permits for Early Reductions Sources § 71.24 Permit applications. (a) Where to file. To apply for a...

  14. 40 CFR 144.33 - Area permits.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 40 Protection of Environment 23 2011-07-01 2011-07-01 false Area permits. 144.33 Section 144.33 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) UNDERGROUND INJECTION CONTROL PROGRAM Authorization by Permit § 144.33 Area permits. (a) The Director may issue a permit on an area basis, rather than...

  15. 50 CFR 622.90 - Permits.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ..., DEPARTMENT OF COMMERCE FISHERIES OF THE CARIBBEAN, GULF OF MEXICO, AND SOUTH ATLANTIC Red Drum Fishery of the Gulf of Mexico § 622.90 Permits. (a) Dealer permits and conditions—(1) Permits. For a dealer to first receive Gulf red drum harvested in or from the EEZ, a Gulf and South Atlantic dealer permit must be......

  16. 50 CFR 660.25 - Permits.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... in 50 CFR part 660, subparts C through G. (b) Limited entry permit—(1) Eligibility and registration... implementing regulations at 15 CFR part 904, subpart D, apply. (2) Mothership (MS) permit. The MS permit... 15 CFR part 904, subpart D. (2) All Shorebased IFQ Program permits (QS permit, first receiver...

  17. 45 CFR 670.13 - Permit administration.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 45 Public Welfare 3 2013-10-01 2013-10-01 false Permit administration. 670.13 Section 670.13 Public Welfare Regulations Relating to Public Welfare (Continued) NATIONAL SCIENCE FOUNDATION CONSERVATION OF ANTARCTIC ANIMALS AND PLANTS Permits § 670.13 Permit administration. (a) Issuance of the permits. The Director may approve any application...

  18. Industrial-user-permitting guidance manual

    SciTech Connect

    Not Available

    1989-09-01

    The manual provides publicly-owned treatment works (POTWs) with guidance on the development and issuance of effective industrial user permits. The manual addresses and expands upon minimum requirements and provides guidance on how to establish a permit program, procedures for permit issuance, procedures for writing a permit, and requirements for waste haulers. It is intended to assist new permit writers, experienced permit writers, and legal and administrative personnel who are involved in the implementation of an industrial user permitting program in preparing effective and enforceable industrial user permits. It provides documentation of EPA's recommendations for industrial user permit contents/structure. It contains many examples of sections and conditions of a permit, as well as complete sample permits and fact sheets. It also contains background info on requirements of the issuance process and discusses the necessary legal authority required to implement an effective program. Appendix A: Bibliography; Appendix B: List of State/Regional Pretreatment Coordinators; Appendix C: Glossary of Terms; Appendix D: Sample Sewer Use Ordinance Provisions for Permits; Appendix E: Sample Permit Application Form; Appendix F: Sample IU Permit; Appendix G: Sample Standard Conditions for Permits; Appendix H: IU Management Practices; Appendix I: Fact Sheet: Appendix J: Sample Waste Hauler Permit.

  19. 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

  20. Long term dismantling of a basaltic volcano (Piton des Neiges, La Réunion hotspot).

    NASA Astrophysics Data System (ADS)

    Chaput, Marie; Famin, Vincent; Michon, Laurent; Catry, Thibault

    2010-05-01

    We present a structural investigation of destabilization processes at the Piton des Neiges, the extinct volcano of La Reunion Island. We focus on the Cirque of Cilaos (a large erosional depression south of the volcano summit), where the exposed internal structure of Piton des Neiges is made of pahoehoe lava flows of the shield building stage (unknown thickness) and breccias (~1 km thick), covered by volcanic products of the differentiated stage (~1 km thick). The breccias contain only basic elements and consist in debris flows and debris avalanches deposits. Beddings in the debris flows and shear structures in the avalanche deposits indicate a runout in the direction 300°. We suggest that these breccias may represent the upper part of the Cap La Houssaye mass wasting events observed onshore and offshore on the western side of la Réunion (Bachèlery et al., 2003). The breccias display many indicators of brittle deformation, such as faults (normal and strike slip) and intrusions (dykes and sills). Fault data inversion allows to recognize two episodes of deformation. The first, older step of deformation is consistent with a minimum principal stress oriented N120. Intrusions related to this deformation are basic magmas of the shield building stage. The second, later stage of extension oriented N-S crosscuts the N120 deformation with intrusion compositions of the differentiated stage. These results show that the dismantling of Piton des Neiges proceeded in two ways: catastrophic episodic destabilization and slow internal deformation. During the shield-building stage, slow and rapid dismantling was occurring in the 300° direction in the studied area, whereas it evolved toward a N-S slow collapse during the differentiated stage of magmatic activity. This result fully agrees with a recent study carried out within debris avalanches deposits in the cirque of Salazie (north of Piton des Neiges summit) which attests that the northern flank of the Piton des Neiges has also

  1. Melting of the metallic wastes generated by dismantling retired nuclear research facilities

    SciTech Connect

    Chong-Hun Jung; Pyung-Seob Song; Byung-Youn Min; Wang-Kyu Choi

    2008-01-15

    The decommissioning of nuclear installations results in considerably large amounts of radioactive metallic wastes such as stainless steel, carbon steel, aluminum, copper etc. It is known that the reference 1,000 MWe PWR and 881 MWe PHWR will generate metal wastes of 24,800 ton and 26,500 ton, respectively. In Korea, the D and D of KRR-2 and a UCP at KAERI have been performed. The amount of metallic wastes from the KRR-1 and UCP was about 160 ton and 45 ton, respectively, up to now. These radioactive metallic wastes will induce problems of handling and storing these materials from environmental and economical aspects. For this reason, prompt countermeasures should be taken to deal with the metal wastes generated by dismantling retired nuclear facilities. The most interesting materials among the radioactive metal wastes are stainless steel (SUS), carbon steel (CS) and aluminum wastes because they are the largest portions of the metallic wastes generated by dismantling retired nuclear research facilities. As most of these steels are slightly contaminated, if they are properly treated they are able to be recycled and reused in the nuclear field. In general, the technology of a metal melting is regarded as one of the most effective methods to treat metallic wastes from nuclear facilities. In conclusion: The melting of metal wastes (Al, SUS, carbon steel) from a decommissioning of research reactor facilities was carried out with the use of a radioisotope such as cobalt and cesium in an electric arc furnace. In the aluminum melting tests, the cobalt was captured at up to 75% into the slag phase. Most of the cesium was completely eliminated from the aluminum ingot phase and moved into the slag and dust phases. In the melting of the stainless steel wastes, the {sup 60}Co could almost be retained uniformly in the ingot phase. However, we found that significant amounts of {sup 60}Co remained in the slag at up to 15%. However the removal of the cobalt from the ingot phase was

  2. Dismantling the RB-2 research reactor; An application of a radiation protection approach relevant to Italy's decommissioning methodology

    SciTech Connect

    Laraia, M. ); Brighenti, G.; Camiscioni, B. Via Sabbionara, 611, 40059 Medicina ); Chessa, G. )

    1989-08-01

    The RB-2 research reactor was operated for 17 yr at power levels of the order of 10kW (1963-1969) and 100W (1971-1980). During dismantling, the radiological risk for personnel was recognizable low, but radioactivity levels associated with the waste materials and the site itself needed to be evaluated. Predismantling activities consisted of a preliminary radiological characterization, including direct measurements, spectrometric analyses of samples, and theoretical calculations. Determination of nonradioactive limits determined the disposition of the site and the transportation routes for the waste materials. After dismantling, the site was extensively monitored for remaining radioactivity. In general, unrestricted release has been achievable for the site; only a small area is still subject to radiological control.

  3. Aspects of operational radiation protection during dismantling of nuclear facilities relevant for the estimation of internal doses.

    PubMed

    Labarta, T

    2007-01-01

    Operational radiation protection of workers during the dismantling of nuclear facilities is based on the same radiation protection principles as that applied in its exploitation period with the objective of ensuring proper implementation of the as-low-as-reasonably-achievable (ALARA) principle. These principles are: prior determination of the nature and magnitude of radiological risk; classification of workplaces and workers depending on the risks; implementation of control measures; monitoring of zones and working conditions, including, if necessary, individual monitoring. From the experiences and the lessons learned during the dismantling processes carried out in Spain, several important aspects in the practical implementation of these principles that directly influence and ensure an adequate prevention of exposures and the estimation of internal doses are pointed out, with special emphasis on the estimation of internal doses due to transuranic intakes. PMID:17951606

  4. 49 CFR 1242.30 - Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39, 62-17...

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 49 Transportation 9 2011-10-01 2011-10-01 false Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39, 62-17-00, 62-18-00, and 62-19-00). 1242.30 Section 1242.30....30 Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39,...

  5. 49 CFR 1242.30 - Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39, 62-17...

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 49 Transportation 9 2010-10-01 2010-10-01 false Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39, 62-17-00, 62-18-00, and 62-19-00). 1242.30 Section 1242.30....30 Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39,...

  6. 49 CFR 1242.30 - Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39, 62-17...

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 49 Transportation 9 2012-10-01 2012-10-01 false Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39, 62-17-00, 62-18-00, and 62-19-00). 1242.30 Section 1242.30....30 Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39,...

  7. 49 CFR 1242.30 - Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39, 62-17...

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 49 Transportation 9 2014-10-01 2014-10-01 false Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39, 62-17-00, 62-18-00, and 62-19-00). 1242.30 Section 1242.30....30 Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39,...

  8. 49 CFR 1242.30 - Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39, 62-17...

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 49 Transportation 9 2013-10-01 2013-10-01 false Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39, 62-17-00, 62-18-00, and 62-19-00). 1242.30 Section 1242.30....30 Dismantling retired road property and depreciation (accounts XX-17-39, XX-18-39, XX-19-39,...

  9. [Pollution Characteristics and Ecological Risk of PBDEs in Water and Sediment from an Electronic Waste Dismantling Area in Taizhou].

    PubMed

    Chen, Xiang-ping; Peng, Bao-qi; Lü, Su-ping; Chen, Qiang; Zhang, Yong; Huang, Chang-jiang; Dong, Qiao-xiang

    2016-05-15

    An e-waste dismantling industrial park of Taizhou was selected as the sampling center, within a radius of 16 km, and a total of 30 sampling sites were designed in three circles as follows: C (3 km), S (5-10 km) and R (10-16 km). Pollution characteristics and ecological risk of polybrominated diphenyl ethers (PBDEs) in water and sediments were investigated. The concentrations of PBDEs in water ranged from 9.4 to 57.2 ng · L⁻¹, with a mean value of 25.9 ng · L⁻¹; and 3.7 to 38,775 ng · g⁻¹, with an average of 2 779 ng · g⁻¹ in sediments. BDE-209 was the predominant congener. The spatial distribution patterns of PBDE levels in water and sediment were both in the following order: C > S > R. Furthermore, the concentrations of PBDEs in sediments showed significant negative correlation against the distance from the industrial park (P < 0.01). Compared with other regions around the world, the PBDEs contamination was more serious in the area, which indicated that e-waste dismantling activity was one of the significant sources for PBDEs pollution. It was estimated that a total of 30. 7 t PBDEs (including 28. 9 t BDE- 209) was discharged into surrounding environment as a result of dismantling industrial activities in last 40 years. A preliminary ecological risk assessment for PBDEs in water and sediments was conducted by hazard quotient method. The results demonstrated that the Penta-BDEs in the center of e-waste dismantling area ( a radius of 1.5 km) was at particularly high risk level and could cause serious influence on the ecological safety and human health. PMID:27506030

  10. Flow analysis of heavy metals in a pilot-scale incinerator for residues from waste electrical and electronic equipment dismantling.

    PubMed

    Long, Yu-Yang; Feng, Yi-Jian; Cai, Si-Shi; Ding, Wei-Xu; Shen, Dong-Sheng

    2013-10-15

    The large amount of residues generated from dismantling waste electrical and electronic equipment (WEEE) results in a considerable environmental burden. We used material flow analysis to investigate heavy metal behavior in an incineration plant in China used exclusively to incinerate residues from WEEE dismantling. The heavy metals tested were enriched in the bottom and fly ashes after incineration. However, the contents of heavy metals in the bottom ash, fly ash and exhaust gas do not have a significant correlation with that of the input waste. The evaporation and recondensation behavior of heavy metals caused their contents to differ with air pollution control equipment because of the temperature difference during gas venting. Among the heavy metals tested, Cd had the strongest tendency to transfer during incineration (TCd=69.5%) because it had the lowest melting point, followed by Cu, Ni, Pb and Zn. The exchangeable and residual fractions of heavy metals increased substantially in the incineration products compared with that of the input residues. Although the mass of residues from WEEE dismantling can be reduced by 70% by incineration, the safe disposal of the metal-enriched bottom and fly ashes is still required. PMID:23973476

  11. PcrA helicase dismantles RecA filaments by reeling in DNA in uniform steps

    PubMed Central

    Park, Jeehae; Myong, Sua; Niedziela-Majka, Anita; Yu, Jin; Lohman, Timothy M.; Ha, Taekjip

    2010-01-01

    Translocation of helicase-like proteins on nucleic acids underlies key cellular functions. However, it is still unclear how translocation can drive removal of DNA bound proteins, and basic properties like the elementary step size remain controversial. Using single molecule fluorescence analysis on a prototypical superfamily 1 helicase, Bacillus stearothermophilus PcrA, we discovered that PcrA preferentially translocates on the DNA lagging strand instead of unwinding the template duplex. PcrA anchors itself to the template duplex using the 2B subdomain and reels in the lagging strand, extruding a single stranded loop. Static disorder limited previous ensemble studies of PcrA stepping mechanism. Here, highly repetitive looping revealed that PcrA translocates in uniform steps of 1 nt. This reeling-in activity requires the open conformation of PcrA and can rapidly dismantle a preformed RecA filament even at low PcrA concentrations suggesting a mode of action for eliminating potentially deleterious recombination intermediates. PMID:20723756

  12. PcrA helicase dismantles RecA filaments by reeling in DNA in uniform steps.

    PubMed

    Park, Jeehae; Myong, Sua; Niedziela-Majka, Anita; Lee, Kyung Suk; Yu, Jin; Lohman, Timothy M; Ha, Taekjip

    2010-08-20

    Translocation of helicase-like proteins on nucleic acids underlies key cellular functions. However, it is still unclear how translocation can drive removal of DNA-bound proteins, and basic properties like the elementary step size remain controversial. Using single-molecule fluorescence analysis on a prototypical superfamily 1 helicase, Bacillus stearothermophilus PcrA, we discovered that PcrA preferentially translocates on the DNA lagging strand instead of unwinding the template duplex. PcrA anchors itself to the template duplex using the 2B subdomain and reels in the lagging strand, extruding a single-stranded loop. Static disorder limited previous ensemble studies of a PcrA stepping mechanism. Here, highly repetitive looping revealed that PcrA translocates in uniform steps of 1 nt. This reeling-in activity requires the open conformation of PcrA and can rapidly dismantle a preformed RecA filament even at low PcrA concentrations, suggesting a mode of action for eliminating potentially deleterious recombination intermediates. PMID:20723756

  13. Integration of Environmental Restoration and Decontamination and Dismantlement Requirements at the INEEL

    SciTech Connect

    C. L. Reese; D. J. Kuhns

    1999-02-01

    In 1997, the Environmental Restoration Program at the Idaho National Engineering and Environmental Laboratory (INEEL) determined that it was necessary to remediate a Comprehensive Environmental Response and Liability Act (CERCLA) site to address the risk of subsurface petroleum contamination to human health and the environment. This cleanup project was conducted utilizing the Non-time Critical Removal Action process. Due to the close proximity (above the contaminated soil) of a number of above ground storage tanks and a building, the CERCLA project team worked closely with the D&D group to ensure all requirements for each program were met. Lessons learned and regulatory requirements are discussed in the paper, including the factors unknown to many ER personnel regarding the steps required to be completed prior to the dismantlement of structures. The paper summarizes the background associated with the site, why the removal action was conducted, the scope of the removal action, and the results. The emphasis of the paper is to discuss the integration between ER and D&D requirements and processes. In the current environment where ER and D&D activities are commingled, it is imperative that ER and D&D personnel are aware of the requirements imposed upon each program. By working together and building upon the strengths of each program, the INEEL�s 1997 removal action was a tremendous success.

  14. Integration of Environmental Restoration and Decontamination and Dismantlement Requirements at the INEEL

    SciTech Connect

    Kuhns, Douglass Jack; Reese, Craig Lyle

    1999-03-01

    In 1997, the Environmental Restoration Program at the Idaho National Engineering and Environmental Laboratory (INEEL) determined that it was necessary to remediate a Comprehensive Environmental Response and Liability Act (CERCLA) site to address the risk of subsurface petroleum contamination to human health and the environment. This cleanup project was conducted utilizing the Non-time Critical Removal Action process. Due to the close proximity (above the contaminated soil) of a number of above ground storage tanks and a building, the CERCLA project team worked closely with the D&D group to ensure all requirements for each program were met. Lessons learned and regulatory requirements will be discussed in the paper, including the factors unknown to many ER personnel regarding the steps required to be completed prior to the dismantlement of structures. The paper will summarize the background associated with the site, why the removal action was conducted, the scope of the removal action, and the results. The emphasis of the paper will discuss the integration between ER and D&D requirements and processes. In the current environment where ER and D&D activities are commingled, it is imperative that ER and D&D personnel are aware of the requirements imposed upon each program. By working together and building upon the strengths of each program, the INEEL’s 1997 removal action was a tremendous success.

  15. The feasibility of improving CBT for childhood anxiety disorders through a dismantling study.

    PubMed

    Whiteside, Stephen P H; Ale, Chelsea M; Young, Brennan; Dammann, Julie E; Tiede, Michael S; Biggs, Bridget K

    2015-10-01

    This preliminary randomized controlled trial (RCT) examines the feasibility of dismantling cognitive behavioral therapy (CBT) for childhood anxiety disorders. Fourteen children (10 girls) ages 7 to 14 (m = 10.2) with social phobia, generalized anxiety disorder, separation anxiety disorder, or panic disorder were randomized to receive 6 sessions of either a) the pre-exposure anxiety management strategies presented in traditional CBT, or b) parent-coached exposure therapy. The sample was selected from a treatment seeking population and is representative of children in clinical settings. Examination of fidelity ratings, dropouts, and satisfaction ratings indicated that the interventions were distinguishable, safe, and tolerable. The overall sample improved significantly with pre-post effect sizes generally in the large range for both conditions. Between-group effect sizes indicating greater improvement with parent-coached exposure therapy were moderate or large for ten of 12 variables (i.e., 0.53 to 1.52). Re-evaluation after three months of open treatment suggested that the intervention emphasizing exposure early maintained its superiority while requiring fewer appointments. PMID:26275761

  16. Post-decontamination and dismantlement (D&D) characterization report for CFA-669 site

    SciTech Connect

    Smith, D.L.

    1995-01-01

    This report presents results of post-decontamination and dismantling (D&D) characterization surveys performed by EG&G Idaho, Inc. (EG&G Idaho), at Central Facilities Area (CFA)-669, which was the Hot Laundry Facility. The site was characterized to determine and document the radiological and chemical conditions of the site following D&D and to determine if the site satisfies the release criteria. Constructed in 1950, CFA-669 served as the ``hot`` and ``cold`` laundry for Idaho National Engineering Laboratory site contractors until the boiler exploded in 1981. The building was shut down at that time. Before D&D activities began in 1992, the facility was characterized and the results documented. D&D activities were completed in July 1994. The post-D&D radiological characterization consisted of radiation measurements and analyses of soil samples to identify man-made radionuclides and determine the specific activity of each sample. The chemical characterization consisted of toxicity characterization leaching procedure (TCLP) analysis for metals and for volatile and semivolatile organic contamination.

  17. Characterisation and materials flow management for waste electrical and electronic equipment plastics from German dismantling centres.

    PubMed

    Arends, Dagmar; Schlummer, Martin; Mäurer, Andreas; Markowski, Jens; Wagenknecht, Udo

    2015-09-01

    Waste electrical and electronic equipment is a complex waste stream and treatment options that work for one waste category or product may not be appropriate for others. A comprehensive case study has been performed for plastic-rich fractions that are treated in German dismantling centres. Plastics from TVs, monitors and printers and small household appliances have been characterised extensively. Based on the characterisation results, state-of-the-art treatment technologies have been combined to design an optimised recycling and upgrade process for each input fraction. High-impact polystyrene from TV casings that complies with the European directive on the restriction of hazardous substances (RoHS) was produced by applying continuous density separation with yields of about 60%. Valuable acrylonitrile butadiene styrene/polycarbonate can be extracted from monitor and printer casings by near-infrared-based sorting. Polyolefins and/or a halogen-free fraction of mixed styrenics can be sorted out by density separation from monitors and printers and small household appliances. Emerging separation technologies are discussed to improve recycling results. PMID:26111535

  18. UvrD helicase, unlike Rep helicase, dismantles RecA nucleoprotein filaments in Escherichia coli.

    PubMed

    Veaute, Xavier; Delmas, Stéphane; Selva, Marjorie; Jeusset, Josette; Le Cam, Eric; Matic, Ivan; Fabre, Francis; Petit, Marie-Agnès

    2005-01-12

    The roles of UvrD and Rep DNA helicases of Escherichia coli are not yet fully understood. In particular, the reason for rep uvrD double mutant lethality remains obscure. We reported earlier that mutations in recF, recO or recR genes suppress the lethality of uvrD rep, and proposed that an essential activity common to UvrD and Rep is either to participate in the removal of toxic recombination intermediates or to favour the proper progression of replication. Here, we show that UvrD, but not Rep, directly prevents homologous recombination in vivo. In addition to RecFOR, we provide evidence that RecA contributes to toxicity in the rep uvrD mutant. In vitro, UvrD dismantles the RecA nucleoprotein filament, while Rep has only a marginal activity. We conclude that UvrD and Rep do not share a common activity that is essential in vivo: while Rep appears to act at the replication stage, UvrD plays a role of RecA nucleoprotein filament remover. This activity of UvrD is similar to that of the yeast Srs2 helicase. PMID:15565170

  19. Dismantling of the 904 Cell at the HAO/Sud Facility - 13466

    SciTech Connect

    Vaudey, C.E.; Crosnier, S.; Renouf, M.; Gaspard, N.; Pinot, L.

    2013-07-01

    La Hague facility, in France, is the spent fuel recycling plant wherein a part of the fuel coming from some of the French, German, Belgian, Swiss, Dutch and Japanese nuclear reactors is reprocessed before being recycled in order to separate certain radioactive elements. The facility has been successively handled by the CEA (1962-1978), Cogema (1978-2006), and AREVA NC (since 2006). La Hague facility is composed of 3 production units: The UP2-400 production unit started to be operated in 1966 for the reprocessing of UNGG metal fuel. In 1976, following the dropout of the graphite-gas technology by EDF, an HAO workshop to reprocess the fuel from the light water reactors is affiliated and then stopped in 2003. - UP2-400 is partially stopped in 2002 and then definitely the 1 January 2004 and is being dismantled - UP2-800, with the same capacity than UP3, started to be operated in 1994 and is still in operation. And UP3 - UP3 was implemented in 1990 with an annual reprocessing capacity of 800 tons of fuel and is still in operation The combined licensed capacity of UP2-800 and UP3 is 1,700 tons of used fuel. (authors)

  20. Antibodies to gliomedin cause peripheral demyelinating neuropathy and the dismantling of the nodes of Ranvier.

    PubMed

    Devaux, Jérôme J

    2012-10-01

    Guillain-Barré syndrome (GBS) and chronic inflammatory demyelinating polyneuropathy (CIDP) are conditions that affect peripheral nerves. The mechanisms that underlie demyelination in these neuropathies are unknown. Recently, we demonstrated that the node of Ranvier is the primary site of the immune attack in patients with GBS and CIDP. In particular, GBS patients have antibodies against gliomedin and neurofascin, two adhesion molecules that play a crucial role in the formation of nodes of Ranvier. We demonstrate that immunity toward gliomedin, but not neurofascin, induced a progressive neuropathy in Lewis rats characterized by conduction defects and demyelination in spinal nerves. The clinical symptoms closely followed the titers of anti-gliomedin IgG and were associated with an important deposition of IgG at nodes. Furthermore, passive transfer of antigliomedin IgG induced a severe demyelinating condition and conduction loss. In both active and passive models, the immune attack at nodes occasioned the loss of the nodal clusters for gliomedin, neurofascin-186, and voltage-gated sodium channels. These results indicate that primary immune reaction against gliomedin, a peripheral nervous system adhesion molecule, can be responsible for the initiation or progression of the demyelinating form of GBS. Furthermore, these autoantibodies affect saltatory propagation by dismantling nodal organization and sodium channel clusters. Antibodies reactive against nodal adhesion molecules thus likely participate in the pathologic process of GBS and CIDP. PMID:22885108

  1. Evaluating and planning the radioactive waste options for dismantling the Tokamak Fusion Test Reactor

    SciTech Connect

    Rule, K.; Scott, J.; Larson, S.

    1995-12-31

    The Tokamak Fusion Test Reactor (TFTR) is a one-of-a kind tritium fusion research reactor, and is planned to be decommissioned within the next several years. This is the largest fusion reactor in the world and as a result of deuterium-tritum reactions is tritium contaminated and activated from 14 Mev neutrons. This presents many unusual challenges when dismantling, packaging and disposing its components and ancillary systems. Special containers are being designed to accommodate the vacuum vessel, neutral beams, and tritium delivery and processing systems. A team of experienced professionals performed a detailed field study to evaluate the requirements and appropriate methods for packaging the radioactive materials. This team focused on several current and innovative methods for waste minimization that provides the oppurtunmost cost effective manner to package and dispose of the waste. This study also produces a functional time-phased schedule which conjoins the waste volume, weight, costs and container requirements with the detailed project activity schedule for the entire project scope. This study and project will be the first demonstration of the decommissioning of a tritium fusion test reactor. The radioactive waste disposal aspects of this project are instrumental in demonstrating the viability of a fusion power reactor with regard to its environmental impact and ultimate success.

  2. Remote-controlled dismantling of a nuclear power plant Kernkraftwerk Niederaichbach (KKN)

    SciTech Connect

    Ebbinghaus, K.; Orwantschke, D.

    1996-12-31

    Bavaria was the first in Europe to completely decommission a nuclear power plant and return the site to a green field condition. KKN, the prototype in Niederaichbach (HWGR, 100 MWe), was constructed from 1966 to 1972. During trial runs in 1973 and 1974, the plant operated up to 40% of nominal power and subsequently closed due to problems with the steam generators. The first step of decommission, which took place in 1981, was the transferral of the plant into a {open_quotes}SAFE ENCLOSURE{close_quotes} (IAEA decommissioning stage 1/2) and then completely dismantled in a federal project managed by the Karlsruhe research center, with decommissioning carried out under a {open_quotes}turnkey contract{close_quotes} by a consortium composed of Preussag Noell (leader) and NIS (IAE4 decommissioning stage 3). The first license was applied for in 1980. The project was completed in August 1995 with the planting of a tree on the restored Niederaichbach green field site.

  3. Proceedings of the workshop on transite decontamination dismantlement and recycle/disposal

    SciTech Connect

    Not Available

    1993-12-31

    On February 3--4, 1993, a workshop was conducted to examine issues associated with the decontamination, dismantlement, and recycle/disposal of transite located at the US Department of Energy Fernald site near Cincinnati, OH. The Fernald Environmental Management Project (FEMP) is a Superfund Site currently undergoing remediation. A major objective of the workshop was to assess the state-of-the-art of transite remediation, and generate concepts that could be useful to the Fernald Environmental Restoration Management Co. (FERMCO) for remediation of transite. Transite is a building material consisting of asbestos fiber and cement and may be radioactively contaminated as a result of past uranium processing operations at the FEMP. Many of the 100 buildings within the former uranium production area were constructed of transite siding and roofing and consequently, over 180,000 m{sup 2} of transite must be disposed or recycled. Thirty-six participants representing industry, academia, and government institutions such as the EPA and DOE assembled at the workshop to present their experience with transite, describe work in progress, and address the issues involved in remediating transite.

  4. 27 CFR 71.49a - Applications for operating permits and industrial use permits.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... permits and industrial use permits. 71.49a Section 71.49a Alcohol, Tobacco Products and Firearms ALCOHOL... and industrial use permits. If, on examination of an application for an operating permit or an industrial use permit, the appropriate TTB officer has reason to believe: (a) In case of an application...

  5. 27 CFR 71.48 - Operating permits and industrial use permits.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... industrial use permits. 71.48 Section 71.48 Alcohol, Tobacco Products and Firearms ALCOHOL AND TOBACCO TAX... PERMIT PROCEEDINGS Grounds for Citation § 71.48 Operating permits and industrial use permits. Whenever... industrial use permit: (a) Has not in good faith complied with the provisions of 26 U.S.C. chapter 51...

  6. 27 CFR 71.49a - Applications for operating permits and industrial use permits.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... permits and industrial use permits. 71.49a Section 71.49a Alcohol, Tobacco Products and Firearms ALCOHOL... and industrial use permits. If, on examination of an application for an operating permit or an industrial use permit, the appropriate TTB officer has reason to believe: (a) In case of an application...

  7. 27 CFR 71.48 - Operating permits and industrial use permits.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... industrial use permits. 71.48 Section 71.48 Alcohol, Tobacco Products and Firearms ALCOHOL AND TOBACCO TAX... PERMIT PROCEEDINGS Grounds for Citation § 71.48 Operating permits and industrial use permits. Whenever... industrial use permit: (a) Has not in good faith complied with the provisions of 26 U.S.C. chapter 51...

  8. 27 CFR 71.48 - Operating permits and industrial use permits.

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... industrial use permits. 71.48 Section 71.48 Alcohol, Tobacco Products and Firearms ALCOHOL AND TOBACCO TAX... PERMIT PROCEEDINGS Grounds for Citation § 71.48 Operating permits and industrial use permits. Whenever... industrial use permit: (a) Has not in good faith complied with the provisions of 26 U.S.C. chapter 51...

  9. 27 CFR 71.48 - Operating permits and industrial use permits.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... industrial use permits. 71.48 Section 71.48 Alcohol, Tobacco Products and Firearms ALCOHOL AND TOBACCO TAX... PERMIT PROCEEDINGS Grounds for Citation § 71.48 Operating permits and industrial use permits. Whenever... industrial use permit: (a) Has not in good faith complied with the provisions of 26 U.S.C. chapter 51...

  10. 27 CFR 71.49a - Applications for operating permits and industrial use permits.

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... permits and industrial use permits. 71.49a Section 71.49a Alcohol, Tobacco Products and Firearms ALCOHOL... and industrial use permits. If, on examination of an application for an operating permit or an industrial use permit, the appropriate TTB officer has reason to believe: (a) In case of an application...