Hybrid statistical testing for nuclear material accounting data and/or process monitoring data in nuclear safeguards

DOE PAGES

Burr, Tom; Hamada, Michael S.; Ticknor, Larry; ...

2015-01-01

The aim of nuclear safeguards is to ensure that special nuclear material is used for peaceful purposes. Historically, nuclear material accounting (NMA) has provided the quantitative basis for monitoring for nuclear material loss or diversion, and process monitoring (PM) data is collected by the operator to monitor the process. PM data typically support NMA in various ways, often by providing a basis to estimate some of the in-process nuclear material inventory. We develop options for combining PM residuals and NMA residuals (residual = measurement - prediction), using a hybrid of period-driven and data-driven hypothesis testing. The modified statistical tests canmore » be used on time series of NMA residuals (the NMA residual is the familiar material balance), or on a combination of PM and NMA residuals. The PM residuals can be generated on a fixed time schedule or as events occur.« less

Detection of shielded nuclear material in a cargo container

NASA Astrophysics Data System (ADS)

Jones, James L.; Norman, Daren R.; Haskell, Kevin J.; Sterbentz, James W.; Yoon, Woo Y.; Watson, Scott M.; Johnson, James T.; Zabriskie, John M.; Bennett, Brion D.; Watson, Richard W.; Moss, Cavin E.; Frank Harmon, J.

2006-06-01

The Idaho National Laboratory, along with Los Alamos National Laboratory and the Idaho State University's Idaho Accelerator Center, are developing electron accelerator-based, photonuclear inspection technologies for the detection of shielded nuclear material within air-, rail-, and especially, maritime-cargo transportation containers. This paper describes a developing prototypical cargo container inspection system utilizing the Pulsed Photonuclear Assessment (PPA) technology, incorporates interchangeable, well-defined, contraband shielding structures (i.e., "calibration" pallets) providing realistic detection data for induced radiation signatures from smuggled nuclear material, and provides various shielded nuclear material detection results. Using a 4.8-kg quantity of depleted uranium, neutron and gamma-ray detection responses are presented for well-defined shielded and unshielded configurations evaluated in a selected cargo container inspection configuration.

Nuclear Forensic Science: Analysis of Nuclear Material Out of Regulatory Control

NASA Astrophysics Data System (ADS)

Kristo, Michael J.; Gaffney, Amy M.; Marks, Naomi; Knight, Kim; Cassata, William S.; Hutcheon, Ian D.

2016-06-01

Nuclear forensic science seeks to identify the origin of nuclear materials found outside regulatory control. It is increasingly recognized as an integral part of a robust nuclear security program. This review highlights areas of active, evolving research in nuclear forensics, with a focus on analytical techniques commonly employed in Earth and planetary sciences. Applications of nuclear forensics to uranium ore concentrates (UOCs) are discussed first. UOCs have become an attractive target for nuclear forensic researchers because of the richness in impurities compared to materials produced later in the fuel cycle. The development of chronometric methods for age dating nuclear materials is then discussed, with an emphasis on improvements in accuracy that have been gained from measurements of multiple radioisotopic systems. Finally, papers that report on casework are reviewed, to provide a window into current scientific practice.

Development of Curricula for Nuclear Radiation Protection, Nuclear Instrumentation, and Nuclear Materials Processing Technologies. Final Report.

ERIC Educational Resources Information Center

Hull, Daniel M.

A study was conducted to assist two-year postsecondary educational institutions in providing technical specialty courses for preparing nuclear technicians. As a result of project activities, curricula have been developed for five categories of nuclear technicians and operators: (1) radiation protection technician, (2) nuclear instrumentation and…

Nuclear forensics of a non-traditional sample: Neptunium

DOE Office of Scientific and Technical Information (OSTI.GOV)

Doyle, Jamie L.; Schwartz, Daniel; Tandon, Lav

Recent nuclear forensics cases have focused primarily on plutonium (Pu) and uranium (U) materials. By definition however, nuclear forensics can apply to any diverted nuclear material. This includes neptunium (Np), an internationally safeguarded material like Pu and U, that could offer a nuclear security concern if significant quantities were found outside of regulatory control. This case study couples scanning electron microscopy (SEM) with quantitative analysis using newly developed specialized software, to evaluate a non-traditional nuclear forensic sample of Np. Here, the results of the morphological analyses were compared with another Np sample of known pedigree, as well as other traditionalmore » actinide materials in order to determine potential processing and point-of-origin.« less

Nuclear forensics of a non-traditional sample: Neptunium

DOE PAGES

Doyle, Jamie L.; Schwartz, Daniel; Tandon, Lav

2016-05-16

Recent nuclear forensics cases have focused primarily on plutonium (Pu) and uranium (U) materials. By definition however, nuclear forensics can apply to any diverted nuclear material. This includes neptunium (Np), an internationally safeguarded material like Pu and U, that could offer a nuclear security concern if significant quantities were found outside of regulatory control. This case study couples scanning electron microscopy (SEM) with quantitative analysis using newly developed specialized software, to evaluate a non-traditional nuclear forensic sample of Np. Here, the results of the morphological analyses were compared with another Np sample of known pedigree, as well as other traditionalmore » actinide materials in order to determine potential processing and point-of-origin.« less

The Use of Basalt, Basalt Fibers and Modified Graphite for Nuclear Waste Repository - 12150

DOE Office of Scientific and Technical Information (OSTI.GOV)

Gulik, V.I.; Biland, A.B.

2012-07-01

New materials enhancing the isolation of radioactive waste and spent nuclear fuel are continuously being developed.. Our research suggests that basalt-based materials, including basalt roving chopped basalt fiber strands, basalt composite rebar and materials based on modified graphite, could be used for enhancing radioactive waste isolation during the storage and disposal phases and maintaining it during a significant portion of the post-closure phase. The basalt vitrification process of nuclear waste is a viable alternative to glass vitrification. Basalt roving, chopped basalt fiber strands and basalt composite rebars can significantly increase the strength and safety characteristics of nuclear waste and spentmore » nuclear fuel storages. Materials based on MG are optimal waterproofing materials for nuclear waste containers. (authors)« less

Summary of NR Program Prometheus Efforts

DOE Office of Scientific and Technical Information (OSTI.GOV)

J Ashcroft; C Eshelman

2006-02-08

The Naval Reactors Program led work on the development of a reactor plant system for the Prometheus space reactor program. The work centered on a 200 kWe electric reactor plant with a 15-20 year mission applicable to nuclear electric propulsion (NEP). After a review of all reactor and energy conversion alternatives, a direct gas Brayton reactor plant was selected for further development. The work performed subsequent to this selection included preliminary nuclear reactor and reactor plant design, development of instrumentation and control techniques, modeling reactor plant operational features, development and testing of core and plant material options, and development ofmore » an overall project plan. Prior to restructuring of the program, substantial progress had been made on defining reference plant operating conditions, defining reactor mechanical, thermal and nuclear performance, understanding the capabilities and uncertainties provided by material alternatives, and planning non-nuclear and nuclear system testing. The mission requirements for the envisioned NEP missions cannot be accommodated with existing reactor technologies. Therefore concurrent design, development and testing would be needed to deliver a functional reactor system. Fuel and material performance beyond the current state of the art is needed. There is very little national infrastructure available for fast reactor nuclear testing and associated materials development and testing. Surface mission requirements may be different enough to warrant different reactor design approaches and development of a generic multi-purpose reactor requires substantial sacrifice in performance capability for each mission.« less

The Science of Nuclear Materials: A Modular, Laboratory-based Curriculum

DOE Office of Scientific and Technical Information (OSTI.GOV)

Cahill, C.L., E-mail: cahill@gwu.edu; Feldman, G.; Briscoe, W.J.

The development of a curriculum for nuclear materials courses targeting students pursuing Master of Arts degrees at The George Washington University is described. The courses include basic concepts such as radiation and radioactivity as well as more complex topics such the nuclear fuel cycle, nuclear weapons, radiation detection and technological aspects of non-proliferation.

Keeping Nuclear Materials Secure

DOE Office of Scientific and Technical Information (OSTI.GOV)

None

For 50 years, Los Alamos National Laboratory has been helping to keep nuclear materials secure. We do this by developing instruments and training inspectors that are deployed to other countries to make sure materials such as uranium are being used for peaceful purposes and not diverted for use in weapons. These measures are called “nuclear safeguards,” and they help make the world a safer place.

Active Neutron-Based Interrogation System with D-D Neutron Source for Detection of Special Nuclear Materials

NASA Astrophysics Data System (ADS)

Takahashi, Y.; Misawa, T.; Yagi, T.; Pyeon, C. H.; Kimura, M.; Masuda, K.; Ohgaki, H.

2015-10-01

The detection of special nuclear materials (SNM) is an important issue for nuclear security. The interrogation systems used in a sea port and an airport are developed in the world. The active neutron-based interrogation system is the one of the candidates. We are developing the active neutron-based interrogation system with a D-D fusion neutron source for the nuclear security application. The D-D neutron source is a compact discharge-type fusion neutron source called IEC (Inertial-Electrostatic Confinement fusion) device which provides 2.45 MeV neutrons. The nuclear materials emit the highenergy neutrons by fission reaction. High-energy neutrons with energies over 2.45 MeV amount to 30% of all the fission neutrons. By using the D-D neutron source, the detection of SNMs is considered to be possible with the attention of fast neutrons if there is over 2.45 MeV. Ideally, neutrons at En>2.45 MeV do not exist if there is no nuclear materials. The detection of fission neutrons over 2.45 MeV are hopeful prospect for the detection of SNM with a high S/N ratio. In the future, the experiments combined with nuclear materials and a D-D neutron source will be conducted. Furthermore, the interrogation system will be numerically investigated by using nuclear materials, a D-D neutron source, and a steel container.

Applications Using High Flux LCS gamma-ray Beams: Nuclear Security and Contributions to Fukushima

NASA Astrophysics Data System (ADS)

Fujiwara, Mamoru

2014-09-01

Nuclear nonproliferation and security are an important issue for the peaceful use of nuclear energy. Many countries now collaborate together for preventing serious accidents from nuclear terrorism. Detection of hidden long-lived radioisotopes and fissionable nuclides in a non-destructive manner is useful for nuclear safeguards and management of nuclear wastes as well as nuclear security. After introducing the present situation concerning the nuclear nonproliferation and security in Japan, we plan to show the present activities of JAEA to detect the hidden nuclear materials by means of the nuclear resonance fluorescence with energy-tunable, monochromatic gamma-rays generated by Laser Compton Scattering (LCS) with an electron beam. The energy recovery linac (ERL) machine is now under development with the KEK-JAEA collaboration for realizing the new generation of gamma-ray sources. The detection technologies of nuclear materials are currently developed using the existing electron beam facilities at Duke University and at NewSubaru. These developments in Japan will contribute to the nuclear security program in Japan and to the assay of melted nuclear fuels in the Fukushima Daiichi nuclear power plants.

Nuclear materials safeguards for the future

DOE Office of Scientific and Technical Information (OSTI.GOV)

Tape, J.W.

Basic concepts of domestic and international safeguards are described, with an emphasis on safeguards systems for the fuel cycles of commercial power reactors. Future trends in institutional and technical measures for nuclear materials safeguards are outlined. The conclusion is that continued developments in safeguards approaches and technology, coupled with institutional measures that facilitate the global management and protection of nuclear materials, are up to the challenge of safeguarding the growing inventories of nuclear materials in commercial fuel cycles in technologically advanced States with stable governments that have signed the nonproliferation treaty. These same approaches also show promise for facilitating internationalmore » inspection of excess weapons materials and verifying a fissile materials cutoff convention.« less

Specifics of MS training in the area of nuclear materials safe management for new-comers in nuclear power

NASA Astrophysics Data System (ADS)

Geraskin, N. I.; Glebov, V. B.

2017-01-01

The issues of specialists training in the field of nuclear materials safe management for the countries, who have taken a way of nuclear power development are analyzed. Arguments in justification of a need of these specialists training for the new-comers are adduced. The general characteristic of the reference MS program “Nuclear materials safe management” is considered. The peculiar features of the program, which is important for graduates from the new-comers have been analyzed. The best practices got as a result of implementation of the program in recent years for the students from Kazakhstan, Belarus, Azerbaijan, Tajikistan, Iran, Turkey and other countries are presented. Finally, the directions of international cooperation in further improvement and development of the program are considered.

Feasibility study of a gamma camera for monitoring nuclear materials in the PRIDE facility

NASA Astrophysics Data System (ADS)

Jo, Woo Jin; Kim, Hyun-Il; An, Su Jung; Lee, Chae Young; Song, Han-Kyeol; Chung, Yong Hyun; Shin, Hee-Sung; Ahn, Seong-Kyu; Park, Se-Hwan

2014-05-01

The Korea Atomic Energy Research Institute (KAERI) has been developing pyroprocessing technology, in which actinides are recovered together with plutonium. There is no pure plutonium stream in the process, so it has an advantage of proliferation resistance. Tracking and monitoring of nuclear materials through the pyroprocess can significantly improve the transparency of the operation and safeguards. An inactive engineering-scale integrated pyroprocess facility, which is the PyRoprocess Integrated inactive DEmonstration (PRIDE) facility, was constructed to demonstrate engineering-scale processes and the integration of each unit process. the PRIDE facility may be a good test bed to investigate the feasibility of a nuclear material monitoring system. In this study, we designed a gamma camera system for nuclear material monitoring in the PRIDE facility by using a Monte Carlo simulation, and we validated the feasibility of this system. Two scenarios, according to locations of the gamma camera, were simulated using GATE (GEANT4 Application for Tomographic Emission) version 6. A prototype gamma camera with a diverging-slat collimator was developed, and the simulated and experimented results agreed well with each other. These results indicate that a gamma camera to monitor the nuclear material in the PRIDE facility can be developed.

Long Duration Hot Hydrogen Exposure of Nuclear Thermal Rocket Materials

NASA Technical Reports Server (NTRS)

Litchford, Ron J.; Foote, John P.; Hickman, Robert; Dobson, Chris; Clifton, Scooter

2007-01-01

An arc-heater driven hyper-thermal convective environments simulator was recently developed and commissioned for long duration hot hydrogen exposure of nuclear thermal rocket materials. This newly established non-nuclear testing capability uses a high-power, multi-gas, wall-stabilized constricted arc-heater to .produce high-temperature pressurized hydrogen flows representative of nuclear reactor core environments, excepting radiation effects, and is intended to serve as a low cost test facility for the purpose of investigating and characterizing candidate fuel/structural materials and improving associated processing/fabrication techniques. Design and engineering development efforts are fully summarized, and facility operating characteristics are reported as determined from a series of baseline performance mapping runs and long duration capability demonstration tests.

Technology readiness levels for advanced nuclear fuels and materials development

DOE PAGES

Carmack, W. J.; Braase, L. A.; Wigeland, R. A.; ...

2016-12-23

The Technology Readiness Level (TRL) process is used to quantitatively assess the maturity of a given technology. It was pioneered by the National Aeronautics and Space Administration (NASA) in the 1980s to develop and deploy new systems for space applications. The process was subsequently adopted by the Department of Defense (DoD) to develop and deploy new technology and systems for defense applications as well as the Department of Energy (DOE) to evaluate the maturity of new technologies in major construction projects. Advanced nuclear fuels and materials development is a critical technology needed for improving the performance and safety of currentmore » and advanced reactors, and ultimately closing the nuclear fuel cycle. Because deployment of new nuclear fuel forms requires a lengthy and expensive research, development, and demonstration program, applying the TRL concept to the advanced fuel development program is very useful as a management, communication and tracking tool. Furthermore, this article provides examples regarding the methods by which TRLs are currently used to assess the maturity of nuclear fuels and materials under development in the DOE Fuel Cycle Research and Development (FCRD) Program within the Advanced Fuels Campaign (AFC).« less

Technology readiness levels for advanced nuclear fuels and materials development

DOE Office of Scientific and Technical Information (OSTI.GOV)

Carmack, W. J.; Braase, L. A.; Wigeland, R. A.

The Technology Readiness Level (TRL) process is used to quantitatively assess the maturity of a given technology. It was pioneered by the National Aeronautics and Space Administration (NASA) in the 1980s to develop and deploy new systems for space applications. The process was subsequently adopted by the Department of Defense (DoD) to develop and deploy new technology and systems for defense applications as well as the Department of Energy (DOE) to evaluate the maturity of new technologies in major construction projects. Advanced nuclear fuels and materials development is a critical technology needed for improving the performance and safety of currentmore » and advanced reactors, and ultimately closing the nuclear fuel cycle. Because deployment of new nuclear fuel forms requires a lengthy and expensive research, development, and demonstration program, applying the TRL concept to the advanced fuel development program is very useful as a management, communication and tracking tool. Furthermore, this article provides examples regarding the methods by which TRLs are currently used to assess the maturity of nuclear fuels and materials under development in the DOE Fuel Cycle Research and Development (FCRD) Program within the Advanced Fuels Campaign (AFC).« less

Material control and accountancy at EDF PWR plants; GCN: Gestion du Combustible Nucleaire

DOE Office of Scientific and Technical Information (OSTI.GOV)

de Cormis, F.

1991-01-01

The paper describes the comprehensive system which is developed and implemented at Electricite de France to provide a single reliable nuclear material control and accounting system for all nuclear plants. This software aims at several objectives among which are: the control and the accountancy of nuclear material at the plant, the optimization of the consistency of data by minimizing the possibility of transcription errors, the fulfillment of the statutory requirements by automatic transfer of reports to national and international safeguards authorities, the servicing of other EDF users of nuclear material data for technical or commercial purposes.

Rattling Nucleons: New Developments in Active Interrogation of Special Nuclear Material

DOE Office of Scientific and Technical Information (OSTI.GOV)

Robert C. Runkle; David L. Chichester; Scott J. Thompson

2012-01-01

Active interrogation is a vigorous area of research and development due to its promise of offering detection and characterization capabilities of special nuclear material in environments where passive detection fails. The primary value added by active methods is the capability to penetrate shielding - special nuclear material itself, incidental materials, or intentional shielding - and advocates hope that active interrogation will provide a solution to the problem of detecting shielded uranium, which is at present the greatest obstacle to interdiction efforts. The technique also provides a unique benefit for quantifying nuclear material in high background-radiation environments, an area important formore » nuclear material safeguards and material accountancy. Progress has been made in the field of active interrogation on several fronts, most notably in the arenas of source development, systems integration, and the integration and exploitation of multiple fission and non-fission signatures. But penetration of interrogating radiation often comes at a cost, not only in terms of finance and dose but also in terms of induced backgrounds, system complexity, and extended measurement times (including set up and acquisition). These costs make the calculus for deciding to implement active interrogation more subtle than may be apparent. The purpose of this review is thus to examine existing interrogation methods, compare and contrast their attributes and limitations, and identify missions where active interrogation may hold the most promise.« less

Rattling nucleons: New developments in active interrogation of special nuclear material

NASA Astrophysics Data System (ADS)

Runkle, Robert C.; Chichester, David L.; Thompson, Scott J.

2012-01-01

Active interrogation is a vigorous area of research and development due to its promise of offering detection and characterization capabilities of special nuclear material in environments where passive detection fails. The primary value added by active methods is the capability to penetrate shielding—special nuclear material itself, incidental materials, or intentional shielding—and advocates hope that active interrogation will provide a solution to the problem of detecting shielded uranium, which is at present the greatest obstacle to interdiction efforts. The technique also provides a unique benefit for quantifying nuclear material in high background-radiation environments, an area important for nuclear material safeguards and material accountancy. Progress has been made in the field of active interrogation on several fronts, most notably in the arenas of source development, systems integration, and the integration and exploitation of multiple fission and non-fission signatures. But penetration of interrogating radiation often comes at a cost, not only in terms of finance and dose but also in terms of induced backgrounds, system complexity, and extended measurement times (including set up and acquisition). These costs make the calculus for deciding to implement active interrogation more subtle than may be apparent. The purpose of this review is thus to examine existing interrogation methods, compare and contrast their attributes and limitations, and identify missions where active interrogation may hold the most promise.

Nuclear Forensic Science: Analysis of Nuclear Material Out of Regulatory Control

DOE PAGES

Kristo, Michael J.; Gaffney, Amy M.; Marks, Naomi; ...

2016-05-11

Nuclear forensic science seeks to identify the origin of nuclear materials found outside regulatory control. It is increasingly recognized as an integral part of a robust nuclear security program. Our review highlights areas of active, evolving research in nuclear forensics, with a focus on analytical techniques commonly employed in Earth and planetary sciences. Applications of nuclear forensics to uranium ore concentrates (UOCs) are discussed first. UOCs have become an attractive target for nuclear forensic researchers because of the richness in impurities compared to materials produced later in the fuel cycle. Furthermore, the development of chronometric methods for age dating nuclearmore » materials is then discussed, with an emphasis on improvements in accuracy that have been gained from measurements of multiple radioisotopic systems. Finally, papers that report on casework are reviewed, to provide a window into current scientific practice.« less

Proliferation risks from nuclear power infrastructure

NASA Astrophysics Data System (ADS)

Squassoni, Sharon

2017-11-01

Certain elements of nuclear energy infrastructure are inherently dual-use, which makes the promotion of nuclear energy fraught with uncertainty. Are current restraints on the materials, equipment, and technology that can be used either to produce fuel for nuclear electricity generation or material for nuclear explosive devices adequate? Technology controls, supply side restrictions, and fuel market assurances have been used to dissuade countries from developing sensitive technologies but the lack of legal restrictions is a continued barrier to permanent reduction of nuclear proliferation risks.

Anomaly detection applied to a materials control and accounting database

DOE Office of Scientific and Technical Information (OSTI.GOV)

Whiteson, R.; Spanks, L.; Yarbro, T.

An important component of the national mission of reducing the nuclear danger includes accurate recording of the processing and transportation of nuclear materials. Nuclear material storage facilities, nuclear chemical processing plants, and nuclear fuel fabrication facilities collect and store large amounts of data describing transactions that involve nuclear materials. To maintain confidence in the integrity of these data, it is essential to identify anomalies in the databases. Anomalous data could indicate error, theft, or diversion of material. Yet, because of the complex and diverse nature of the data, analysis and evaluation are extremely tedious. This paper describes the authors workmore » in the development of analysis tools to automate the anomaly detection process for the Material Accountability and Safeguards System (MASS) that tracks and records the activities associated with accountable quantities of nuclear material at Los Alamos National Laboratory. Using existing guidelines that describe valid transactions, the authors have created an expert system that identifies transactions that do not conform to the guidelines. Thus, this expert system can be used to focus the attention of the expert or inspector directly on significant phenomena.« less

Nuclear Resonance Fluorescence and Isotopic Mapping of Containers

NASA Astrophysics Data System (ADS)

Johnson, Micah S.; McNabb, Dennis P.

2009-03-01

National security programs have expressed interest in developing systems to isotopically map shipping containers, fuel assemblies, and waste barrels for various materials including special nuclear material (SNM). Current radiographic systems offer little more than an ambiguous density silhouette of a container's contents. In this paper we will present a system being developed at LLNL to isotopically map containers using the nuclear resonance fluorescence (NRF) method. Recent experimental measurements on NRF strengths in SNM are discussed.

Studies and research concerning BNFP: computerized nuclear materials control and accounting system development evaluation report, FY 1978

DOE Office of Scientific and Technical Information (OSTI.GOV)

Crawford, J M; Ehinger, M H; Joseph, C

1978-10-01

Development work on a computerized system for nuclear materials control and accounting in a nuclear fuel reprocessing plant is described and evaluated. Hardware and software were installed and tested to demonstrate key measurement, measurement control, and accounting requirements at accountability input/output points using natural uranium. The demonstration included a remote data acquisition system which interfaces process and special instrumentation to a cenral processing unit.

Assessment of Titanium Aluminide Alloys for High-Temperature Nuclear Structural Applications

NASA Astrophysics Data System (ADS)

Zhu, Hanliang; Wei, Tao; Carr, David; Harrison, Robert; Edwards, Lyndon; Hoffelner, Wolfgang; Seo, Dongyi; Maruyama, Kouichi

2012-12-01

Titanium aluminide (TiAl) alloys exhibit high specific strength, low density, good oxidation, corrosion, and creep resistance at elevated temperatures, making them good candidate materials for aerospace and automotive applications. TiAl alloys also show excellent radiation resistance and low neutron activation, and they can be developed to have various microstructures, allowing different combinations of properties for various extreme environments. Hence, TiAl alloys may be used in advanced nuclear systems as high-temperature structural materials. Moreover, TiAl alloys are good materials to be used for fundamental studies on microstructural effects on irradiation behavior of advanced nuclear structural materials. This article reviews the microstructure, creep, radiation, and oxidation properties of TiAl alloys in comparison with other nuclear structural materials to assess the potential of TiAl alloys as candidate structural materials for future nuclear applications.

41 CFR 109-1.100-51 - Definitions and acronyms.

Code of Federal Regulations, 2011 CFR

2011-01-01

... nuclear-related material, equipment, and related technology as described in the International Atomic..., material, or technology as described in the Nuclear Suppliers Group Trigger List and Dual-Use List, or equipment, material or technology used in the research, design, development, testing, or production of...

41 CFR 109-1.100-51 - Definitions and acronyms.

Code of Federal Regulations, 2010 CFR

2010-07-01

... nuclear-related material, equipment, and related technology as described in the International Atomic..., material, or technology as described in the Nuclear Suppliers Group Trigger List and Dual-Use List, or equipment, material or technology used in the research, design, development, testing, or production of...

41 CFR 109-1.100-51 - Definitions and acronyms.

Code of Federal Regulations, 2014 CFR

2014-01-01

... nuclear-related material, equipment, and related technology as described in the International Atomic..., material, or technology as described in the Nuclear Suppliers Group Trigger List and Dual-Use List, or equipment, material or technology used in the research, design, development, testing, or production of...

Detection of Shielded Nuclear Material in a Cargo Container

DOE Office of Scientific and Technical Information (OSTI.GOV)

J. L. Jones; D. R. Norman; K. J. Haskell

The Idaho National Laboratory, along with Los Alamos National Laboratory and the Idaho State University’s Idaho Accelerator Center, are developing electron accelerator-based, photonuclear inspection technologies for the detection of shielded nuclear material within air-, rail-, and especially, maritime-cargo transportation containers. This paper describes a developing prototypical cargo container inspection system utilizing the Pulsed Photonuclear Assessment (PPA) technology, incorporates interchangeable, well-defined, contraband shielding structures (i.e., "calibration" pallets) providing realistic detection data for induced radiation signatures from smuggled nuclear material, and provides various shielded nuclear material detection results. Using a 4.8-kg quantity of depleted uranium, neutron and gamma-ray detection responses are presentedmore » for well-defined shielded and unshielded configurations evaluated in a selected cargo container inspection configuration. © 2001 Elsevier Science. All rights reserved« less

Advanced Ceramics for Use as Fuel Element Materials in Nuclear Thermal Propulsion Systems

NASA Technical Reports Server (NTRS)

Valentine, Peter G.; Allen, Lee R.; Shapiro, Alan P.

2012-01-01

With the recent start (October 2011) of the joint National Aeronautics and Space Administration (NASA) and Department of Energy (DOE) Advanced Exploration Systems (AES) Nuclear Cryogenic Propulsion Stage (NCPS) Program, there is renewed interest in developing advanced ceramics for use as fuel element materials in nuclear thermal propulsion (NTP) systems. Three classes of fuel element materials are being considered under the NCPS Program: (a) graphite composites - consisting of coated graphite elements containing uranium carbide (or mixed carbide), (b) cermets (ceramic/metallic composites) - consisting of refractory metal elements containing uranium oxide, and (c) advanced carbides consisting of ceramic elements fabricated from uranium carbide and one or more refractory metal carbides [1]. The current development effort aims to advance the technology originally developed and demonstrated under Project Rover (1955-1973) for the NERVA (Nuclear Engine for Rocket Vehicle Application) [2].

The State-of-the-Art of Materials Technology Used for Fossil and Nuclear Power Plants in China

NASA Astrophysics Data System (ADS)

Weng, Yuqing

Combined with the development of energy in China during the past 30 years, this paper clarified that high steam parameters ultra-supercritical (USC) coal-fired power plants and 1000MW nuclear power plants are the most important method to optimize energy structure and achieve national goals of energy saving and CO2 emission in China. Additionally, requirement of materials technology in high steam parameters USC coal-fired power plants and 1000MW nuclear power plants, current research and major development of relevant materials technology in China were briefly described in this paper.

Complete Report on the Development of Welding Parameters for Irradiated Materials

DOE Office of Scientific and Technical Information (OSTI.GOV)

Frederick, Greg; Sutton, Benjamin J.; Tatman, Jonathan K.

The advanced welding facility at the Radiochemical Engineering Development Center of Oak Ridge National Laboratory, which was conceived to enable research and development of weld repair techniques for nuclear power plant life extension, is now operational. The development of the facility and its advanced welding capabilities, along with the model materials for initial welding trials, were funded jointly by the U.S. Department of Energy, Office of Nuclear Energy, Light Water Reactor Sustainability Program, the Electric Power Research Institute, Long Term Operations Program and the Welding and Repair Technology Center, with additional support from Oak Ridge National Laboratory. Welding of irradiatedmore » materials was initiated on November 17, 2017, which marked a significant step in the development of the facility and the beginning of extensive welding research and development campaigns on irradiated materials that will eventually produce validated techniques and guidelines for weld repair activities carried out to extend the operational lifetimes of nuclear power plants beyond 60 years. This report summarizes the final steps that were required to complete weld process development, initial irradiated materials welding activities, near-term plans for irradiated materials welding, and plans for post-weld analyses that will be carried out to assess the ability of the advanced welding processes to make repairs on irradiated materials.« less

After Action Report - Kazakhstan NSDD July 2015

DOE Office of Scientific and Technical Information (OSTI.GOV)

Fox, Caterina; Eppich, Gary; Kips, Ruth

On Monday 20 July, Caterina Fox, Ruth Kips and Kim Knight were invited to participate in Kazakhstan's nuclear material inventory management working group meeting coordinated by Alexander Vasilliev as nuclear forensics subject matter experts. The meeting included participants from Kazakhstan's nuclear regulatory agency (CAESC, the Committee on Atomic and Energetic Supervision and Control) and 3 institutes 1. Institute of Nuclear Physics, INP (Almaty), 2. National Nuclear Center, NNC (Kurchatov), and 3. Ulba Metallurgical Plant, UMP (Oskemen). CAESC requested attendance of an MC&A expert, an IT Specialist, and a Physical Security Specialist from each site. The general meeting concerned considerations formore » creating unified or compatible systems for nuclear material inventory management. NSDD representatives provided an overview of nuclear forensics and presented considerations for developments of inventory management that might be synergistic with future consideration of development of a National Nuclear Forensics Library to support nuclear forensics investigations.« less

Nuclear Weapons, Nuclear War and the Health Professions: Curriculum Development in Medical Schools.

ERIC Educational Resources Information Center

Cassell, Christine K.; McCally, Michael

1984-01-01

Describes the design and development of a 10-week course entitled Medical Consequences of Nuclear War, offered to medical and nursing students at the Oregon Health Sciences University. Other curriculum models and teaching materials are also discussed. (SK)

MHSS: a material handling system simulator

DOE Office of Scientific and Technical Information (OSTI.GOV)

Pomernacki, L.; Hollstien, R.B.

1976-04-07

A Material Handling System Simulator (MHSS) program is described that provides specialized functional blocks for modeling and simulation of nuclear material handling systems. Models of nuclear fuel fabrication plants may be built using functional blocks that simulate material receiving, storage, transport, inventory, processing, and shipping operations as well as the control and reporting tasks of operators or on-line computers. Blocks are also provided that allow the user to observe and gather statistical information on the dynamic behavior of simulated plants over single or replicated runs. Although it is currently being developed for the nuclear materials handling application, MHSS can bemore » adapted to other industries in which material accountability is important. In this paper, emphasis is on the simulation methodology of the MHSS program with application to the nuclear material safeguards problem. (auth)« less

The state of nuclear forensics

NASA Astrophysics Data System (ADS)

Kristo, Michael J.; Tumey, Scott J.

2013-01-01

Nuclear terrorism has been identified as one of the most serious security threats facing the world today. Many countries, including the United States, have incorporated nuclear forensic analysis as a component of their strategy to prevent nuclear terrorism. Nuclear forensics involves the laboratory analysis of seized illicit nuclear materials or debris from a nuclear detonation to identify the origins of the material or weapon. Over the years, a number of forensic signatures have been developed to improve the confidence with which forensic analysts can draw conclusions. These signatures are validated and new signatures are discovered through research and development programs and in round-robin exercises among nuclear forensic laboratories. The recent Nuclear Smuggling International Technical Working Group Third Round Robin Exercise and an on-going program focused on attribution of uranium ore concentrate provide prime examples of the current state of nuclear forensics. These case studies will be examined and the opportunities for accelerator mass spectrometry to play a role in nuclear forensics will be discussed.

Developing Ultra-small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hosemann, Peter; Kaoumi, Djamel

Nuclear materials are an essential aspect of nuclear engineering. While great effort is spent on designing more advanced reactors or enhancing a reactor’s safety, materials have been the bottleneck of most new developments. The designs of new reactor concepts are driven by neutronic and thermodynamic aspects, leading to unusual coolants (liquid metal, liquid salt, gases), higher temperatures, and higher radiation doses than conventional light water reactors have. However, any (nuclear) engineering design must consider the materials used in the anticipated application in order to ever be realized. Designs which may look easy, simple and efficient considering thermodynamics or neutronic aspectsmore » can show their true difficulty in the materials area, which then prevents them from being deployed. In turn, the materials available are influencing the neutronic and thermodynamic designs and therefore must be considered from the beginning, requiring close collaborations between different aspects of nuclear engineering. If a particular design requires new materials, the licensing of the reactor must be considered, but licensing can be a costly and time consuming process that results in long lead times to realize true materials innovation.« less

Status of the prototype Pulsed Photonuclear Assessment (PPA) inspection system

NASA Astrophysics Data System (ADS)

Jones, James L.; Blackburn, Brandon W.; Norman, Daren R.; Watson, Scott M.; Haskell, Kevin J.; Johnson, James T.; Hunt, Alan W.; Harmon, Frank; Moss, Calvin

2007-08-01

The Idaho National Laboratory, in collaboration with Idaho State University's Idaho Accelerator Center and the Los Alamos National Laboratory, continues to develop the Pulsed Photonuclear Assessment (PPA) technique for shielded nuclear material detection in large volume configurations, such as cargo containers. In recent years, the Department of Homeland Security has supported the development of a prototype PPA cargo inspection system. This PPA system integrates novel neutron and gamma-ray detectors for nuclear material detection along with a complementary and unique gray scale, density mapping component for significant shield material detection. This paper will present the developmental status of the prototype system, its detection performance using several INL Calibration Pallets, and planned enhancements to further increase its nuclear material detection capability.

NUCLEAR REACTOR FUEL-BREEDER FUEL ELEMENT

DOEpatents

Currier, E.L. Jr.; Nicklas, J.H.

1962-08-14

A fuel-breeder fuel element was developed for a nuclear reactor wherein discrete particles of fissionable material are dispersed in a matrix of fertile breeder material. The fuel element combines the advantages of a dispersion type and a breeder-type. (AEC)

Savannah River Site nuclear materials management plan FY 2017-2031

DOE Office of Scientific and Technical Information (OSTI.GOV)

Magoulas, V.

The purpose of the Nuclear Materials Management Plan (herein referred to as “this Plan”) is to integrate and document the activities required to disposition the legacy and/or surplus Enriched Uranium (EU) and Plutonium (Pu) and other nuclear materials already stored or anticipated to be received by facilities at the Department of Energy (DOE) Savannah River Site (SRS) as well as the activities to support the DOE Tritium mission. It establishes a planning basis for EU and Pu processing operations in Environmental Management Operations (EMO) facilities through the end of their program missions and for the tritium through the National Nuclearmore » Security Administration (NNSA) Defense Programs (DP) facilities. Its development is a joint effort among the Department of Energy - Savannah River (DOE-SR), DOE – Environmental Management (EM), NNSA Office of Material Management and Minimization (M3), NNSA Savannah River Field Office (SRFO), and the Management and Operations (M&O) contractor, Savannah River Nuclear Solutions, LLC (SRNS). Life-cycle program planning for Nuclear Materials Stabilization and Disposition and the Tritium Enterprise may use this Plan as a basis for the development of the nuclear materials disposition scope and schedule. This Plan assumes full funding to accomplish the required project and operations activities. It is recognized that some aspects of this Plan are pre decisional with regard to National Environmental Policy Act (NEPA); in such cases new NEPA actions will be required.« less

Solid-State Nuclear Power

NASA Technical Reports Server (NTRS)

George, Jeffrey A.

2012-01-01

A strategy for "Solid-State" Nuclear Power is proposed to guide development of technologies and systems into the second 50 years of nuclear spaceflight. The strategy emphasizes a simple and highly integrated system architecture with few moving parts or fluid loops; the leverage of modern advances in materials, manufacturing, semiconductors, microelectromechanical and nanotechnology devices; and the targeted advancement of high temperature nuclear fuels, materials and static power conversion to enable high performance from simple system topologies.

Nuclear Forensics at Los Alamos National Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kinman, William Scott; Steiner, Robert Ernest; Lamont, Stephen Philip

Nuclear forensics assists in responding to any event where nuclear material is found outside of regulatory control; a response plan is presented and a nuclear forensics program is undergoing further development so that smugglers are sufficiently deterred.

Nuclear Terrorism - Dimensions, Options, and Perspectives in Moldova

NASA Astrophysics Data System (ADS)

Vaseashta, Ashok; Susmann, P.; Braman, Eric W.; Enaki, Nicolae A.

Securing nuclear materials, controlling contraband and preventing proliferation is an international priority to resolve using technology, diplomacy, strategic alliances, and if necessary, targeted military exercises. Nuclear security consists of complementary programs involving international legal and regulatory structure, intelligence and law enforcement agencies, border and customs forces, point and stand-off radiation detectors, personal protection equipment, preparedness for emergency and disaster, and consequence management teams. The strategic goal of UNSCR 1540 and the GICNT is to prevent nuclear materials from finding their way into the hands of our adversaries. This multi-jurisdictional and multi-agency effort demands tremendous coordination, technology assessment, policy development and guidance from several sectors. The overall goal envisions creating a secured environment that controls and protects nuclear materials while maintaining the free flow of commerce and individual liberty on international basis. Integral to such efforts are technologies to sense/detect nuclear material, provide advance information of nuclear smuggling routes, and other advanced means to control nuclear contraband and prevent proliferation. We provide an overview of GICNT and several initiatives supporting such efforts. An overview is provided of technological advances in support of point and stand-off detection and receiving advance information of nuclear material movement from perspectives of the Republic of Moldova.

Multi-Detector Analysis System for Spent Nuclear Fuel Characterization

DOE Office of Scientific and Technical Information (OSTI.GOV)

Reber, Edward Lawrence; Aryaeinejad, Rahmat; Cole, Jerald Donald

1999-09-01

The Spent Nuclear Fuel (SNF) Non-Destructive Analysis (NDA) program at INEEL is developing a system to characterize SNF for fissile mass, radiation source term, and fissile isotopic content. The system is based on the integration of the Fission Assay Tomography System (FATS) and the Gamma-Neutron Analysis Technique (GNAT) developed under programs supported by the DOE Office of Non-proliferation and National Security. Both FATS and GNAT were developed as separate systems to provide information on the location of special nuclear material in weapons configuration (FATS role), and to measure isotopic ratios of fissile material to determine if the material was frommore » a weapon (GNAT role). FATS is capable of not only determining the presence and location of fissile material but also the quantity of fissile material present to within 50%. GNAT determines the ratios of the fissile and fissionable material by coincidence methods that allow the two prompt (immediately) produced fission fragments to be identified. Therefore, from the combination of FATS and GNAT, MDAS is able to measure the fissile material, radiation source term, and fissile isotopics content.« less

Evaluating Nonproliferation Bona Fides

DOE Office of Scientific and Technical Information (OSTI.GOV)

Seward, Amy M.; Mathews, Caroline E.; Kessler, Carol E.

2008-07-14

Anticipated growth of global nuclear energy in a difficult international security environment heightens concerns that states could decide to exploit their civilian nuclear fuel cycles as a means of acquiring nuclear weapons. Such concerns partly reflect a fundamental tension in the Treaty on the Non-Proliferation of Nuclear Weapons (NPT). On the one hand, Articles II and III of the NPT clearly prohibit each non-nuclear-weapon state party from acquiring nuclear weapons. On the other hand, Article IV of the NPT confers the “inalienable right” of Parties to the treaty to “develop research, production and use of nuclear energy for peaceful purposes…,”more » and directs all Parties to “facilitate… the fullest possible exchange of equipment, materials and scientific and technological information for the peaceful uses of nuclear energy…,” and “cooperate in contributing…to the further development of the applications of nuclear energy for peaceful purposes….” This juxtaposition raises the possibility that a state could exercise its Article IV right to develop a civilian nuclear fuels cycle and then use the equipment, materials and technology to acquire nuclear weapons in violation of its Article II and III obligations.« less

Editorial

DOE PAGES

Whittle, K. R.; Edmondson, P. D.

2015-07-01

The development of nuclear materials for the next generation of reactor technology, e.g. GenIV and fusion, is at a critical juncture, with an increasing body of research into the long-term effects of radiation damage on materials being examined. As it is hopefully evident from the papers in this journal issue, there are many pertinent and challenging topics for research in this exciting and challenging area of research, driving forward the development of new materials and the next generation of nuclear reactor technologies.

U.S. and Russian Collaboration in the Area of Nuclear Forensics

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kristo, M J

2007-10-22

Nuclear forensics has become increasingly important in the fight against illicit trafficking in nuclear and other radioactive materials. The illicit trafficking of nuclear materials is, of course, an international problem; nuclear materials may be mined and milled in one country, manufactured in a second country, diverted at a third location, and detected at a fourth. There have been a number of articles in public policy journals in the past year that call for greater interaction between the U. S. and the rest of the world on the topic of nuclear forensics. Some believe that such international cooperation would help providemore » a more certain capability to identify the source of the nuclear material used in a terrorist event. An improved international nuclear forensics capability would also be important as part of the IAEA verification toolkit, particularly linked to increased access provided by the additional protocol. A recent study has found that, although international progress has been made in securing weapons-usable HEU and Pu, the effort is still insufficient. They found that nuclear material, located in 40 countries, could be obtained by terrorists and criminals and used for a crude nuclear weapon. Through 2006, the IAEA Illicit Trafficking Database had recorded a total of 607 confirmed events involving illegal possession, theft, or loss of nuclear and other radioactive materials. Although it is difficult to predict the future course of such illicit trafficking, increasingly such activities are viewed as significant threats that merit the development of special capabilities. As early as April, 1996, nuclear forensics was recognized at the G-8 Summit in Moscow as an important element of an illicit nuclear trafficking program. Given international events over the past several years, the value and need for nuclear forensics seems greater than ever. Determining how and where legitimate control of nuclear material was lost and tracing the route of the material from diversion through interdiction are important goals for nuclear forensics and attribution. It is equally important to determine whether additional devices or materials that pose a threat to public safety are also available. Finding the answer to these questions depends on determining the source of the material and its method of production. Nuclear forensics analysis and interpretation provide essential insights into methods of production and sources of illicit radioactive materials. However, they are most powerful when combined with other sources of information, including intelligence and traditional detective work. The certainty of detection and punishment for those who remove nuclear materials from legitimate control provides the ultimate deterrent for such diversion and, ultimately, for the intended goal of such diversion, including nuclear terrorism or proliferation. Consequently, nuclear forensics is an integral part of 'nuclear deterrence' in the 21st century. Nuclear forensics will always be limited by the diagnostic information inherent in the interdicted material. Important markers for traditional forensics (fingerprints, stray material, etc.) can be eliminated or obscured, but many nuclear materials have inherent isotopic or chemical characteristics that serve as unequivocal markers of specific sources, production processes, or transit routes. The information needed for nuclear forensics goes beyond that collected for most commercial and international verification activities. Fortunately, the international nuclear engineering enterprise has a restricted number of conspicuous process steps that makes the interpretation process easier. Ultimately, though, it will always be difficult to distinguish between materials that reflect similar source or production histories, but are derived from disparate sites. Due to the significant capital costs of the equipment and the specialized expertise of the personnel, work in the field of nuclear forensics has been restricted so far to a handful of national and international laboratories. There are a limited number of specialists who have experience working with interdicted nuclear materials and affiliated evidence. Therefore, a knowledge management system that utilizes information resources relevant to nuclear forensic and attribution signatures, processes, origins, and pathways, allowing subject matter experts to access the right information in order to interpret forensics data and draw appropriate conclusions, is essential. In order to determine the origin, point of diversion of the nuclear material, and those responsible for the unauthorized transfer, close relationships are required between governments who maintain inventories and data of fissile or other radioactive materials. Numerous databases exist in many countries and organizations that could be valuable for the future development and application of nuclear forensics.« less

Technical Readiness and Gaps Analysis of Commercial Optical Materials and Measurement Systems for Advanced Small Modular Reactors

DOE Office of Scientific and Technical Information (OSTI.GOV)

Anheier, Norman C.; Suter, Jonathan D.; Qiao, Hong

2013-08-06

This report intends to support Department of Energy’s Office of Nuclear Energy (DOE-NE) Nuclear Energy Research and Development Roadmap and industry stakeholders by evaluating optical-based instrumentation and control (I&C) concepts for advanced small modular reactor (AdvSMR) applications. These advanced designs will require innovative thinking in terms of engineering approaches, materials integration, and I&C concepts to realize their eventual viability and deployability. The primary goals of this report include: 1. Establish preliminary I&C needs, performance requirements, and possible gaps for AdvSMR designs based on best available published design data. 2. Document commercial off-the-shelf (COTS) optical sensors, components, and materials in termsmore » of their technical readiness to support essential AdvSMR in-vessel I&C systems. 3. Identify technology gaps by comparing the in-vessel monitoring requirements and environmental constraints to COTS optical sensor and materials performance specifications. 4. Outline a future research, development, and demonstration (RD&D) program plan that addresses these gaps and develops optical-based I&C systems that enhance the viability of future AdvSMR designs. The development of clean, affordable, safe, and proliferation-resistant nuclear power is a key goal that is documented in the Nuclear Energy Research and Development Roadmap. This roadmap outlines RD&D activities intended to overcome technical, economic, and other barriers, which currently limit advances in nuclear energy. These activities will ensure that nuclear energy remains a viable component to this nation’s energy security.« less

Nuclear Forensics Applications of Principal Component Analysis on Micro X-ray Fluorescence Images

DTIC Science & Technology

analysis on quantified micro x-ray fluorescence intensity values. This method is then applied to address goals of nuclear forensics . Thefirst...researchers in the development and validation of nuclear forensics methods. A method for determining material homogeneity is developed and demonstrated

A New Program to Teach Nuclear and Radiochemistry to Undergraduates.

ERIC Educational Resources Information Center

Catchen, Gary L.; Canelos, James

1988-01-01

Follows the development of a course in nuclear and radiochemistry at Penn State. Lists specific nuclear science topics covered in the undergraduate level course. Describes audio-visual materials that have been developed for the course and includes a survey of students taking the course. (ML)

Nuclear quadrupole resonance detection of explosives: an overview

NASA Astrophysics Data System (ADS)

Miller, Joel B.

2011-06-01

Nuclear Quadrupole Resonance (NQR) is a spectroscopic technique closely related to Nuclear Magnetic Resonance (NMR) and Magnetic Resonance Imaging (MRI). These techniques, and NQR in particular, induce signals from the material being interrogated that are very specific to the chemical and physical structure of the material, but are relatively insensitive to the physical form of the material. NQR explosives detection exploits this specificity to detect explosive materials, in contrast to other well known techniques that are designed to detect explosive devices. The past two decades have seen a large research and development effort in NQR explosives detection in the United States aimed at transportation security and military applications. Here, I will briefly describe the physical basis for NQR before discussing NQR developments over the past decade, with particular emphasis on landmine detection and the use of NQR in combating IED's. Potential future directions for NQR research and development are discussed.

Methodology for characterizing potential adversaries of Nuclear Material Safeguards Systems

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kirkwood, C.W.; Pollock, S.M.

1978-11-01

The results are described of a study by Woodward--Clyde Consultants to assist the University of California Lawrence Livermore Laboratory in the development of methods to analyze and evaluate Nuclear Material Safeguards (NMS) Systems. The study concentrated on developing a methodology to assist experts in describing, in quantitative form, their judgments about the characteristics of potential adversaries of NMS Systems.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kristo, Michael J.; Gaffney, Amy M.; Marks, Naomi

Nuclear forensic science seeks to identify the origin of nuclear materials found outside regulatory control. It is increasingly recognized as an integral part of a robust nuclear security program. Our review highlights areas of active, evolving research in nuclear forensics, with a focus on analytical techniques commonly employed in Earth and planetary sciences. Applications of nuclear forensics to uranium ore concentrates (UOCs) are discussed first. UOCs have become an attractive target for nuclear forensic researchers because of the richness in impurities compared to materials produced later in the fuel cycle. Furthermore, the development of chronometric methods for age dating nuclearmore » materials is then discussed, with an emphasis on improvements in accuracy that have been gained from measurements of multiple radioisotopic systems. Finally, papers that report on casework are reviewed, to provide a window into current scientific practice.« less

Safeguards in Pyroprocessing: an Integrated Model Development and Measurement Data Analysis

DOE Office of Scientific and Technical Information (OSTI.GOV)

Zhang, Jinsuo

Pyroprocessing is an electrochemical method based on the molten salt electrolyte, mainly the LiCl-KCl eutectic molten salt, to recycle the used nuclear fuel. For a conceptual design of commercial pyroprocessing facility, tons of special nuclear materials, namely U and Pu, may be involved, which could be used for non-peaceful purposes if they are diverted. Effective safeguards approaches have to be developed prior to the development and construction of a pyroprocessing facility. Present research focused on two main objectives, namely calculating the properties of nuclear species in LiCl-KCl molten salt and developing integrated model to safeguard a pyroprocessing facility. Understanding themore » characteristics of special nuclear materials in LiCl-KCl eutectic salt is extremely important to understand their behaviors in an electrorefiner. The model development for the separation processes in the pyroprocessing, including electrorefining, actinide drawdown, and rare earth drawdown benefits the understanding of material transport and separation performance of these processes under various conditions. The output signals, such as potential, current, and species concentration contribute to the material balance closure and provide safeguards signatures to detect the scenarios of diversion. U and Pu are the two main elements concerned in this study due to our interest in safeguards.« less

Keeping the Momentum and Nuclear Forensics at Los Alamos National Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

Steiner, Robert Ernest; Dion, Heather M.; Dry, Donald E.

LANL has 70 years of experience in nuclear forensics and supports the community through a wide variety of efforts and leveraged capabilities: Expanding the understanding of nuclear forensics, providing training on nuclear forensics methods, and developing bilateral relationships to expand our understanding of nuclear forensic science. LANL remains highly supportive of several key organizations tasked with carrying forth the Nuclear Security Summit messages: IAEA, GICNT, and INTERPOL. Analytical chemistry measurements on plutonium and uranium matrices are critical to numerous programs including safeguards accountancy verification measurements. Los Alamos National Laboratory operates capable actinide analytical chemistry and material science laboratories suitable formore » nuclear material and environmental forensic characterization. Los Alamos National Laboratory uses numerous means to validate and independently verify that measurement data quality objectives are met. Numerous LANL nuclear facilities support the nuclear material handling, preparation, and analysis capabilities necessary to evaluate samples containing nearly any mass of an actinide (attogram to kilogram levels).« less

Don't Mess with the NEST

NASA Astrophysics Data System (ADS)

Larson, Michael

2012-03-01

This presentation will describe the history of the Nuclear Emergency Support Team (NEST) and its evolution over the years. NEST was formed due to a number of nuclear extortion threats received in the early 1970s. From the beginning NEST developed an extensive exercise program to test and expand capabilities. The Nuclear Assessment Program (NAP) was developed, in part, to determine if NEST deployments were required. A major revamp of the NEST program occurred in 1994. Many other organizations work in conjunction with NEST in particular the FBI and DOD. Considerable research and development has been performed in the areas of Access, Search, Diagnostics, Device Assessment, and Disablement. Extensive searches of material appearing in the unclassified literature have been and are being performed to see what is being said about nuclear materials and devices. A comprehensive study of Improvised Nuclear Devices (IND) is ongoing to determine what a terrorist can and cannot do. NEST now consists of four phases with the latest additions of Phase III, Disposition and Phase IV, Nuclear Forensics. LLNL-ABS-521775

Radiation chemistry for modern nuclear energy development

NASA Astrophysics Data System (ADS)

Chmielewski, Andrzej G.; Szołucha, Monika M.

2016-07-01

Radiation chemistry plays a significant role in modern nuclear energy development. Pioneering research in nuclear science, for example the development of generation IV nuclear reactors, cannot be pursued without chemical solutions. Present issues related to light water reactors concern radiolysis of water in the primary circuit; long-term storage of spent nuclear fuel; radiation effects on cables and wire insulation, and on ion exchangers used for water purification; as well as the procedures of radioactive waste reprocessing and storage. Radiation effects on materials and enhanced corrosion are crucial in current (II/III/III+) and future (IV) generation reactors, and in waste management, deep geological disposal and spent fuel reprocessing. The new generation of reactors (III+ and IV) impose new challenges for radiation chemists due to their new conditions of operation and the usage of new types of coolant. In the case of the supercritical water-cooled reactor (SCWR), water chemistry control may be the key factor in preventing corrosion of reactor structural materials. This paper mainly focuses on radiation effects on long-term performance and safety in the development of nuclear power plants.

Nuclear energy and security

DOE Office of Scientific and Technical Information (OSTI.GOV)

BLEJWAS,THOMAS E.; SANDERS,THOMAS L.; EAGAN,ROBERT J.

2000-01-01

Nuclear power is an important and, the authors believe, essential component of a secure nuclear future. Although nuclear fuel cycles create materials that have some potential for use in nuclear weapons, with appropriate fuel cycles, nuclear power could reduce rather than increase real proliferation risk worldwide. Future fuel cycles could be designed to avoid plutonium production, generate minimal amounts of plutonium in proliferation-resistant amounts or configurations, and/or transparently and efficiently consume plutonium already created. Furthermore, a strong and viable US nuclear infrastructure, of which nuclear power is a large element, is essential if the US is to maintain a leadershipmore » or even participatory role in defining the global nuclear infrastructure and controlling the proliferation of nuclear weapons. By focusing on new fuel cycles and new reactor technologies, it is possible to advantageously burn and reduce nuclear materials that could be used for nuclear weapons rather than increase and/or dispose of these materials. Thus, the authors suggest that planners for a secure nuclear future use technology to design an ideal future. In this future, nuclear power creates large amounts of virtually atmospherically clean energy while significantly lowering the threat of proliferation through the thoughtful use, physical security, and agreed-upon transparency of nuclear materials. The authors must develop options for policy makers that bring them as close as practical to this ideal. Just as Atoms for Peace became the ideal for the first nuclear century, they see a potential nuclear future that contributes significantly to power for peace and prosperity.« less

To discuss illicit nuclear trafficking

DOE Office of Scientific and Technical Information (OSTI.GOV)

Balatsky, Galya I; Severe, William R; Wallace, Richard K

2010-01-01

The Illicit nuclear trafficking panel was conducted at the 4th Annual INMM workshop on Reducing the Risk from Radioactive and Nuclear Materials on February 2-3, 2010 in Washington DC. While the workshop occurred prior to the Nuclear Security Summit, April 12-13 2010 in Washington DC, some of the summit issues were raised during the workshop. The Communique of the Washington Nuclear Security Summit stated that 'Nuclear terrorism is one of the most challenging threats to international security, and strong nuclear security measures are the most effective means to prevent terrorists, criminals, or other unauthorized actors from acquiring nuclear materials.' Themore » Illicit Trafficking panel is one means to strengthen nuclear security and cooperation at bilateral, regional and multilateral levels. Such a panel promotes nuclear security culture through technology development, human resources development, education and training. It is a tool which stresses the importance of international cooperation and coordination of assistance to improve efforts to prevent and respond to incidents of illicit nuclear trafficking. Illicit trafficking panel included representatives from US government, an international organization (IAEA), private industry and a non-governmental organization to discuss illicit nuclear trafficking issues. The focus of discussions was on best practices and challenges for addressing illicit nuclear trafficking. Terrorism connection. Workshop discussions pointed out the identification of terrorist connections with several trafficking incidents. Several trafficking cases involved real buyers (as opposed to undercover law enforcement agents) and there have been reports identifying individuals associated with terrorist organizations as prospective plutonium buyers. Some specific groups have been identified that consistently search for materials to buy on the black market, but no criminal groups were identified that specialize in nuclear materials or isotope smuggling. In most cases, sellers do not find legitimate buyers; however, there have been specific cases where sellers did find actual terrorist group representatives. There appears to be a connection between terrorist groups engaged in trafficking conventional arms and explosives components that are also looking for both nuclear materials and radioisotopes. Sale opportunities may create additional demand for such materials. As we can observe from Figure 1, many cases in the mid-90s involved kilogram quantities of material. There were smaller amounts of material moved in 2001, 2003 and 2006. While we have seen less trafficking cases involving PujHEU in recent years, the fact that it continues at all is troubling. The trafficking cases can be presented through their life cycle: Diversion of materials leads to Trafficker and then to Terrorist/Proliferator. Most of the information we have in trafficking cases is on the Trafficker. In 16 cases reported by the IAEA, there are 10 prosecutions of the involved trafficker. However, there are no confirmed diversions of material recorded in any of the 18 seizures. Most seizures were sting operations performed by law enforcement or security agents with no actual illicit end-user involved.« less

The Importance of International Technical Nuclear Forensics to Deter Illicit Trafficking

DOE Office of Scientific and Technical Information (OSTI.GOV)

Smith, D K

2007-01-30

Illicit trafficking of nuclear materials is a transboundary problem that requires a cooperative approach involving international nuclear forensics to ensure all states understand the threat posed by nuclear smuggling as well as a means to best deter the movement of nuclear contraband. To achieve the objectives, all cases involving illicit trafficking of nuclear and radiological materials must be vigorously pursued and prosecuted when appropriate. The importance of outreach and formal government-to-government relationships with partner nations affected by nuclear trafficking cannot be under-estimated. States that are situated on smuggling routes may be well motivated to counter nuclear crimes to bolster theirmore » own border and transportation security as well as strengthen their economic and political viability. National law enforcement and atomic energy agencies in these states are aggressively pursuing a comprehensive strategy to counter nuclear smuggling through increasing reliance on technical nuclear forensics. As part of these activities, it is essential that these organizations be given adequate orientation to the best practices in this emerging discipline including the categorization of interdicted nuclear material, collection of traditional and nuclear forensic evidence, data analysis using optimized analytical protocols, and how to best fuse forensics information with reliable case input to best develop a law enforcement or national security response. The purpose of formalized USG relationship is to establish an institutional framework for collaboration in international forensics, improve standards of forensics practice, conduct joint exercises, and pursue case-work that benefits international security objectives. Just as outreach and formalized relationships are important to cultivate international nuclear forensics, linking nuclear forensics to ongoing national assistance in border and transpiration security, including port of entry of entry monitoring, nuclear safeguards, and emerging civilian nuclear power initiatives including the Global Nuclear Energy Partnership are crucial components of a successful nuclear detection and security architecture. Once illicit shipments of nuclear material are discovered at a border, the immediate next question will be the nature and the source of the material, as well as the identity of the individual(s) involved in the transfer as well as their motivations. The Nuclear Smuggling International Technical Working Group (ITWG) is a forum for the first responder, law enforcement, policy, and diplomatic community to partner with nuclear forensics experts worldwide to identify requirements and develop technical solutions in common. The ITWG was charted in 1996 and since that time approximately 30 member states and organizations have participated in 11 annual international meetings. The ITWG also works closely with the IAEA to provide countries with support for forensic analyses. Priorities include the development of common protocols for the collection of nuclear forensic evidence and laboratory investigations, organization of forensic round-robin analytical exercises and technical forensic assistance to requesting nations. To promote the science of nuclear forensics within the ITWG the Nuclear Forensics Laboratory Group was organized in 2004. A Model Action Plan for nuclear forensics was developed by the ITWG and published as an IAEA Nuclear security Series document to guide member states in their own forensics investigations. Through outreach, formalized partnerships, common approaches and security architectures, and international working groups, nuclear forensics provides an important contribution to promoting nuclear security and accountability.« less

The myth of the ``proliferation-resistant'' closed nuclear fuel cycle

NASA Astrophysics Data System (ADS)

Lyman, Edwin S.

2000-07-01

National nuclear energy programs that engage in reprocessing of spent nuclear fuel (SNF) and the development of "closed" nuclear fuel cycles based on the utilization of plutonium process and store large quantities of weapons-usable nuclear materials in forms vulnerable to diversion or theft by national or subnational groups. Proliferation resistance, an idea dating back at least as far as the International Fuel Cycle Evaluation (INFCE) of the late 1970s, is a loosely defined term referring to processes for chemical separation of SNF that do not extract weapons-usable materials in a purified form.

MSTD 2007 Publications and Patents

DOE Office of Scientific and Technical Information (OSTI.GOV)

King, W E

2008-04-01

The Materials Science and Technology Division (MSTD) supports the central scientific and technological missions of the Laboratory, and at the same time, executes world-class, fundamental research and novel technological development over a wide range of disciplines. Our organization is driven by the institutional needs in nuclear weapons stockpile science, high-energy-density science, nuclear reactor science, and energy and environment science and technology. We maintain expertise and capabilities in many diverse areas, including actinide science, electron microscopy, laser-materials interactions, materials theory, simulation and modeling, materials synthesis and processing, materials science under extreme conditions, ultrafast materials science, metallurgy, nanoscience and technology, nuclear fuelsmore » and energy security, optical materials science, and surface science. MSTD scientists play leadership roles in the scientific community in these key and emerging areas.« less

New Non-Intrusive Inspection Technologies for Nuclear Security and Nonproliferation

NASA Astrophysics Data System (ADS)

Ledoux, Robert J.

2015-10-01

Comprehensive monitoring of the supply chain for nuclear materials has historically been hampered by non-intrusive inspection systems that have such large false alarm rates that they are impractical in the flow of commerce. Passport Systems, Inc. (Passport) has developed an active interrogation system which detects fissionable material, high Z material, and other contraband in land, sea and air cargo. Passport's design utilizes several detection modalities including high resolution imaging, passive radiation detection, effective-Z (EZ-3D™) anomaly detection, Prompt Neutrons from Photofission (PNPF), and Nuclear Resonance Fluorescence (NRF) isotopic identification. These technologies combine to: detect fissionable, high-Z, radioactive and contraband materials, differentiate fissionable materials from high-Z shielding materials, and isotopically identify actinides, Special Nuclear Materials (SNM), and other contraband (e.g. explosives, drugs, nerve agents). Passport's system generates a 3-D image of the scanned object which contains information such as effective-Z and density, as well as a 2-D image and isotopic and fissionable information for regions of interest.

AGC 2 Irradiated Material Properties Analysis

DOE Office of Scientific and Technical Information (OSTI.GOV)

Rohrbaugh, David Thomas

2017-05-01

The Advanced Reactor Technologies Graphite Research and Development Program is conducting an extensive graphite irradiation experiment to provide data for licensing of a high temperature reactor (HTR) design. In past applications, graphite has been used effectively as a structural and moderator material in both research and commercial high temperature gas cooled reactor designs. , Nuclear graphite H 451, used previously in the United States for nuclear reactor graphite components, is no longer available. New nuclear graphite grades have been developed and are considered suitable candidates for new HTR reactor designs. To support the design and licensing of HTR core componentsmore » within a commercial reactor, a complete properties database must be developed for these current grades of graphite. Quantitative data on in service material performance are required for the physical, mechanical, and thermal properties of each graphite grade, with a specific emphasis on data accounting for the life limiting effects of irradiation creep on key physical properties of the HTR candidate graphite grades. Further details on the research and development activities and associated rationale required to qualify nuclear grade graphite for use within the HTR are documented in the graphite technology research and development plan.« less

Advanced Borobond™ Shields for Nuclear Materials Containment and Borobond™ Immobilization of Volatile Fission Products - Final CRADA Report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Wagh, Arun S.

2016-05-19

Borobond is a company-proprietary material developed by the CRADA partner in collaboration with Argonne, and is based on Argonne's Ceramicrete technology. It is being used by DOE for nuclear materials safe storage, and Boron Products, LLC is the manufacturer and supplier of Borobond. The major objective of this project was to produce a more versatile composition of this material and find new applications. Major target applications were use for nuclear radiation shields, such as in dry storage casks; use in immobilization of most difficult waste streams, such as Hanford K-Basin waste; use for soluble and volatile fission products, such asmore » Cs, Tc, Sr, and I; and use for corrosion and fire protection applications in nuclear facilities.« less

Continuous Efforts to Develop the National System for Material Control and Accounting Training at the George Kuzmycz Training Center

DOE Office of Scientific and Technical Information (OSTI.GOV)

Gavrilyuk, Victor I.; Kirischuk, Volodymyr; Romanova, Olena

2011-10-01

The George Kuzmycz Training Center (GKTC) for Physical Protection, Control and Accounting of Nuclear Materials was established in 1998 at the Kyiv Institute of Nuclear Research of the Ukrainian Academy of Sciences through the collaborative efforts of the United States and Ukraine. Later the European Commission (EC) joined the US in assisting with the Material Control and Accounting (MC&A) part of the GKTC training program. The Government of Ukraine designated the GKTC as the National Center responsible for providing training and methodological support for nuclear facilities and nuclear specialists in the Material Protection, Control and Accounting (MPC&A) area. To increasemore » the efficiency of the State MC&A system an essential number of new regulations, norms and rules have been developed; some of them mandate regular and more intensive training of MC&A specialists in the industry - from those working at the Nuclear Regulatory Authority of Ukraine to the personnel of nuclear facilities. To meet such regulations GKTC plans to develop next year a number of training courses under the EC contract; such courses will reflect both the specifics of Ukrainian nuclear facilities and the level of expertise of the facilities’ personnel. The NDA training laboratory, established in 2003 with US DOE financial support and technical and methodological assistance, considerably expanded the GKTC’s training capabilities for MC&A programs. Next year that lab will be supplemented with a new NM Surveillance and Containment laboratory as current plans call for under the EC contract. The US DOE is also providing funding to support that project. Under the EC contract the laboratory will be equipped with state-of-the-art, advanced surveillance and containment equipment which will strengthen and expand even further the GKTC’s training capabilities and potential. This will allow GKTC to train Ukrainian nuclear industry specialists in practically all MC&A topics. Furthermore, GKTC is planning to offer already this year and to continue offering in the future, on a regular basis, the courses that have already been developed, while continuing to develop new ones. This paper briefly describes the work done to upgrade the Ukrainian MC&A system, both at the State and at the facilities’ levels, as well as the results of efforts to develop the National System for training MC&A personnel at the GKTC. It also describes problems encountered and their solution; it includes comments, suggestions and recommendations for future activities to promote and improve the nuclear material management culture in Ukraine.« less

Science based integrated approach to advanced nuclear fuel development - integrated multi-scale multi-physics hierarchical modeling and simulation framework Part III: cladding

DOE Office of Scientific and Technical Information (OSTI.GOV)

Tome, Carlos N; Caro, J A; Lebensohn, R A

2010-01-01

Advancing the performance of Light Water Reactors, Advanced Nuclear Fuel Cycles, and Advanced Reactors, such as the Next Generation Nuclear Power Plants, requires enhancing our fundamental understanding of fuel and materials behavior under irradiation. The capability to accurately model the nuclear fuel systems to develop predictive tools is critical. Not only are fabrication and performance models needed to understand specific aspects of the nuclear fuel, fully coupled fuel simulation codes are required to achieve licensing of specific nuclear fuel designs for operation. The backbone of these codes, models, and simulations is a fundamental understanding and predictive capability for simulating themore » phase and microstructural behavior of the nuclear fuel system materials and matrices. In this paper we review the current status of the advanced modeling and simulation of nuclear reactor cladding, with emphasis on what is available and what is to be developed in each scale of the project, how we propose to pass information from one scale to the next, and what experimental information is required for benchmarking and advancing the modeling at each scale level.« less

Non-Nuclear Testing of Fission Technologies at NASA MSFC

NASA Technical Reports Server (NTRS)

Houts, Robert G.; Pearson, J. Boise; Aschenbrenner, Kenneth C.; Bradley, David E.; Dickens, Ricky E.; Emrich, William J.; Garber, Anne E.; Godfroy, Thomas J.; Harper, Roger T.; Martin, Jim J.;

George Kuzmycz Training Center : 5 years of American-Ukrainian efforts in the field of material control and accounting

DOE Office of Scientific and Technical Information (OSTI.GOV)

Gavrilyuk, V. I.; Gavrylyuk, A. V.; Kirischuk, V. I.

2004-01-01

The George Kuzmycz Training Center for Physical Protection, Control and Accounting of Nuclear Material (GKTC) was established in October 1998 at the Kiev Institute for Nuclear Research. During the past six years, about 700 professionals from all Ukrainian nuclear installations, executive and regulatory bodies were trained at the GKTC. Future Material Control and Accounting (MC&A) training courses are going to be held even more frequently because Ukraine has already signed the Additional Model Protocol and its ratification by Ukrainian Parliament is expected to happen very soon. Additionally, a number of new training courses will be developed. US DOE trough Argonnemore » National Laboratory has made significant efforts to transfer Automated Inventory/Material Accounting System (AIMAS) software to Ukraine. As a result, AIMAS software can be used as a basic code for the development of the Computerized MC&A System for all Ukrainian nuclear facilities despite their differences. In 2003, a new laboratory for Nondestructive Assay (NDA) was established with assistance from the U.S. Department of Energy. As a result, GKTC training capabilities will increase substantially. Furthermore, in order to increase the efficiency of NDA laboratory, it is planned to use the NDA equipment for a program of interdiction of illicit traffic of nuclear materials in Ukraine. American-Ukrainian MC&A efforts for the last 6 years, the problems encountered and the solutions to these problems, as well as comments, suggestions and recommendations for future activity at GKTC to promote and improve the nuclear material management culture in Ukraine are discussed in detail.« less

Investigating the binding properties of porous drug delivery systems using nuclear sensors (radiotracers) and positron annihilation lifetime spectroscopy--predicting conditions for optimum performance.

PubMed

Mume, Eskender; Lynch, Daniel E; Uedono, Akira; Smith, Suzanne V

2011-06-21

Understanding how the size, charge and number of available pores in porous material influences the uptake and release properties is important for optimising their design and ultimately their application. Unfortunately there are no standard methods for screening porous materials in solution and therefore formulations must be developed for each encapsulated agent. This study investigates the potential of a library of radiotracers (nuclear sensors) for assessing the binding properties of hollow silica shell materials. Uptake and release of Cu(2+) and Co(2+) and their respective complexes with polyazacarboxylate macrocycles (dota and teta) and a series of hexa aza cages (diamsar, sarar and bis-(p-aminobenzyl)-diamsar) from the hollow silica shells was monitored using their radioisotopic analogues. Coordination chemistry of the metal (M) species, subtle alterations in the molecular architecture of ligands (Ligand) and their resultant complexes (M-Ligand) were found to significantly influence their uptake over pH 3 to 9 at room temperature. Positively charged species were selectively and rapidly (within 10 min) absorbed at pH 7 to 9. Negatively charged species were preferentially absorbed at low pH (3 to 5). Rates of release varied for each nuclear sensor, and time to establish equilibrium varied from minutes to days. The subtle changes in design of the nuclear sensors proved to be a valuable tool for determining the binding properties of porous materials. The data support the development of a library of nuclear sensors for screening porous materials for use in optimising the design of porous materials and the potential of nuclear sensors for high through-put screening of materials.

Secure Transportation of HEU in Romania

DOE Office of Scientific and Technical Information (OSTI.GOV)

None

2009-07-06

The National Nuclear Security Administration has announced the final shipments of Russian-origin highly enriched uranium (HEU) nuclear fuel from Romania. The material was removed and returned to Russia by air for storage at two secure nuclear facilities, making Romania the first country to remove all HEU since President Obama outlined his commitment to securing all vulnerable nuclear material around the world within four years. This was also the first time NNSA has shipped spent HEU by airplane, a development that will help accelerate efforts to meet the Presidents objective.

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

DOE Office of Scientific and Technical Information (OSTI.GOV)

Menon, S.

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

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kornreich, Drew E; Vaidya, Rajendra U; Ammerman, Curtt N

Integrated Computational Materials Engineering (ICME) is a novel overarching approach to bridge length and time scales in computational materials science and engineering. This approach integrates all elements of multi-scale modeling (including various empirical and science-based models) with materials informatics to provide users the opportunity to tailor material selections based on stringent application needs. Typically, materials engineering has focused on structural requirements (stress, strain, modulus, fracture toughness etc.) while multi-scale modeling has been science focused (mechanical threshold strength model, grain-size models, solid-solution strengthening models etc.). Materials informatics (mechanical property inventories) on the other hand, is extensively data focused. All of thesemore » elements are combined within the framework of ICME to create architecture for the development, selection and design new composite materials for challenging environments. We propose development of the foundations for applying ICME to composite materials development for nuclear and high-radiation environments (including nuclear-fusion energy reactors, nuclear-fission reactors, and accelerators). We expect to combine all elements of current material models (including thermo-mechanical and finite-element models) into the ICME framework. This will be accomplished through the use of a various mathematical modeling constructs. These constructs will allow the integration of constituent models, which in tum would allow us to use the adaptive strengths of using a combinatorial scheme (fabrication and computational) for creating new composite materials. A sample problem where these concepts are used is provided in this summary.« less

JAEA's actions and contributions to the strengthening of nuclear non-proliferation

NASA Astrophysics Data System (ADS)

Suda, Kazunori; Suzuki, Mitsutoshi; Michiji, Toshiro

2012-06-01

Japan, a non-nuclear weapons state, has established a commercial nuclear fuel cycle including LWRs, and now is developing a fast neutron reactor fuel cycle as part of the next generation nuclear energy system, with commercial operation targeted for 2050. Japan Atomic Energy Agency (JAEA) is the independent administrative agency for conducting comprehensive nuclear R&D in Japan after the merger of Japan Atomic Energy Research Institute (JAERI) and Japan Nuclear Cycle Development Institute (JNC). JAEA and its predecessors have extensive experience in R&D, facility operations, and safeguards development and implementation for new types of nuclear facilities for the peaceful use of nuclear energy. As the operator of various nuclear fuel cycle facilities and numerous nuclear materials, JAEA makes international contributions to strengthen nuclear non-proliferation. This paper provides an overview of JAEA's development of nuclear non-proliferation and safeguards technologies, including remote monitoring of nuclear facilities, environmental sample analysis methods and new efforts since the 2010 Nuclear Security Summit in Washington D.C.

The Power of Integrators, Financiers, and Insurers to Reduce Proliferation Risks: Nuclear Dual-Use Goods

DOE Office of Scientific and Technical Information (OSTI.GOV)

Weise, Rachel A.; Hund, Gretchen

2015-05-01

Globalization of manufacturing supply chains has changed the nature of nuclear proliferation. Before 1991, nonproliferation efforts focused almost exclusively on limiting the spread of materials and equipment specifically designed for nuclear use -- reactors, centrifuges, and fissile material. Dual-use items, those items with both nuclear and non-nuclear applications, were not closely scrutinized or controlled. However, in 1991 the international community discovered that Iraq had developed a fairly sophisticated nuclear weapons program by importing dual-use items; this discovery spurred the international community to increase controls on dual-use technologies. Despite these international efforts, dual-use items are still a challenge for those seekingmore » to limit proliferation.« less

PHASE I MATERIALS PROPERTY DATABASE DEVELOPMENT FOR ASME CODES AND STANDARDS

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ren, Weiju; Lin, Lianshan

2013-01-01

To support the ASME Boiler and Pressure Vessel Codes and Standard (BPVC) in modern information era, development of a web-based materials property database is initiated under the supervision of ASME Committee on Materials. To achieve efficiency, the project heavily draws upon experience from development of the Gen IV Materials Handbook and the Nuclear System Materials Handbook. The effort is divided into two phases. Phase I is planned to deliver a materials data file warehouse that offers a depository for various files containing raw data and background information, and Phase II will provide a relational digital database that provides advanced featuresmore » facilitating digital data processing and management. Population of the database will start with materials property data for nuclear applications and expand to data covering the entire ASME Code and Standards including the piping codes as the database structure is continuously optimized. The ultimate goal of the effort is to establish a sound cyber infrastructure that support ASME Codes and Standards development and maintenance.« less

Foreign Trip Report MATGEN-IV Sep 24- Oct 26, 2007

DOE Office of Scientific and Technical Information (OSTI.GOV)

de Caro, M S

2007-10-30

Gen-IV activities in France, Japan and US focus on the development of new structural materials for Gen-IV nuclear reactors. Oxide dispersion strengthened (ODS) F/M steels have raised considerable interest in nuclear applications. Promising collaborations can be established seeking fundamental knowledge of relevant Gen-IV ODS steel properties (see attached travel report on MATGEN- IV 'Materials for Generation IV Nuclear Reactors'). Major highlights refer to results on future Ferritic/Martensitic steel cladding candidates (relevant to Gen-IV materials properties for LFR Materials Program) and on thermodynamic and mechanic behavior of metallic FeCr binary alloys, base matrix for future candidate steels (for the LLNL-LDRD projectmore » on Critical Issues on Materials for Gen-IV Reactors).« less

Fabrication and Testing of CERMET Fuel Materials for Nuclear Thermal Propulsion

NASA Technical Reports Server (NTRS)

Hickman, Robert; Broadway, Jeramie; Mireles, Omar

2012-01-01

A first generation Nuclear Cryogenic Propulsion Stage (NCPS) based on Nuclear Thermal Propulsion (NTP) is currently being developed for Advanced Space Exploration Systems. The overall goal of the project is to address critical NTP technology challenges and programmatic issues to establish confidence in the affordability and viability of NTP systems. The current technology roadmap for NTP identifies the development of a robust fuel form as a critical near term need. The lack of a qualified nuclear fuel is a significant technical risk that will require a considerable fraction of program resources to mitigate. Due to these risks and the cost for qualification, the development and selection of a primary fuel must begin prior to Authority to Proceed (ATP) for a specific mission. The fuel development is a progressive approach to incrementally reduce risk, converge the fuel materials, and mature the design and fabrication process of the fuel element. A key objective of the current project is to advance the maturity of CERMET fuels. The work includes fuel processing development and characterization, fuel specimen hot hydrogen screening, and prototypic fuel element testing. Early fuel materials development is critical to help validate requirements and fuel performance. The purpose of this paper is to provide an overview and status of the work at Marshall Space Flight Center (MSFC).

Nuclear Proliferation Technology Trends Analysis

DOE Office of Scientific and Technical Information (OSTI.GOV)

Zentner, Michael D.; Coles, Garill A.; Talbert, Robert J.

2005-10-04

A process is underway to develop mature, integrated methodologies to address nonproliferation issues. A variety of methodologies (both qualitative and quantitative) are being considered. All have one thing in common, a need for a consistent set of proliferation related data that can be used as a basis for application. One approach to providing a basis for predicting and evaluating future proliferation events is to understand past proliferation events, that is, the different paths that have actually been taken to acquire or attempt to acquire special nuclear material. In order to provide this information, this report describing previous material acquisition activitiesmore » (obtained from open source material) has been prepared. This report describes how, based on an evaluation of historical trends in nuclear technology development, conclusions can be reached concerning: (1) The length of time it takes to acquire a technology; (2) The length of time it takes for production of special nuclear material to begin; and (3) The type of approaches taken for acquiring the technology. In addition to examining time constants, the report is intended to provide information that could be used to support the use of the different non-proliferation analysis methodologies. Accordingly, each section includes: (1) Technology description; (2) Technology origin; (3) Basic theory; (4) Important components/materials; (5) Technology development; (6) Technological difficulties involved in use; (7) Changes/improvements in technology; (8) Countries that have used/attempted to use the technology; (9) Technology Information; (10) Acquisition approaches; (11) Time constants for technology development; and (12) Required Concurrent Technologies.« less

Nuclear Fuel Reprocessing: U.S. Policy Development

DTIC Science & Technology

2006-11-29

to the chemical separation of fissionable uranium and plutonium from irradiated nuclear fuel. The World War II-era Manhattan Project developed...created the Atomic Energy Commission (AEC) and transferred production and control of fissionable materials from the Manhattan Project . As the exclusive

Materials for Active Engagement in Nuclear and Particle Physics Courses

NASA Astrophysics Data System (ADS)

Loats, Jeff; Schwarz, Cindy; Krane, Ken

2013-04-01

Physics education researchers have developed a rich variety of research-based instructional strategies that now permeate many introductory courses. Carrying these active-engagement techniques to upper-division courses requires effort and is bolstered by experience. Instructors interested in these methods thus face a large investment of time to start from scratch. This NSF-TUES grant, aims to develop, test and disseminate active-engagement materials for nuclear and particle physics topics. We will present examples of these materials, including: a) Conceptual discussion questions for use with Peer Instruction; b) warm-up questions for use with Just in Time Teaching, c) ``Back of the Envelope'' estimation questions and small-group case studies that will incorporate use of nuclear and particle databases, as well as d) conceptual exam questions.

ROBOCAL: An automated NDA (nondestructive analysis) calorimetry and gamma isotopic system

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hurd, J.R.; Powell, W.D.; Ostenak, C.A.

1989-11-01

ROBOCAL, which is presently being developed and tested at Los Alamos National Laboratory, is a full-scale, prototype robotic system for remote calorimetric and gamma-ray analysis of special nuclear materials. It integrates a fully automated, multidrawer, vertical stacker-retriever system for staging unmeasured nuclear materials, and a fully automated gantry robot for computer-based selection and transfer of nuclear materials to calorimetric and gamma-ray measurement stations. Since ROBOCAL is designed for minimal operator intervention, a completely programmed user interface is provided to interact with the automated mechanical and assay systems. The assay system is designed to completely integrate calorimetric and gamma-ray data acquisitionmore » and to perform state-of-the-art analyses on both homogeneous and heterogeneous distributions of nuclear materials in a wide variety of matrices.« less

Planetary surface reactor shielding using indigenous materials

DOE Office of Scientific and Technical Information (OSTI.GOV)

Houts, Michael G.; Poston, David I.; Trellue, Holly R.

The exploration and development of Mars will require abundant surface power. Nuclear reactors are a low-cost, low-mass means of providing that power. A significant fraction of the nuclear power system mass is radiation shielding necessary for protecting humans and/or equipment from radiation emitted by the reactor. For planetary surface missions, it may be desirable to provide some or all of the required shielding from indigenous materials. This paper examines shielding options that utilize either purely indigenous materials or a combination of indigenous and nonindigenous materials.

SOLID SOLUTION CARBIDES ARE THE KEY FUELS FOR FUTURE NUCLEAR THERMAL PROPULSION

NASA Technical Reports Server (NTRS)

Panda, Binayak; Hickman, Robert R.; Shah, Sandeep

2005-01-01

Nuclear thermal propulsion uses nuclear energy to directly heat a propellant (such as liquid hydrogen) to generate thrust for space transportation. In the 1960 s, the early Rover/Nuclear Engine for Rocket Propulsion Application (NERVA) program showed very encouraging test results for space nuclear propulsion but, in recent years, fuel research has been dismal. With NASA s renewed interest in long-term space exploration, fuel researchers are now revisiting the RoverMERVA findings, which indicated several problems with such fuels (such as erosion, chemical reaction of the fuel with propellant, fuel cracking, and cladding issues) that must be addressed. It is also well known that the higher the temperature reached by a propellant, the larger the thrust generated from the same weight of propellant. Better use of fuel and propellant requires development of fuels capable of reaching very high temperatures. Carbides have the highest melting points of any known material. Efforts are underway to develop carbide mixtures and solid solutions that contain uranium carbide, in order to achieve very high fuel temperatures. Binary solid solution carbides (U, Zr)C have proven to be very effective in this regard. Ternary carbides such as (U, Zr, X) carbides (where X represents Nb, Ta, W, and Hf) also hold great promise as fuel material, since the carbide mixtures in solid solution generate a very hard and tough compact material. This paper highlights past experience with early fuel materials and bi-carbides, technical problems associated with consolidation of the ingredients, and current techniques being developed to consolidate ternary carbides as fuel materials.

Annual Report to Congress of the Atomic Energy Commission for 1969

DOE Office of Scientific and Technical Information (OSTI.GOV)

Seaborg, Glenn T.

1970-01-31

The document represents the 1969 Annual Report of the Atomic Energy Commission (AEC) to Congress. The report opens with ''An Introduction to the Atomic Energy Programs during 1969'' followed by 17 Chapters, 8 appendices and an index. Chapters are as follows: (1) Source, Special, and Byproduct Nuclear Materials; (2) Nuclear Materials Safeguards; (3) The Nuclear Defense Effort; (4) Naval Propulsion Reactors; (5) Reactor Development and Technology; (6) Licensing and Regulating the Atom; (7) Operational and Public Safety; (8) Space Nuclear Propulsion; (9) Specialized Nuclear Power; (10) Isotopic Radiation Applications; (11) Peaceful Nuclear Explosives; (12) International Affairs and Cooperation; (13) Informationalmore » and Related Activities; (14) Nuclear Education and Training; (15) Biomedical and Physical Research; (16) Industrial Participation Aspects; and, (17) Administrative and Management Matters.« less

Annual Report to Congress of the Atomic Energy Commission for 1968

DOE Office of Scientific and Technical Information (OSTI.GOV)

Seaborg, Glenn T.

1969-01-31

The document represents the 1968 Annual Report of the Atomic Energy Commission (AEC) to Congress. The report opens with ''An Introduction to the Atomic Energy Programs during 1968'' followed by 17 Chapters, 8 appendices and an index. Chapters are as follows: (1) Source, Special, and Nuclear Byproduct Materials; (2) Nuclear Materials Safeguards; (3) The Nuclear Defense Effort; (4) Naval Propulsion Reactors; (5) Reactor Development and Technology; (6) Licensing and Regulating the Atom; (7) Operational and Public Safety; (8) Nuclear Rocket Propulsion; (9) Specialized Nuclear Power; (10) Isotopic Radiation Applications; (11) Peaceful Nuclear Explosives; (12) International Affairs and Cooperation; (13) Informationalmore » and Related Activities; (14) Nuclear Education and Training; (15) Biomedical and Physical Research; (16) Industrial Participation Aspects; and, (17) Administrative and Management Matters.« less

Tracking of Nuclear Production using Indigenous Species: Final LDRD Report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Alam, Todd Michael; Alam, Mary Kathleen; McIntyre, Sarah K.

Our LDRD research project sought to develop an analytical method for detection of chemicals used in nuclear materials processing. Our approach is distinctly different than current research involving hardware-based sensors. By utilizing the response of indigenous species of plants and/or animals surrounding (or within) a nuclear processing facility, we propose tracking 'suspicious molecules' relevant to nuclear materials processing. As proof of concept, we have examined TBP, tributylphosphate, used in uranium enrichment as well as plutonium extraction from spent nuclear fuels. We will compare TBP to the TPP (triphenylphosphate) analog to determine the uniqueness of the metabonomic response. We show thatmore » there is a unique metabonomic response within our animal model to TBP. The TBP signature can further be delineated from that of TPP. We have also developed unique methods of instrumental transfer for metabonomic data sets.« less

IMPROVED TECHNNOLOGY TO PREVENT ILLICIT TRAFFICKING IN NUCLEAR MATERIALS

DOE Office of Scientific and Technical Information (OSTI.GOV)

Richardson, J H

2005-07-20

The proliferation of nuclear, chemical, and biological weapons (collectively known as weapons of mass destruction, or WMD) and the potential acquisition and use of WMD against the world by terrorists are extremely serious threats to international security. These threats are complex and interrelated. There are myriad routes to weapons of mass destruction--many different starting materials, material sources, and production processes. There are many possible proliferators--threshold countries, rogue states, state-sponsored or transnational terrorists groups, domestic terrorists, and even international crime organizations. Motives for acquiring and using WMD are similarly wide ranging--from a desire to change the regional power balance, deny accessmore » to a strategic area, or alter international policy to extortion, revenge, or hate. Because of the complexity of this threat landscape, no single program, technology, or capability--no silver bullet--can solve the WMD proliferation and terrorism problem. An integrated program is needed that addresses the WMD proliferation and terrorism problem from end to end, from prevention to detection, reversal, and response, while avoiding surprise at all stages, with different activities directed specifically at different types of WMD and proliferators. Radiation detection technologies are an important tool in the prevention of proliferation. A variety of new developments have enabled enhanced performance in terms of energy resolution, spatial resolution, predictive modeling and simulation, active interrogation, and ease of operation and deployment in the field. The radiation properties of nuclear materials, particularly highly enriched uranium (HEU), make the detection of smuggled nuclear materials technically difficult. A number of efforts are under way to devise improved detector materials and instruments and to identify novel signatures that could be detected. Key applications of this work include monitoring for radioactive materials at choke points, searching for nuclear materials, and developing instruments for response personnel.« less

10 CFR 74.41 - Nuclear material control and accounting for special nuclear material of moderate strategic...

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Nuclear material control and accounting for special nuclear material of moderate strategic significance. 74.41 Section 74.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material...

10 CFR 74.31 - Nuclear material control and accounting for special nuclear material of low strategic significance.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Nuclear material control and accounting for special nuclear material of low strategic significance. 74.31 Section 74.31 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material of Low...

10 CFR 74.41 - Nuclear material control and accounting for special nuclear material of moderate strategic...

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Nuclear material control and accounting for special nuclear material of moderate strategic significance. 74.41 Section 74.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material...

10 CFR 74.41 - Nuclear material control and accounting for special nuclear material of moderate strategic...

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Nuclear material control and accounting for special nuclear material of moderate strategic significance. 74.41 Section 74.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material...

10 CFR 74.41 - Nuclear material control and accounting for special nuclear material of moderate strategic...

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Nuclear material control and accounting for special nuclear material of moderate strategic significance. 74.41 Section 74.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material...

10 CFR 74.31 - Nuclear material control and accounting for special nuclear material of low strategic significance.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Nuclear material control and accounting for special nuclear material of low strategic significance. 74.31 Section 74.31 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material of Low...

10 CFR 74.41 - Nuclear material control and accounting for special nuclear material of moderate strategic...

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for special nuclear material of moderate strategic significance. 74.41 Section 74.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material...

10 CFR 74.31 - Nuclear material control and accounting for special nuclear material of low strategic significance.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Nuclear material control and accounting for special nuclear material of low strategic significance. 74.31 Section 74.31 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material of Low...

10 CFR 74.31 - Nuclear material control and accounting for special nuclear material of low strategic significance.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Nuclear material control and accounting for special nuclear material of low strategic significance. 74.31 Section 74.31 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material of Low...

The nuclear energy outlook--a new book from the OECD nuclear energy agency.

PubMed

Yoshimura, Uichiro

2011-01-01

This paper summarizes the key points of a report titled Nuclear Energy Outlook, published in 2008 by the Nuclear Energy Agency of the Organization for Economic Cooperation and Development, which has 30 member nations. The report discusses the commitment of many nations to increase nuclear power generating capacity and the potential rate of building new electricity-generating nuclear plants by 2030 to 2050. The resulting decrease in carbon dioxide emissions from fossil fuel combustion resulting from an increase in nuclear power sources is described. Other topics that are discussed include the need to develop non-proliferative nuclear fuels, the importance of developing geological disposal facilities or reprocessing capabilities for spent nuclear fuel and high-level radioactive waste materials, and the requirements for a larger nuclear workforce and greater cost competitiveness for nuclear power generation. Copyright © 2010 Health Physics Society

Efforts of Uzbekistan to prevent nuclear terrorism and smuggling of radioactive and nuclear materials.

PubMed

Petrenko, V D; Karimov, Yu N; Podkovirin, A I; Shipilov, N N; Yuldashev, B S; Fazylov, M I

2005-01-01

Uzbekistan is located on the cross-roads from the north--Russia, Western Europe--to the south--Afghanistan, Iran, Iraq and others. The appearance of terrorist organizations urged some Asian countries to make the nuclear weapons, the making the task of stopping the transportation of nuclear materials and technologies from the north (from countries possessing nuclear weapon) to the south (to countries desiring to have weapons and its components) a reality. To resolve this problem, on the main transportation routes, "Yantar" stationary radiation monitors of Russian production were installed, and development and production of monitors of our own make was started. This paper covers these works as well as those on preventing possible terrorist attacks on nuclear objects of Uzbekistan.

Qualification of submerged-arc narrow strip cladding process

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ayres, P.S.; Gottschling, J.D.; Jeffers, G.K.

1975-08-01

An unique narrow strip cladding process for use on both plate and forging material for nuclear components was developed. The qualification testing of this low-heat input process for cladding nuclear components, including those of SA508 Class 2 material is described. The theory that explains the acceptable results of these tests is also given. (auth)

Qualification of submerged-arc narrow strip cladding process

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ayres, P.S.; Gottschling, J.D.; Jeffers, G.K.

1976-03-01

Babcock and Wilcox has developed an unique narrow strip cladding process for use on both plate and forging material for nuclear components. The qualification testing of this low-heat input process for cladding nuclear components is described, including those of SA508 Class 2 material. The theory that explains the acceptable results of these tests is also given.

ATF Neutron Irradiation Program Irradiation Vehicle Design Concepts

DOE Office of Scientific and Technical Information (OSTI.GOV)

Geringer, J. W.; Katoh, Yutai; Howard, Richard H.

The Japan Atomic Energy Agency (JAEA) under the Civil Nuclear Energy Working Group (CNWG) is engaged in a cooperative research effort with the U.S. Department of Energy (DOE) to explore issues related to nuclear energy, including research on accident-tolerant fuels and materials for use in light water reactors. This work develops a draft technical plan for a neutron irradiation program on the candidate accident-tolerant fuel cladding materials and elements using the High Flux Isotope Reactor (HFIR). The research program requires the design of a detailed experiment, development of test vehicles, irradiation of test specimens, possible post irradiation examination and characterizationmore » of irradiated materials and the shipment of irradiated materials to Japan. This report discusses the conceptual design, the development and irradiation of the test vehicles.« less

OCE NEMP PROGRAM DEVELOPMENT OF CRITERIA FOR PROTECTION OF NIKE-X POWER PLANT AND FACILITIES ELECTRICAL SYSTEMS AGAINST NUCLEAR ELECTROMAGNETIC PULSE EFFECTS.

DTIC Science & Technology

technical backup material for the OCE NEMP PROGRAM, Development of Criteria for Protection of NIKE-X Power Plant and Facilities Electrical Systems Against Nuclear Electromagnetic Pulse Effects, Protective MEASURES. (Author)

10 CFR 74.51 - Nuclear material control and accounting for strategic special nuclear material.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Nuclear material control and accounting for strategic special nuclear material. 74.51 Section 74.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Formula Quantities of Strategic Special Nuclear...

10 CFR 74.51 - Nuclear material control and accounting for strategic special nuclear material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for strategic special nuclear material. 74.51 Section 74.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Formula Quantities of Strategic Special Nuclear...

10 CFR 74.51 - Nuclear material control and accounting for strategic special nuclear material.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Nuclear material control and accounting for strategic special nuclear material. 74.51 Section 74.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Formula Quantities of Strategic Special Nuclear...

10 CFR 74.51 - Nuclear material control and accounting for strategic special nuclear material.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Nuclear material control and accounting for strategic special nuclear material. 74.51 Section 74.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Formula Quantities of Strategic Special Nuclear...

10 CFR 74.51 - Nuclear material control and accounting for strategic special nuclear material.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Nuclear material control and accounting for strategic special nuclear material. 74.51 Section 74.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Formula Quantities of Strategic Special Nuclear...

Methods and apparatuses for the development of microstructured nuclear fuels

DOEpatents

Jarvinen, Gordon D [Los Alamos, NM; Carroll, David W [Los Alamos, NM; Devlin, David J [Santa Fe, NM

2009-04-21

Microstructured nuclear fuel adapted for nuclear power system use includes fissile material structures of micrometer-scale dimension dispersed in a matrix material. In one method of production, fissile material particles are processed in a chemical vapor deposition (CVD) fluidized-bed reactor including a gas inlet for providing controlled gas flow into a particle coating chamber, a lower bed hot zone region to contain powder, and an upper bed region to enable powder expansion. At least one pneumatic or electric vibrator is operationally coupled to the particle coating chamber for causing vibration of the particle coater to promote uniform powder coating within the particle coater during fuel processing. An exhaust associated with the particle coating chamber and can provide a port for placement and removal of particles and powder. During use of the fuel in a nuclear power reactor, fission products escape from the fissile material structures and come to rest in the matrix material. After a period of use in a nuclear power reactor and subsequent cooling, separation of the fissile material from the matrix containing the embedded fission products will provide an efficient partitioning of the bulk of the fissile material from the fission products. The fissile material can be reused by incorporating it into new microstructured fuel. The fission products and matrix material can be incorporated into a waste form for disposal or processed to separate valuable components from the fission products mixture.

Review of current nuclear fallout codes.

PubMed

Auxier, Jerrad P; Auxier, John D; Hall, Howard L

2017-05-01

The importance of developing a robust nuclear forensics program to combat the illicit use of nuclear material that may be used as an improvised nuclear device is widely accepted. In order to decrease the threat to public safety and improve governmental response, government agencies have developed fallout-analysis codes to predict the fallout particle size, dose, and dispersion and dispersion following a detonation. This paper will review the different codes that have been developed for predicting fallout from both chemical and nuclear weapons. This will decrease the response time required for the government to respond to the event. Copyright © 2017 The Authors. Published by Elsevier Ltd.. All rights reserved.

REBOCOL (Robotic Calorimetry): An automated NDA (Nondestructive assay) calorimetry and gamma isotopic system

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hurd, J.R.; Bonner, C.A.; Ostenak, C.A.

1989-01-01

ROBOCAL, which is presently being developed and tested at Los Alamos National Laboratory, is a full-scale, prototypical robotic system, for remote calorimetric and gamma-ray analysis of special nuclear materials. It integrates a fully automated, multi-drawer, vertical stacker-retriever system for staging unmeasured nuclear materials, and a fully automated gantry robot for computer-based selection and transfer of nuclear materials to calorimetric and gamma-ray measurement stations. Since ROBOCAL is designed for minimal operator intervention, a completely programmed user interface and data-base system are provided to interact with the automated mechanical and assay systems. The assay system is designed to completely integrate calorimetric andmore » gamma-ray data acquisition and to perform state-of-the-art analyses on both homogeneous and heterogeneous distributions of nuclear materials in a wide variety of matrices. 10 refs., 10 figs., 4 tabs.« less

The Defense Threat Reduction Agency's Technical Nuclear Forensics Research and Development Program

NASA Astrophysics Data System (ADS)

Franks, J.

2015-12-01

The Defense Threat Reduction Agency (DTRA) Technical Nuclear Forensics (TNF) Research and Development (R&D) Program's overarching goal is to design, develop, demonstrate, and transition advanced technologies and methodologies that improve the interagency operational capability to provide forensics conclusions after the detonation of a nuclear device. This goal is attained through the execution of three focus areas covering the span of the TNF process to enable strategic decision-making (attribution): Nuclear Forensic Materials Exploitation - Development of targeted technologies, methodologies and tools enabling the timely collection, analysis and interpretation of detonation materials.Prompt Nuclear Effects Exploitation - Improve ground-based capabilities to collect prompt nuclear device outputs and effects data for rapid, complementary and corroborative information.Nuclear Forensics Device Characterization - Development of a validated and verified capability to reverse model a nuclear device with high confidence from observables (e.g., prompt diagnostics, sample analysis, etc.) seen after an attack. This presentation will outline DTRA's TNF R&D strategy and current investments, with efforts focusing on: (1) introducing new technical data collection capabilities (e.g., ground-based prompt diagnostics sensor systems; innovative debris collection and analysis); (2) developing new TNF process paradigms and concepts of operations to decrease timelines and uncertainties, and increase results confidence; (3) enhanced validation and verification (V&V) of capabilities through technology evaluations and demonstrations; and (4) updated weapon output predictions to account for the modern threat environment. A key challenge to expanding these efforts to a global capability is the need for increased post-detonation TNF international cooperation, collaboration and peer reviews.

Nuclear forensic analysis of a non-traditional actinide sample

DOE PAGES

Doyle, Jamie L.; Kuhn, Kevin John; Byerly, Benjamin; ...

2016-06-15

Nuclear forensic publications, performance tests, and research and development efforts typically target the bulk global inventory of intentionally safeguarded materials, such as plutonium (Pu) and uranium (U). Other materials, such as neptunium (Np), pose a nuclear security risk as well. Trafficking leading to recovery of an interdicted Np sample is a realistic concern especially for materials originating in countries that reprocesses fuel. Using complementary forensic methods, potential signatures for an unknown Np oxide sample were investigated. Measurement results were assessed against published Np processes to present hypotheses as to the original intended use, method of production, and origin for thismore » Np oxide.« less

Inspection applications with higher electron beam energies

NASA Astrophysics Data System (ADS)

Norman, D. R.; Jones, J. L.; Yoon, W. Y.; Haskell, K. J.; Sterbentz, J. W.; Zabriskie, J. M.; Hunt, A. W.; Harmon, F.; Kinlaw, M. T.

2005-12-01

The Idaho National Laboratory has developed prototype shielded nuclear material detection systems based on pulsed photonuclear assessment (PPA) techniques for the inspection of cargo containers. During this work, increased nuclear material detection capabilities have been demonstrated at higher electron beam energies than those allowed by federal regulations for cargo inspection. This paper gives a general overview of a nuclear material detection system, the PPA technique and discusses the benefits of using these higher energies. This paper also includes a summary of the numerical and test results from LINAC operations up to 24 MeV and discusses some of the federal energy limitations associated with cargo inspection.

Nuclear forensic analysis of a non-traditional actinide sample.

PubMed

Doyle, Jamie L; Kuhn, Kevin; Byerly, Benjamin; Colletti, Lisa; Fulwyler, James; Garduno, Katherine; Keller, Russell; Lujan, Elmer; Martinez, Alexander; Myers, Steve; Porterfield, Donivan; Spencer, Khalil; Stanley, Floyd; Townsend, Lisa; Thomas, Mariam; Walker, Laurie; Xu, Ning; Tandon, Lav

2016-10-01

Nuclear forensic publications, performance tests, and research and development efforts typically target the bulk global inventory of intentionally safeguarded materials, such as plutonium (Pu) and uranium (U). Other materials, such as neptunium (Np), pose a nuclear security risk as well. Trafficking leading to recovery of an interdicted Np sample is a realistic concern especially for materials originating in countries that reprocesses fuel. Using complementary forensic methods, potential signatures for an unknown Np oxide sample were investigated. Measurement results were assessed against published Np processes to present hypotheses as to the original intended use, method of production, and origin for this Np oxide. Published by Elsevier B.V.

Development of Measurement Methods for Detection of Special Nuclear Materials using D-D Pulsed Neutron Source

NASA Astrophysics Data System (ADS)

Misawa, Tsuyoshi; Takahashi, Yoshiyuki; Yagi, Takahiro; Pyeon, Cheol Ho; Kimura, Masaharu; Masuda, Kai; Ohgaki, Hideaki

2015-10-01

For detection of hidden special nuclear materials (SNMs), we have developed an active neutron-based interrogation system combined with a D-D fusion pulsed neutron source and a neutron detection system. In the detection scheme, we have adopted new measurement techniques simultaneously; neutron noise analysis and neutron energy spectrum analysis. The validity of neutron noise analysis method has been experimentally studied in the Kyoto University Critical Assembly (KUCA), and was applied to a cargo container inspection system by simulation.

Nuclear fuels for very high temperature applications

NASA Astrophysics Data System (ADS)

Lundberg, L. B.; Hobbins, R. R.

The success of the development of nuclear thermal propulsion devices and thermionic space nuclear power generation systems depends on the successful utilization of nuclear fuel materials at temperatures in the range 2000 to 3500 K. Problems associated with the utilization of uranium bearing fuel materials at these very high temperatures while maintaining them in the solid state for the required operating times are addressed. The critical issues addressed include evaporation, melting, reactor neutron spectrum, high temperature chemical stability, fabrication, fission induced swelling, fission product release, high temperature creep, thermal shock resistance, and fuel density, both mass and fissile atom. Candidate fuel materials for this temperature range are based on UO2 or uranium carbides. Evaporation suppression, such as a sealed cladding, is required for either fuel base. Nuclear performance data needed for design are sparse for all candidate fuel forms in this temperature range, especially at the higher temperatures.

National and International Security Applications of Cryogenic Detectors—Mostly Nuclear Safeguards

NASA Astrophysics Data System (ADS)

Rabin, Michael W.

2009-12-01

As with science, so with security—in both arenas, the extraordinary sensitivity of cryogenic sensors enables high-confidence detection and high-precision measurement even of the faintest signals. Science applications are more mature, but several national and international security applications have been identified where cryogenic detectors have high potential payoff. International safeguards and nuclear forensics are areas needing new technology and methods to boost speed, sensitivity, precision and accuracy. Successfully applied, improved nuclear materials analysis will help constrain nuclear materials diversion pathways and contribute to treaty verification. Cryogenic microcalorimeter detectors for X-ray, gamma-ray, neutron, and alpha-particle spectrometry are under development with these aims in mind. In each case the unsurpassed energy resolution of microcalorimeters reveals previously invisible spectral features of nuclear materials. Preliminary results of quantitative analysis indicate substantial improvements are still possible, but significant work will be required to fully understand the ultimate performance limits.

Report on {open_quotes}audit of internal controls over special nuclear materials{close_quotes}

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1996-04-01

The Department of Energy (Department) is responsible for safeguarding a significant amount of plutonium, uranium-233 and enriched uranium - collectively referred to as special nuclear materials - stored in the United States. The Department`s office of Nonproliferation and National Security has overall management cognizance for developing policies for safeguarding these materials, while other Headquarters program offices have {open_quotes}landlord{close_quotes} responsibilities for the sites where the materials are stored, and the Department`s operations and field offices provide onsite management of contractor operations. The Department`s management and operating contractors, under the direction of the Department, safeguard and account for the special nuclear materialmore » stored at Department sites.« less

Portable vibro-acoustic testing system for in situ microstructure characterization and metrology

NASA Astrophysics Data System (ADS)

Smith, James A.; Nichol, Corrie I.; Zuck, Larry D.; Fatemi, Mostafa

2018-04-01

There is a need in research reactors like the one at INL to inspect irradiated materials and structures. The goal of this work is to develop a portable scanning infrastructure for a material characterization technique called vibro-acoustography (VA) that has been developed by the Idaho National laboratory for nuclear applications to characterize fuel, cladding materials, and structures. The proposed VA technology is based on ultrasound and acoustic waves; however, it provides information beyond what is available from the traditional ultrasound techniques and can expand the knowledge on nuclear material characterization and microstructure evolution. This paper will report on the development of a portable scanning system that will be set up to characterize materials and components in open water reactors and canals in situ. We will show some initial laboratory results of images generated by vibro-acoustics of surrogate fuel plates and graphite structures and discuss the design of the portable system.

Nuclear techniques in studies of condensed matter

NASA Technical Reports Server (NTRS)

Singh, Jag J.

1987-01-01

Nuclear techniques have played an important role in the studies of materials over the past several decades. For example, X-ray diffraction, neutron diffraction, neutron activation, and particle- or photon-induced X-ray emission techniques have been used extensively for the elucidation of structural and compositional details of materials. Several new techniques have been developed recently. Four such techniques are briefly reviewed which have great potential in the study and development of new materials. Of these four, Mossbauer spectroscopy, muon spin rotation, and positron annihilation spectroscopy techniques exploit their great sensitivity to the local atomic environments in the test materials. Interest in synchrotron radiation, on the other hand, stems from its special properties, such as high intensity, high degree of polarization, and high monochromaticity. It is hoped that this brief review will stimulate interest in the exploitation of these newer techniques for the development of improved materials.

Evaluation of Spacecraft Shielding Effectiveness for Radiation Protection

NASA Technical Reports Server (NTRS)

Cucinotta, Francis A.; Wilson, John W.

1999-01-01

The potential for serious health risks from solar particle events (SPE) and galactic cosmic rays (GCR) is a critical issue in the NASA strategic plan for the Human Exploration and Development of Space (HEDS). The excess cost to protect against the GCR and SPE due to current uncertainties in radiation transmission properties and cancer biology could be exceedingly large based on the excess launch costs to shield against uncertainties. The development of advanced shielding concepts is an important risk mitigation area with the potential to significantly reduce risk below conventional mission designs. A key issue in spacecraft material selection is the understanding of nuclear reactions on the transmission properties of materials. High-energy nuclear particles undergo nuclear reactions in passing through materials and tissue altering their composition and producing new radiation types. Spacecraft and planetary habitat designers can utilize radiation transport codes to identify optimal materials for lowering exposures and to optimize spacecraft design to reduce astronaut exposures. To reach these objectives will require providing design engineers with accurate data bases and computationally efficient software for describing the transmission properties of space radiation in materials. Our program will reduce the uncertainty in the transmission properties of space radiation by improving the theoretical description of nuclear reactions and radiation transport, and provide accurate physical descriptions of the track structure of microscopic energy deposition.

Holdup measurement for nuclear fuel manufacturing plants

DOE Office of Scientific and Technical Information (OSTI.GOV)

Zucker, M.S.; Degen, M.; Cohen, I.

1981-07-13

The assay of nuclear material holdup in fuel manufacturing plants is a laborious but often necessary part of completing the material balance. A range of instruments, standards, and a methodology for assaying holdup has been developed. The objectives of holdup measurement are ascertaining the amount, distribution, and how firmly fixed the SNM is. The purposes are reconciliation of material unbalance during or after a manufacturing campaign or plant decommissioning, to decide security requirements, or whether further recovery efforts are justified.

New radiological material detection technologies for nuclear forensics: Remote optical imaging and graphene-based sensors.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Harrison, Richard Karl; Martin, Jeffrey B.; Wiemann, Dora K.

We developed new detector technologies to identify the presence of radioactive materials for nuclear forensics applications. First, we investigated an optical radiation detection technique based on imaging nitrogen fluorescence excited by ionizing radiation. We demonstrated optical detection in air under indoor and outdoor conditions for alpha particles and gamma radiation at distances up to 75 meters. We also contributed to the development of next generation systems and concepts that could enable remote detection at distances greater than 1 km, and originated a concept that could enable daytime operation of the technique. A second area of research was the development ofmore » room-temperature graphene-based sensors for radiation detection and measurement. In this project, we observed tunable optical and charged particle detection, and developed improved devices. With further development, the advancements described in this report could enable new capabilities for nuclear forensics applications.« less

Planetary surface reactor shielding using indigenous materials

DOE Office of Scientific and Technical Information (OSTI.GOV)

Houts, Michael G.; Poston, David I.; Trellue, Holly R.

The exploration and development of Mars will require abundant surface power. Nuclear reactors are a low-cost, low-mass means of providing that power. A significant fraction of the nuclear power system mass is radiation shielding necessary for protecting humans and/or equipment from radiation emitted by the reactor. For planetary surface missions, it may be desirable to provide some or all of the required shielding from indigenous materials. This paper examines shielding options that utilize either purely indigenous materials or a combination of indigenous and nonindigenous materials. {copyright} {ital 1999 American Institute of Physics.}

Dangers associated with civil nuclear power programmes: weaponization and nuclear waste.

PubMed

Boulton, Frank

2015-07-24

The number of nuclear power plants in the world rose exponentially to 420 by 1990 and peaked at 438 in 2002; but by 2014, as closed plants were not replaced, there were just 388. In spite of using more renewable energy, the world still relies on fossil fuels, but some countries plan to develop new nuclear programmes. Spent nuclear fuel, one of the most dangerous and toxic materials known, can be reprocessed into fresh fuel or into weapons-grade materials, and generates large amounts of highly active waste. This article reviews available literature on government and industry websites and from independent analysts on world energy production, the aspirations of the 'new nuclear build' programmes in China and the UK, and the difficulties in keeping the environment safe over an immense timescale while minimizing adverse health impacts and production of greenhouse gases, and preventing weaponization by non-nuclear-weapons states acquiring civil nuclear technology.

Study of a Tricarbide Grooved Ring Fuel Element for Nuclear Thermal Propulsion

NASA Technical Reports Server (NTRS)

Taylor, Brian; Emrich, Bill; Tucker, Dennis; Barnes, Marvin; Donders, Nicolas; Benensky, Kelsa

2018-01-01

Deep space exploration, especially that of Mars, is on the horizon as the next big challenge for space exploration. Nuclear propulsion, through which high thrust and efficiency can be achieved, is a promising option for decreasing the cost and logistics of such a mission. Work on nuclear thermal engines goes back to the days of the NERVA program. Currently, nuclear thermal propulsion is under development again in various forms to provide a superior propulsion system for deep space exploration. The authors have been working to develop a concept nuclear thermal engine that uses a grooved ring fuel element as an alternative to the traditional hexagonal rod design. The authors are also studying the use of carbide fuels. The concept was developed in order to increase surface area and heat transfer to the propellant. The use of carbides would also raise the operating temperature of the reactor. It is hoped that this could lead to a higher thrust to weight nuclear thermal engine. This paper describes the modeling of neutronics, heat transfer, and fluid dynamics of this alternative nuclear fuel element geometry. Fabrication experiments of grooved rings from carbide refractory metals are also presented along with material characterization and interactions with a hot hydrogen environment. Results of experiments and associated analysis are discussed. The authors demonstrated success in reaching desired densities with some success in material distribution and reaching a solid solution. Future work is needed to improve distribution of material, minimize oxidation during the milling process, and define a fabrication process that will serve for constructing grooved ring fuel rods for large system tests.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Nichols, T.

The Nuclear Forensics Analysis Center (NFAC) is part of Savannah River National Laboratory (SRNL) and is one of only two USG National Laboratories accredited to perform nuclear forensic analyses to the requirements of ISO 17025. SRNL NFAC is capable of analyzing nuclear and radiological samples from bulk material to ultra-trace samples. NFAC provides analytical support to the FBI's Radiological Evidence Examination Facility (REEF), which is located within SRNL. REEF gives the FBI the capability to perform traditional forensics on material that is radiological and/or is contaminated. SRNL is engaged in research and development efforts to improve the USG technical nuclearmore » forensics capabilities. Research includes improving predictive signatures and developing a database containing comparative samples.« less

Developing a Nuclear Grade of Alloy 617 for Gen IV Nuclear Energy Systems

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ren, Weiju; Swindeman, Robert W; Santella, Michael L

2010-01-01

Alloy 617, an attractive material not particularly developed for nuclear use, is now being considered as a leading candidate alloy by several countries for applications in the Gen IV Nuclear Energy Systems. An extensive review of its existing data suggests that it would be beneficial to refine the alloy s specification to a nuclear grade for the intended Gen IV systems. In this paper, rationale for developing a nuclear grade of the alloy is first discussed through an analysis on existing data from various countries. Then initial experiments for refining the alloy specification are described. Preliminary results have suggested themore » feasibility of the refinement approach, as well as the possibility for achieving a desirable nuclear grade. Based on the results, further research activities are recommended.« less

NASA/DOE/DOD nuclear propulsion technology planning: Summary of FY 1991 interagency panel results

NASA Technical Reports Server (NTRS)

Clark, John S.; Wickenheiser, Timothy J.; Doherty, Michael P.; Marshall, Albert; Bhattacharryya, Samit K.; Warren, John

1992-01-01

Interagency (NASA/DOE/DOD) technical panels worked in 1991 to evaluate critical nuclear propulsion issues, compare nuclear propulsion concepts for a manned Mars mission on a consistent basis, and to continue planning a technology development project for the Space Exploration Initiative (SEI). Panels were formed to address mission analysis, nuclear facilities, safety policy, nuclear fuels and materials, nuclear electric propulsion technology, and nuclear thermal propulsion technology. A summary of the results and recommendations of the panels is presented.

Thermally and chemically responsive nanoporous materials for efficient capture of fission product gases.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Stroeve, Pieter; Faller, Roland

The objective of this project was to develop robust, high-efficiency materials for capture of fission product gases such as He, Xe and Kr in scenarios relevant for both reactor fuels and reprocessing operations. The relevant environments are extremely harsh, encompassing temperatures up to 1500 °C, high levels of radiation, as well as potential exposures to highly-reactive chemicals such as nitric acid and organic solvents such as kerosene. The requirement for nanostructured capture materials is driven in part by the very short (few micron) diffusion distances for product gases in nuclear fuel. We achieved synthesis, characterization and detailed modeling of themore » materials. Although not all materials reviewed in this report will be feasible for the ultimate goal of integration in nuclear fuel, nevertheless each material studied has particular properties which will enable an optimized material to be efficiently developed and characterized.« less

Nuclear physics for materials technology

NASA Astrophysics Data System (ADS)

Conlon, T. W.

1987-04-01

Although particle accelerators have traditionally been used to further our knowledge of nuclear physics, the last decade or so has seen a rapid growth of their involvement in materials technology — both to modify materials and to provide analytical information at the atomic level that cannot be obtained in other ways. The deployment of ion beams in these areas has occurred in three phases: first the exploitation of keV ion beams (in ion implantation and SIMS) then MeV light ion beams (using RBS, NRA, PIXE analysis and TLA) and currently MeV heavy ion beams, together with the associated fast recoil atoms and nuclei that they produce in interactions with materials. This trend has been accompanied by the gradual assimilation of methods such as energy analysis, microbeam focussing, particle identification, time of flight and coincidence techniques, etc., which were first developed for experimental nuclear physics use. Current examples of developments in the MeV range relevant to phases 2 and 3 are given.

Tungsten - Yttrium Based Nuclear Structural Materials

NASA Astrophysics Data System (ADS)

Ramana, Chintalapalle; Chessa, Jack; Martinenz, Gustavo

2013-04-01

The challenging problem currently facing the nuclear science community in this 21st century is design and development of novel structural materials, which will have an impact on the next-generation nuclear reactors. The materials available at present include reduced activation ferritic/martensitic steels, dispersion strengthened reduced activation ferritic steels, and vanadium- or tungsten-based alloys. These materials exhibit one or more specific problems, which are either intrinsic or caused by reactors. This work is focussed towards tungsten-yttrium (W-Y) based alloys and oxide ceramics, which can be utilized in nuclear applications. The goal is to derive a fundamental scientific understanding of W-Y-based materials. In collaboration with University of Califonia -- Davis, the project is designated to demonstrate the W-Y based alloys, ceramics and composites with enhanced physical, mechanical, thermo-chemical properties and higher radiation resistance. Efforts are focussed on understanding the microstructure, manipulating materials behavior under charged-particle and neutron irradiation, and create a knowledge database of defects, elemental diffusion/segregation, and defect trapping along grain boundaries and interfaces. Preliminary results will be discussed.

Materials technology for an advanced space power nuclear reactor concept: Program summary

NASA Technical Reports Server (NTRS)

Gluyas, R. E.; Watson, G. K.

1975-01-01

The results of a materials technology program for a long-life (50,000 hr), high-temperature (950 C coolant outlet), lithium-cooled, nuclear space power reactor concept are reviewed and discussed. Fabrication methods and compatibility and property data were developed for candidate materials for fuel pins and, to a lesser extent, for potential control systems, reflectors, reactor vessel and piping, and other reactor structural materials. The effects of selected materials variables on fuel pin irradiation performance were determined. The most promising materials for fuel pins were found to be 85 percent dense uranium mononitride (UN) fuel clad with tungsten-lined T-111 (Ta-8W-2Hf).

Nondestructive evaluation of nuclear-grade graphite

NASA Astrophysics Data System (ADS)

Kunerth, D. C.; McJunkin, T. R.

2012-05-01

The material of choice for the core of the high-temperature gas-cooled reactors being developed by the U.S. Department of Energy's Next Generation Nuclear Plant Program is graphite. Graphite is a composite material whose properties are highly dependent on the base material and manufacturing methods. In addition to the material variations intrinsic to the manufacturing process, graphite will also undergo changes in material properties resulting from radiation damage and possible oxidation within the reactor. Idaho National Laboratory is presently evaluating the viability of conventional nondestructive evaluation techniques to characterize the material variations inherent to manufacturing and in-service degradation. Approaches of interest include x-ray radiography, eddy currents, and ultrasonics.

Physics in the Confrontation of Nuclear Weapons

NASA Astrophysics Data System (ADS)

Toevs, James

2011-03-01

Had the detonations on 9/11 involved nuclear explosives rather than jet fuel the number of deaths and the costs would have been multiplied by 100 or 1,000. This talk will briefly describe the nuclear threat and then focus on the technologies, both extant and evolving, for the detection and interdiction of clandestine trafficking of nuclear weapons and nuclear and radiological material. The methods vary from passive detection of heat, gamma radiation, neutrons, or other signatures from nuclear material, through radiological approaches to examine contents of vehicles and cargo containers, to active interrogation concepts that are under development. All of these methods have major physics components ranging from simple gamma ray detection as learned in a senior undergraduate lab to the latest ideas in muon production and acceleration.

Nanostructured Bulk Thermoelectric Generator for Efficient Power Harvesting for Self-powered Sensor Networks

DOE Office of Scientific and Technical Information (OSTI.GOV)

Zhang, Yanliang; Butt, Darryl; Agarwal, Vivek

2015-07-01

The objective of this Nuclear Energy Enabling Technology research project is to develop high-efficiency and reliable thermoelectric generators for self-powered wireless sensors nodes utilizing thermal energy from nuclear plant or fuel cycle. The power harvesting technology has crosscutting significance to address critical technology gaps in monitoring nuclear plants and fuel cycle. The outcomes of the project will lead to significant advancement in sensors and instrumentation technology, reducing cost, improving monitoring reliability and therefore enhancing safety. The self-powered wireless sensor networks could support the long-term safe and economical operation of all the reactor designs and fuel cycle concepts, as well asmore » spent fuel storage and many other nuclear science and engineering applications. The research is based on recent breakthroughs in high-performance nanostructured bulk (nanobulk) thermoelectric materials that enable high-efficiency direct heat-to-electricity conversion over a wide temperature range. The nanobulk thermoelectric materials that the research team at Boise State University and University of Houston has developed yield up to a 50% increase in the thermoelectric figure of merit, ZT, compared with state-of-the-art bulk counterparts. This report focuses on the selection of optimal thermoelectric materials for this project. The team has performed extensive study on two thermoelectric materials systems, i.e. the half-Heusler materials, and the Bismuth-Telluride materials. The report contains our recent research results on the fabrication, characterization and thermoelectric property measurements of these two materials.« less

Arc-Heater Facility for Hot Hydrogen Exposure of Nuclear Thermal Rocket Materials

NASA Technical Reports Server (NTRS)

Litchford, Ron J.; Foote, John P.; Wang,Ten-See; Hickman, Robert; Panda, Binayak; Dobson, Chris; Osborne, Robin; Clifton, Scooter

2006-01-01

A hyper-thermal environment simulator is described for hot hydrogen exposure of nuclear thermal rocket material specimens and component development. This newly established testing capability uses a high-power, multi-gas, segmented arc-heater to produce high-temperature pressurized hydrogen flows representative of practical reactor core environments and is intended to serve. as a low cost test facility for the purpose of investigating and characterizing candidate fueUstructura1 materials and improving associated processing/fabrication techniques. Design and development efforts are thoroughly summarized, including thermal hydraulics analysis and simulation results, and facility operating characteristics are reported, as determined from a series of baseline performance mapping tests.

Nuclear Weapons Effects (Self-Teaching Materials).

ERIC Educational Resources Information Center

Defense Civil Preparedness Agency (DOD), Battle Creek, MI.

Developed by the Civil Defense Preparedness Agency, this autoinstructional text deals with nuclear weapons effects. The destructive effects of an atomic blast are first introduced, and then long-term radioactive consequences are stressed. (CP)

Economic Analysis of National Nuclear Security Administration (NNSA) Modernization Alternatives

DTIC Science & Technology

2007-11-01

without nuclear testing; works to reduce global danger from weapons of mass destruction; provides the U.S. Navy with safe and effective nuclear...SFE) covers the acquisition of glove boxes, long-lead facility, and actinide chemistry/materials characterization (AC/MC) equipment whose uniqueness...Hazard Category II AC/MC and actinide Research and Development operations, special nuclear 5 Babcock

Development of a Dual-Particle Imaging System for Nonproliferation Applications

NASA Astrophysics Data System (ADS)

Poitrasson-Riviere, Alexis Pierre Valere

A rising concern in our society is preventing the proliferation of nuclear weapons and fissionable material. This prevention can be incorporated at multiple levels, from the use of nuclear safeguards in nuclear facilities to the detection of threat objects in the field. At any level, systems used for such tasks need to be specially designed for use with Special Nuclear Material (SNM) which is defined by the NRC as plutonium and uranium enriched in U-233 or U-235 isotopes. These radioactive materials have the particularity of emitting both fast neutrons and gamma rays; thus, systems able to detect both particles simultaneously are particularly desirable. In the field of nuclear nonproliferation and safeguards, detection systems capable of accurately imaging various sources of radiation can greatly simplify any monitoring or detection task. The localization of the radiation sources can allow users of the system to focus their efforts on the areas of interest, whether it be for radiation detection or radiation characterization. This thesis describes the development of a dual-particle imaging system at the University of Michigan to address these technical challenges. The imaging system relies on the use of organic liquid scintillators that can detect both fast neutrons and gamma rays, and inorganic NaI(Tl) scintillators that are not very sensitive to neutrons yet yield photoelectric absorptions from gamma rays. A prototype of the imaging system has been constructed and operated. The system will aid the remote monitoring of nuclear materials within facilities, and it has the scalability for standoff detection in the field. A software suite has been developed to analyze measured data in real time, in an effort to obtain a system as close to field-ready as possible. The system's performance has been tested with various materials of interest, such as MOX and plutonium metal, measured at the PERLA facility of the Joint Research Center in Ispra, Italy. The robust and versatile imaging system is an attractive alternative to the current imaging systems.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Tan, Lizhen; Yang, Ying; Tyburska-Puschel, Beata

The mission of the Nuclear Energy Enabling Technologies (NEET) program is to develop crosscutting technologies for nuclear energy applications. Advanced structural materials with superior performance at elevated temperatures are always desired for nuclear reactors, which can improve reactor economics, safety margins, and design flexibility. They benefit not only new reactors, including advanced light water reactors (LWRs) and fast reactors such as sodium-cooled fast reactor (SFR) that is primarily designed for management of high-level wastes, but also life extension of the existing fleet when component exchange is needed. Developing and utilizing the modern materials science tools (experimental, theoretical, and computational tools)more » is an important path to more efficient alloy development and process optimization. Ferritic-martensitic (FM) steels are important structural materials for nuclear reactors due to their advantages over other applicable materials like austenitic stainless steels, notably their resistance to void swelling, low thermal expansion coefficients, and higher thermal conductivity. However, traditional FM steels exhibit a noticeable yield strength reduction at elevated temperatures above ~500°C, which limits their applications in advanced nuclear reactors which target operating temperatures at 650°C or higher. Although oxide-dispersion-strengthened (ODS) ferritic steels have shown excellent high-temperature performance, their extremely high cost, limited size and fabricability of products, as well as the great difficulty with welding and joining, have limited or precluded their commercial applications. Zirconium has shown many benefits to Fe-base alloys such as grain refinement, improved phase stability, and reduced radiation-induced segregation. The ultimate goal of this project is, with the aid of computational modeling tools, to accelerate the development of a new generation of Zr-bearing ferritic alloys to be fabricated using conventional steelmaking practices, which have excellent radiation resistance and enhanced high-temperature creep performance greater than Grade 91.« less

Nuclear energy.

PubMed

Grandin, Karl; Jagers, Peter; Kullander, Sven

2010-01-01

Nuclear energy can play a role in carbon free production of electrical energy, thus making it interesting for tomorrow's energy mix. However, several issues have to be addressed. In fission technology, the design of so-called fourth generation reactors show great promise, in particular in addressing materials efficiency and safety issues. If successfully developed, such reactors may have an important and sustainable part in future energy production. Working fusion reactors may be even more materials efficient and environmental friendly, but also need more development and research. The roadmap for development of fourth generation fission and fusion reactors, therefore, asks for attention and research in these fields must be strengthened.

GAIN Technology Workshops Summary Report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Braase, Lori Ann

National and global demand for nuclear energy is increasing and United States (U.S.) global leadership is eroding. There is a sense of urgency with respect to the deployment of the innovative nuclear energy technologies. The Gateway for Accelerated Innovation in Nuclear (GAIN) initiative is based on the simultaneous achievement of three strategic goals. The first is maintaining global technology leadership within the U.S. Department of Energy (DOE). The second is enabling global industrial leadership for nuclear vendors and suppliers. The third is focused on utility optimization of nuclear energy within the clean energy portfolio. An effective public-private partnership is requiredmore » to achieve these goals. DOEs recognizes the recent sense of urgency new developers and investors have in getting their concepts to market. They know that time to market for nuclear technology takes too long and the facilities needed to conduct the necessary research, development and demonstration (RD&D) activities are very expensive to develop and maintain. Early technologies, in the lower technology readiness levels (TRL) need materials testing, analysis, modeling, code development, etc., most of which currently exists in the DOE national laboratory system. However, mature technologies typically need large component testing and demonstration facilities, which are expensive and long-lead efforts. By understanding the needs of advanced nuclear technology developers, GAIN will connect DOE national laboratory capabilities (e.g., facilities, expertise, materials, and data) with industry RD&D needs. In addition, GAIN is working with the Nuclear Regulatory Commission (NRC) to streamline processes and increase understanding of the licensing requirements for advanced reactors.« less

JHR Project: a future Material Testing Reactor working as an International user Facility: The key-role of instrumentation in support to the development of modern experimental capacity

DOE Office of Scientific and Technical Information (OSTI.GOV)

Bignan, G.; Gonnier, C.; Lyoussi, A.

2015-07-01

Research and development on fuel and material behaviour under irradiation is a key issue for sustainable nuclear energy in order to meet specific needs by keeping the best level of safety. These needs mainly deal with a constant improvement of performances and safety in order to optimize the fuel cycle and hence to reach nuclear energy sustainable objectives. A sustainable nuclear energy requires a high level of performances in order to meet specific needs such as: - Pursuing improvement of the performances and safety of present and coming water cooled reactor technologies. This will require a continuous R and Dmore » support following a long-term trend driven by the plant life management, safety demonstration, flexibility and economics improvement. Experimental irradiations of structure materials are necessary to anticipate these material behaviours and will contribute to their optimisation. - Upgrading continuously nuclear fuel technology in present and future nuclear power plants to achieve better performances and to optimise the fuel cycle keeping the best level of safety. Fuel evolution for generation II, III and III+ is a key stake requiring developments, qualification tests and safety experiments to ensure the competitiveness and safety: experimental tests exploring the full range of fuel behaviour determine fuel stability limits and safety margins, as a major input for the fuel reliability analysis. To perform such accurate and innovative progress and developments, specific and ad hoc instrumentation, irradiation devices, measurement methods are necessary to be set up inside or beside the material testing reactor (MTR) core. These experiments require beforehand in situ and on line sophisticated measurements to accurately determine different key parameters such as thermal and fast neutron fluxes and nuclear heating in order to precisely monitor and control the conducted assays. The new Material Testing Reactor JHR (Jules Horowitz Reactor) currently under construction at CEA Cadarache research centre in the south of France will represent a major Research Infrastructure for scientific studies regarding material and fuel behavior under irradiation. It will also be devoted to medical isotopes production. Hence JHR will offer a real opportunity to perform R and D programs regarding needs above and hence will crucially contribute to the selection, optimization and qualification of these innovative materials and fuels. The JHR reactor objectives, principles and main characteristics associated to specific experimental devices associated to measurement techniques and methodology, their performances, their limitations and field of applications will be presented and discussed. (authors)« less

Predicting the remaining service life of concrete

DOE Office of Scientific and Technical Information (OSTI.GOV)

Clifton, J.F.

1991-11-01

Nuclear power plants are providing, currently, about 17 percent of the U.S. electricity and many of these plants are approaching their licensed life of 40 years. The U.S. Nuclear Regulatory Commission and the Department of Energy`s Oak Ridge National Laboratory are carrying out a program to develop a methodology for assessing the remaining safe-life of the concrete components and structures in nuclear power plants. This program has the overall objective of identifying potential structural safety issues, as well as acceptance criteria, for use in evaluations of nuclear power plants for continued service. The National Institute of Standards and Technology (NIST)more » is contributing to this program by identifying and analyzing methods for predicting the remaining life of in-service concrete materials. This report examines the basis for predicting the remaining service lives of concrete materials of nuclear power facilities. Methods for predicting the service life of new and in-service concrete materials are analyzed. These methods include (1) estimates based on experience, (2) comparison of performance, (3) accelerated testing, (4) stochastic methods, and (5) mathematical modeling. New approaches for predicting the remaining service lives of concrete materials are proposed and recommendations for their further development given. Degradation processes are discussed based on considerations of their mechanisms, likelihood of occurrence, manifestations, and detection. They include corrosion, sulfate attack, alkali-aggregate reactions, frost attack, leaching, radiation, salt crystallization, and microbiological attack.« less

Analysis of Material Sample Heated by Impinging Hot Hydrogen Jet in a Non-Nuclear Tester

NASA Technical Reports Server (NTRS)

Wang, Ten-See; Foote, John; Litchford, Ron

2006-01-01

A computational conjugate heat transfer methodology was developed and anchored with data obtained from a hot-hydrogen jet heated, non-nuclear materials tester, as a first step towards developing an efficient and accurate multiphysics, thermo-fluid computational methodology to predict environments for hypothetical solid-core, nuclear thermal engine thrust chamber. The computational methodology is based on a multidimensional, finite-volume, turbulent, chemically reacting, thermally radiating, unstructured-grid, and pressure-based formulation. The multiphysics invoked in this study include hydrogen dissociation kinetics and thermodynamics, turbulent flow, convective and thermal radiative, and conjugate heat transfers. Predicted hot hydrogen jet and material surface temperatures were compared with those of measurement. Predicted solid temperatures were compared with those obtained with a standard heat transfer code. The interrogation of physics revealed that reactions of hydrogen dissociation and recombination are highly correlated with local temperature and are necessary for accurate prediction of the hot-hydrogen jet temperature.

New Brunswick Laboratory: Progress report, October 1993 through September 1994

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

The mission of the New Brunswick Laboratory of the US Department of Energy (DOE) is to serve as the National Certifying Authority for nuclear reference materials and to provide an independent Federal technical staff and laboratory resource performing nuclear material measurement, safeguards and non-proliferation functions in support of multiple program sponsors. During FY 94 New Brunswick Laboratory (NBL) completed development of a Strategic Plan which will aid in better defining performance oriented laboratory goals and objectives in each functional area consistent with the changing needs of the global nuclear community. This annual report describes accomplishments achieved in carrying out NBL`smore » assigned missions. Details of completed projects are reported in separate topical reports or as open-literature publications. Programs discussed here are: (1) safeguards assistance; (2) reference materials program; (3) measurement evaluation; (4) measurement services; and (5) measurement development.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Tsai, H. C.; Chen, K.; Liu, Y. Y.

The US Department of Energy (DOE) [Environmental Management (EM), Office of Packaging and Transportation (EM-45)] Packaging Certification Program (PCP) has developed a radiofrequency identification (RFID) tracking and monitoring system for the management of nuclear materials packages during storage and transportation. The system, developed by the PCP team at Argonne National Laboratory, involves hardware modification, application software development, secured database and web server development, and irradiation experiments. In April 2008, Argonne tested key features of the RFID tracking and monitoring system in a weeklong, 1700 mile (2736 km) demonstration employing 14 empty type B fissile material drums of three designs (modelsmore » 9975, 9977 and ES-3100) that have been certified for shipment by the DOE and the US Nuclear Regulatory Commission. The demonstration successfully integrated global positioning system (GPS) technology for vehicle tracking, satellite/cellular (general packet radio service, or GPRS) technologies for wireless communication, and active RFID tags with multiple sensors (seal integrity, shock, temperature, humidity and battery status) on drums. In addition, the demonstration integrated geographic information system (GIS) technology with automatic alarm notifications of incidents and generated buffer zone reports for emergency response and management of staged incidents. The demonstration was sponsored by EM and the US National Nuclear Security Administration, with the participation of Argonne, Savannah River and Oak Ridge National Laboratories. Over 50 authorised stakeholders across the country observed the demonstration via secured Internet access. The DOE PCP and national laboratories are working on several RFID system implementation projects at selected DOE sites, as well as continuing device and systems development and widening applications beyond DOE sites and possibly beyond nuclear materials to include other radioactive materials.« less

1976 annual summary report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1978-03-01

Abstracts of papers published during the previous calendar year, arranged in accordance with the project titles used in the USDOE Schedule 189 Budget Proposals, are presented. The collection of abstracts supplements the listing of papers published in the Schedule 189. The following subject areas are represented: high-energy physics; nuclear physics; basic energy sciences (nuclear science, materials sciences, solid state physics, materials chemistry); molecular, mathematical, and earth sciences (fundamental interactions, processes and techniques, mathematical and computer sciences); environmental research and development; physical and technological studies (characterization, measurement and monitoring); and nuclear research and applications.

Nuclear Forensic Inferences Using Iterative Multidimensional Statistics

DOE Office of Scientific and Technical Information (OSTI.GOV)

Robel, M; Kristo, M J; Heller, M A

2009-06-09

Nuclear forensics involves the analysis of interdicted nuclear material for specific material characteristics (referred to as 'signatures') that imply specific geographical locations, production processes, culprit intentions, etc. Predictive signatures rely on expert knowledge of physics, chemistry, and engineering to develop inferences from these material characteristics. Comparative signatures, on the other hand, rely on comparison of the material characteristics of the interdicted sample (the 'questioned sample' in FBI parlance) with those of a set of known samples. In the ideal case, the set of known samples would be a comprehensive nuclear forensics database, a database which does not currently exist. Inmore » fact, our ability to analyze interdicted samples and produce an extensive list of precise materials characteristics far exceeds our ability to interpret the results. Therefore, as we seek to develop the extensive databases necessary for nuclear forensics, we must also develop the methods necessary to produce the necessary inferences from comparison of our analytical results with these large, multidimensional sets of data. In the work reported here, we used a large, multidimensional dataset of results from quality control analyses of uranium ore concentrate (UOC, sometimes called 'yellowcake'). We have found that traditional multidimensional techniques, such as principal components analysis (PCA), are especially useful for understanding such datasets and drawing relevant conclusions. In particular, we have developed an iterative partial least squares-discriminant analysis (PLS-DA) procedure that has proven especially adept at identifying the production location of unknown UOC samples. By removing classes which fell far outside the initial decision boundary, and then rebuilding the PLS-DA model, we have consistently produced better and more definitive attributions than with a single pass classification approach. Performance of the iterative PLS-DA method compared favorably to that of classification and regression tree (CART) and k nearest neighbor (KNN) algorithms, with the best combination of accuracy and robustness, as tested by classifying samples measured independently in our laboratories against the vendor QC based reference set.« less

Affordable Development and Optimization of CERMET Fuels for NTP Ground Testing

NASA Technical Reports Server (NTRS)

Hickman, Robert R.; Broadway, Jeramie W.; Mireles, Omar R.

2014-01-01

CERMET fuel materials for Nuclear Thermal Propulsion (NTP) are currently being developed at NASA's Marshall Space Flight Center. The work is part of NASA's Advanced Space Exploration Systems Nuclear Cryogenic Propulsion Stage (NCPS) Project. The goal of the FY12-14 project is to address critical NTP technology challenges and programmatic issues to establish confidence in the affordability and viability of an NTP system. A key enabling technology for an NCPS system is the fabrication of a stable high temperature nuclear fuel form. Although much of the technology was demonstrated during previous programs, there are currently no qualified fuel materials or processes. The work at MSFC is focused on developing critical materials and process technologies for manufacturing robust, full-scale CERMET fuels. Prototypical samples are being fabricated and tested in flowing hot hydrogen to understand processing and performance relationships. As part of this initial demonstration task, a final full scale element test will be performed to validate robust designs. The next phase of the project will focus on continued development and optimization of the fuel materials to enable future ground testing. The purpose of this paper is to provide a detailed overview of the CERMET fuel materials development plan. The overall CERMET fuel development path is shown in Figure 2. The activities begin prior to ATP for a ground reactor or engine system test and include materials and process optimization, hot hydrogen screening, material property testing, and irradiation testing. The goal of the development is to increase the maturity of the fuel form and reduce risk. One of the main accomplishmens of the current AES FY12-14 project was to develop dedicated laboratories at MSFC for the fabrication and testing of full length fuel elements. This capability will enable affordable, near term development and optimization of the CERMET fuels for future ground testing. Figure 2 provides a timeline of the development and optimization tasks for the AES FY15-17 follow on program.

Porous Chromatographic Materials as Substrates for Preparing Synthetic Nuclear Explosion Debris Particles

DOE Office of Scientific and Technical Information (OSTI.GOV)

Harvey, Scott D.; Liezers, Martin; Antolick, Kathryn C.

2013-06-13

In this study, we investigated several porous chromatographic materials as synthetic substrates for preparing surrogate nuclear explosion debris particles. The resulting synthetic debris materials are of interest for use in developing analytical methods. Eighteen metals, including some of forensic interest, were loaded onto materials by immersing them in metal solutions (556 mg/L of each metal) to fill the pores, applying gentle heat (110°C) to drive off water, and then treating them at high temperatures (up to 800°C) in air to form less soluble metal species. High-boiling-point metals were uniformly loaded on spherical controlled-pore glass to emulate early fallout, whereas low-boiling-pointmore » metals were loaded on core-shell silica to represent coated particles formed later in the nuclear fallout-formation process. Analytical studies were applied to characterize solubility, material balance, and formation of recalcitrant species. Dissolution experiments indicated loading was 1.5 to 3 times higher than expected from the pore volume alone, a result attributed to surface coating. Analysis of load solutions before and after filling the material pores revealed that most metals were passively loaded; that is, solutions filled the pores without active metal discrimination. However, niobium and tin concentrations were lower in solutions after pore filling, and were found in elevated concentrations in the final products, indicating some metals were selectively loaded. High-temperature treatments caused reduced solubility of several metal species, and loss of some metals (rhenium and tellurium) because volatile species were formed. Sample preparation reproducibility was high (the inter-batch relative standard deviation was 7.8%, and the intra-batch relative standard deviation was 0.84%) indicating that this material is suitable for use as a working standard for analytical methods development. We anticipate future standardized radionuclide-loaded materials will find use in radioanalytical methods development and/or serve as a starting material for the synthesis of more complex forms of nuclear explosion debris (e.g., Trinitite).« less

Production of Synthetic Nuclear Melt Glass

PubMed Central

Molgaard, Joshua J.; Auxier, John D.; Giminaro, Andrew V.; Oldham, Colton J.; Gill, Jonathan; Hall, Howard L.

2016-01-01

Realistic surrogate nuclear debris is needed within the nuclear forensics community to test and validate post-detonation analysis techniques. Here we outline a novel process for producing bulk surface debris using a high temperature furnace. The material developed in this study is physically and chemically similar to trinitite (the melt glass produced by the first nuclear test). This synthetic nuclear melt glass is assumed to be similar to the vitrified material produced near the epicenter (ground zero) of any surface nuclear detonation in a desert environment. The process outlined here can be applied to produce other types of nuclear melt glass including that likely to be formed in an urban environment. This can be accomplished by simply modifying the precursor matrix to which this production process is applied. The melt glass produced in this study has been analyzed and compared to trinitite, revealing a comparable crystalline morphology, physical structure, void fraction, and chemical composition. PMID:26779720

Leo Szilard Lectureship Award Talk: Nuclear disarmament after the cold war

NASA Astrophysics Data System (ADS)

Podvig, Pavel

2008-04-01

Now that the cold war is long over, our thinking of nuclear weapons and the role that they play in international security has undergone serious changes. The emphasis has shifted from superpower confrontation to nuclear proliferation, spread of weapon materials, and to the dangers of countries developing nuclear weapon capability under a cover of a civilian program. At the same time, the old cold-war dangers, while receded, have not disappeared completely. The United States and Russia keep maintaining thousands of nuclear weapons in their arsenals, some of them in very high degree of readiness. This situation presents a serious challenge that the international community has to deal with. Although Russia and the United States are taking some steps to reduce their nuclear arsenals, the traditional arms control process has stalled -- the last treaty that was signed in 2002 does not place serious limits on strategic forces of either side. The START Treaty, which provides a framework for verification and transparency in reduction of nuclear arsenals, will expire at the end of 2009. Little effort has been undertaken to extend the treaty or renegotiate it. Moreover, in recent years Russia has stepped up the efforts to modernize its strategic nuclear forces. The United States has resisted joining the Comprehensive Nuclear Test Ban Treaty and has been working on controversial new nuclear weapon development programs. The U.S. missile defense program makes the dialogue between Russia and the United States even more difficult. The reluctance of Russia and the United States to engage in a discussion about drastic reductions of their nuclear forces undermines the case of nuclear nonproliferation and seriously complicated their effort to contain the spread of nuclear weapon technologies and expertise. One of the reasons for the current lack of progress in nuclear disarmament is the contradiction between the diminished role that nuclear weapons play in security of nuclear weapon states and the inertia of cold-war institutions that are involved in their development and support. Dealing with this contradiction would require development of new mechanisms of cooperation between nuclear weapons states and their strong commitment to the cause of nuclear nonproliferation. One important area of cooperation is development of a framework that would prevent the spread of nuclear materials and technology at the time when increasing number of countries is turning toward expanded use of nuclear power to cover their energy needs.

Comprehensive Glossary of Nuclear Science

NASA Astrophysics Data System (ADS)

Langlands, Tracy; Stone, Craig; Meyer, Richard

2001-10-01

We have developed a comprehensive glossary of terms covering the broad fields of nuclear and related areas of science. The glossary has been constructed with two sections. A primary section consists of over 6,000 terms covering the fields of nuclear and high energy physics, nuclear chemistry, radiochemistry, health physics, astrophysics, materials science, analytical science, environmental science, nuclear medicine, nuclear engineering, nuclear instrumentation, nuclear weapons, and nuclear safeguards. Approximately 1,500 terms of specific focus on military and nuclear weapons testing define the second section. The glossary is currently larger than many published glossaries and dictionaries covering the entire field of physics. Glossary terms have been defined using an extensive collection of current and historical publications. Historical texts extend back into the 1800's, the early days of atomic physics. The glossary has been developed both as a software application and as a hard copy document.

78 FR 38739 - Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants

Federal Register 2010, 2011, 2012, 2013, 2014

2013-06-27

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0109] Special Nuclear Material Control and Accounting... Guide (RG) 5.29, ``Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants... material control and accounting. This guide applies to all nuclear power plants. ADDRESSES: Please refer to...

DOE Office of Scientific and Technical Information (OSTI.GOV)

Rhodie, K B; Mailhiot, C; Eaglesham, D

Lawrence Livermore National Laboratory's mission is as clear today as it was in 1952 when the Laboratory was founded--to ensure our country's national security and the safety and reliability of its nuclear deterrent. As a laboratory pursuing applied science in the national interest, we strive to accomplish our mission through excellence in science and technology. We do this while developing and implementing sound and robust business practices in an environment that emphasizes security and ensures our safety and the safety of the community around us. Our mission as a directorate derives directly from the Laboratory's charter. When I accepted themore » assignment of Associate Director for Chemistry and Materials Science (CMS), I talked to you about the need for strategic balance and excellence in all our endeavors. We also discussed how to take the directorate to the next level. The long-range CMS strategic plan presented here was developed with this purpose in mind. It also aligns with the Lab's institutional long-range science and technology plan and its 10-year facilities and infrastructure site plan. The plan is aimed at ensuring that we fulfill our directorate's two governing principles: (1) delivering on our commitments to Laboratory programs and sponsors, and (2) anticipating change and capitalizing on opportunities through innovation in science and technology. This will require us to attain a new level of creativity, agility, and flexibility as we move forward. Moreover, a new level of engagement in partnerships with other directorates across the Laboratory as well as with universities and other national labs will also be required. The group of managers and staff that I chartered to build a strategic plan identified four organizing themes that define our directorate's work and unite our staff with a set of common goals. The plan presented here explains how we will proceed in each of these four theme areas: (1) Materials properties and performance under extreme conditions--Fundamental investigations of the properties and performance of states of matter under extreme dynamic, environmental, and nanoscale conditions, with an emphasis on materials of interest to Laboratory programs and mission needs. (2) Chemistry under extreme conditions and chemical engineering to support national security programs--Insights into the chemical reactions of energetic materials in the nuclear stockpile through models of molecular response to extreme conditions of temperature and pressure, advancing a new technique for processing energetic materials by using sol-gel chemistry, providing materials for NIF optics, and furthering developments to enhance other high-power lasers. (3) Science supporting national objectives at the intersection of chemistry, materials science, and biology--Multidisciplinary research for developing new technologies to combat chemical and biological terrorism, to monitor changes in the nation's nuclear stockpile, and to enable the development and application of new physical-science-based methodologies and tools for fundamental biology studies and human health applications. (4) Applied nuclear science for human health and national security: Nuclear science research that is used to develop new methods and technologies for detecting and attributing nuclear materials, assisting Laboratory programs that require nuclear and radiochemical expertise in carrying out their missions, discovering new elements in the periodic table, and finding ways of detecting and understanding cellular response to radiation.« less

Nuclear Fragmentation Processes Relevant for Human Space Radiation Protection

NASA Technical Reports Server (NTRS)

Lin, Zi-Wei

2007-01-01

Space radiation from cosmic ray particles is one of the main challenges for human space explorations such-as a moon base or a trip to Mars. Models have been developed in order to predict the radiation exposure to astronauts and to evaluate the effectiveness of different shielding materials, and a key ingredient in these models is the physics of nuclear fragmentations. We have developed a semi-analytical method to determine which partial cross sections of nuclear fragmentations most affect the radiation dose behind shielding materials due to exposure to galactic cosmic rays. The cross sections thus determined will require more theoretical and/or experimental studies in order for us to better predict, reduce and mitigate the radiation exposure in human space explorations.

Application of the Monte Carlo method to estimate doses due to neutron activation of different materials in a nuclear reactor

NASA Astrophysics Data System (ADS)

Ródenas, José

2017-11-01

All materials exposed to some neutron flux can be activated independently of the kind of the neutron source. In this study, a nuclear reactor has been considered as neutron source. In particular, the activation of control rods in a BWR is studied to obtain the doses produced around the storage pool for irradiated fuel of the plant when control rods are withdrawn from the reactor and installed into this pool. It is very important to calculate these doses because they can affect to plant workers in the area. The MCNP code based on the Monte Carlo method has been applied to simulate activation reactions produced in the control rods inserted into the reactor. Obtained activities are introduced as input into another MC model to estimate doses produced by them. The comparison of simulation results with experimental measurements allows the validation of developed models. The developed MC models have been also applied to simulate the activation of other materials, such as components of a stainless steel sample introduced into a training reactors. These models, once validated, can be applied to other situations and materials where a neutron flux can be found, not only nuclear reactors. For instance, activation analysis with an Am-Be source, neutrography techniques in both medical applications and non-destructive analysis of materials, civil engineering applications using a Troxler, analysis of materials in decommissioning of nuclear power plants, etc.

International training course on nuclear materials accountability for safeguards purposes

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1980-12-01

The two volumes of this report incorporate all lectures and presentations at the International Training Course on Nuclear Materials Accountability and Control for Safeguards Purposes, held May 27-June 6, 1980, at the Bishop's Lodge near Santa Fe, New Mexico. The course, authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, was developed to provide practical training in the design, implementation, and operation of a National system of nuclear materials accountability and control that satisfies both National and IAEA International safeguards objectives. Volume I, covering the firstmore » week of the course, presents the background, requirements, and general features of material accounting and control in modern safeguard systems. Volume II, covering the second week of the course, provides more detailed information on measurement methods and instruments, practical experience at power reactor and research reactor facilities, and examples of operating state systems of accountability and control.« less

Nuclear Thermal Propulsion (NTP) Development Activities at the NASA Marshall Space Flight Center - 2006 Accomplishments

NASA Technical Reports Server (NTRS)

Ballard, Richard O.

2007-01-01

In 2005-06, the Prometheus program funded a number of tasks at the NASA-Marshall Space Flight Center (MSFC) to support development of a Nuclear Thermal Propulsion (NTP) system for future manned exploration missions. These tasks include the following: 1. NTP Design Develop Test & Evaluate (DDT&E) Planning 2. NTP Mission & Systems Analysis / Stage Concepts & Engine Requirements 3. NTP Engine System Trade Space Analysis and Studies 4. NTP Engine Ground Test Facility Assessment 5. Non-Nuclear Environmental Simulator (NTREES) 6. Non-Nuclear Materials Fabrication & Evaluation 7. Multi-Physics TCA Modeling. This presentation is a overview of these tasks and their accomplishments

Conceptual design report: Nuclear materials storage facility renovation. Part 6, Alternatives study

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

1995-07-14

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based onmore » current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for material and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This report is organized according to the sections and subsections outlined by Attachment 111-2 of DOE Document AL 4700.1, Project Management System. It is organized into seven parts. This document, Part VI - Alternatives Study, presents a study of the different storage/containment options considered for NMSF.« less

Improved Technology To Prevent Nuclear Proliferation And Counter Nuclear Terrorism

DOE Office of Scientific and Technical Information (OSTI.GOV)

Richardson, J; Yuldashev, B; Labov, S

2006-06-12

As the world moves into the 21st century, the possibility of greater reliance on nuclear energy will impose additional technical requirements to prevent proliferation. In addition to proliferation resistant reactors, a careful examination of the various possible fuel cycles from cradle to grave will provide additional technical and nonproliferation challenges in the areas of conversion, enrichment, transportation, recycling and waste disposal. Radiation detection technology and information management have a prominent role in any future global regime for nonproliferation. As nuclear energy and hence nuclear materials become an increasingly global phenomenon, using local technologies and capabilities facilitate incorporation of enhanced monitoringmore » and detection on the regional level. Radiation detection technologies are an important tool in the prevention of proliferation and countering radiological/nuclear terrorism. A variety of new developments have enabled enhanced performance in terms of energy resolution, spatial resolution, passive detection, predictive modeling and simulation, active interrogation, and ease of operation and deployment in the field. For example, various gamma ray imaging approaches are being explored to combine spatial resolution with background suppression in order to enhance sensitivity many-fold at reasonable standoff distances and acquisition times. New materials and approaches are being developed in order to provide adequate energy resolution in field use without the necessity for liquid nitrogen. Different detection algorithms enable fissile materials to be distinguished from other radioisotopes.« less

Materials Degradation and Detection (MD2): Deep Dive Final Report

DOE Office of Scientific and Technical Information (OSTI.GOV)

McCloy, John S.; Montgomery, Robert O.; Ramuhalli, Pradeep

2013-02-01

An effort is underway at Pacific Northwest National Laboratory (PNNL) to develop a fundamental and general framework to foster the science and technology needed to support real-time monitoring of early degradation in materials used in the production of nuclear power. The development of such a capability would represent a timely solution to the mounting issues operators face with materials degradation in nuclear power plants. The envisioned framework consists of three primary and interconnected “thrust” areas including 1) microstructural science, 2) behavior assessment, and 3) monitoring and predictive capabilities. A brief state-of-the-art assessment for each of these core technology areas ismore » discussed in the paper.« less

Nuclear Symbiosis - A Means to Achieve Sustainable Nuclear Growth while Limiting the Spread of Sensititive Nuclear Technology

DOE Office of Scientific and Technical Information (OSTI.GOV)

David Shropshire

Global growth of nuclear energy in the 21st century is creating new challenges to limit the spread of nuclear technology without hindering adoption in countries now considering nuclear power. Independent nuclear states desire autonomy over energy choices and seek energy independence. However, this independence comes with high costs for development of new indigenous fuel cycle capabilities. Nuclear supplier states and expert groups have proposed fuel supply assurance mechanisms such as fuel take-back services, international enrichment services and fuel banks in exchange for recipient state concessions on the development of sensitive technologies. Nuclear states are slow to accept any concessions tomore » their rights under the Non-Proliferation Treaty. To date, decisions not to develop indigenous fuel cycle capabilities have been driven primarily by economics. However, additional incentives may be required to offset a nuclear state’s perceived loss of energy independence. This paper proposes alternative economic development incentives that could help countries decide to forgo development of sensitive nuclear technologies. The incentives are created through a nuclear-centered industrial complex with “symbiotic” links to indigenous economic opportunities. This paper also describes a practical tool called the “Nuclear Materials Exchange” for identifying these opportunities.« less

Research on the Use of Robotics in Hazardous Environments at Sandia National Laboratories

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kwok, Kwan S.

Many hazardous material handling needs exist in remote unstructured environments. Currently these operations are accomplished using personnel in direct contact with the hazards. A safe and cost effective alternative to this approach is the use of intelligent robotic systems for safe handling, packaging, transport, and even excavation of hazardous materials. The Intelligent Systems and Robotics Center of Sandia National Laboratories has developed and deployed robotic technologies for use in hazardous environments, three of which have been deployed in DOE production facilities for handling of special nuclear materials. Other systems are currently under development for packaging special nuclear materials. This papermore » presents an overview of the research activities, including five delivered systems, at %ndia National Laboratories on the use of robotics in hazardous environments.« less

ATF Neutron Irradiation Program Technical Plan

DOE Office of Scientific and Technical Information (OSTI.GOV)

Geringer, J. W.; Katoh, Yutai

The Japan Atomic Energy Agency (JAEA) under the Civil Nuclear Energy Working Group (CNWG) is engaged in a cooperative research effort with the U.S. Department of Energy (DOE) to explore issues related to nuclear energy, including research on accident-tolerant fuels and materials for use in light water reactors. This work develops a draft technical plan for a neutron irradiation program on the candidate accident-tolerant fuel cladding materials and elements using the High Flux Isotope Reactor (HFIR). The research program requires the design of a detailed experiment, development of test vehicles, irradiation of test specimens, possible post-irradiation examination and characterization ofmore » irradiated materials and the shipment of irradiated materials to JAEA in Japan. This report discusses the technical plan of the experimental study.« less

10 CFR 74.15 - Nuclear material transaction reports.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Nuclear material transaction reports. 74.15 Section 74.15 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL General Reporting and Recordkeeping Requirements § 74.15 Nuclear material transaction reports. (a...

10 CFR 74.15 - Nuclear material transaction reports.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Nuclear material transaction reports. 74.15 Section 74.15 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL General Reporting and Recordkeeping Requirements § 74.15 Nuclear material transaction reports. (a...

10 CFR 74.15 - Nuclear material transaction reports.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Nuclear material transaction reports. 74.15 Section 74.15 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL General Reporting and Recordkeeping Requirements § 74.15 Nuclear material transaction reports. (a...

10 CFR 74.15 - Nuclear material transaction reports.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Nuclear material transaction reports. 74.15 Section 74.15 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL General Reporting and Recordkeeping Requirements § 74.15 Nuclear material transaction reports. (a...

Experiments and models of general corrosion and flow-assisted corrosion of materials in nuclear reactor environments

NASA Astrophysics Data System (ADS)

Cook, William Gordon

Corrosion and material degradation issues are of concern to all industries. However, the nuclear power industry must conform to more stringent construction, fabrication and operational guidelines due to the perceived additional risk of operating with radioactive components. Thus corrosion and material integrity are of considerable concern for the operators of nuclear power plants and the bodies that govern their operations. In order to keep corrosion low and maintain adequate material integrity, knowledge of the processes that govern the material's breakdown and failure in a given environment are essential. The work presented here details the current understanding of the general corrosion of stainless steel and carbon steel in nuclear reactor primary heat transport systems (PHTS) and examines the mechanisms and possible mitigation techniques for flow-assisted corrosion (FAC) in CANDU outlet feeder pipes. Mechanistic models have been developed based on first principles and a 'solution-pores' mechanism of metal corrosion. The models predict corrosion rates and material transport in the PHTS of a pressurized water reactor (PWR) and the influence of electrochemistry on the corrosion and flow-assisted corrosion of carbon steel in the CANDU outlet feeders. In-situ probes, based on an electrical resistance technique, were developed to measure the real-time corrosion rate of reactor materials in high-temperature water. The probes were used to evaluate the effects of coolant pH and flow on FAC of carbon steel as well as demonstrate of the use of titanium dioxide as a coolant additive to mitigated FAC in CANDU outlet feeder pipes.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Swift, Alicia L.

There is no better time than now to close the loophole in Article IV of the Nuclear Non-proliferation Treaty (NPT) that excludes military uses of fissile material from nuclear safeguards. Several countries have declared their intention to pursue and develop naval reactor technology, including Argentina, Brazil, Iran, and Pakistan, while other countries such as China, India, Russia, and the United States are expanding their capabilities. With only a minority of countries using low enriched uranium (LEU) fuel in their naval reactors, it is possible that a state could produce highly enriched uranium (HEU) under the guise of a nuclear navymore » while actually stockpiling the material for a nuclear weapon program. This paper examines the likelihood that non-nuclear weapon states exploit the loophole to break out from the NPT and also the regional ramifications of deterrence and regional stability of expanding naval forces. Possible solutions to close the loophole are discussed, including expanding the scope of the Fissile Material Cut-off Treaty, employing LEU fuel instead of HEU fuel in naval reactors, amending the NPT, creating an export control regime for naval nuclear reactors, and forming individual naval reactor safeguards agreements.« less

Study of a Tricarbide Grooved Ring Fuel Element for Nuclear Thermal Propulsion

NASA Technical Reports Server (NTRS)

Taylor, Brian; Emrich, Bill; Tucker, Dennis; Barnes, Marvin; Donders, Nicolas; Benensky, Kelsa

2018-01-01

Deep space exploration, especially that of Mars, is on the horizon as the next big challenge for space exploration. Nuclear propulsion, through which high thrust and efficiency can be achieved, is a promising option for decreasing the cost and logistics of such a mission. Work on nu- clear thermal engines goes back to the days of the NERVA program. Currently, nuclear thermal propulsion is under development again in various forms to provide a superior propulsion system for deep space exploration. The authors have been working to develop a concept nuclear thermal engine that uses a grooved ring fuel element as an alternative to the traditional hexagonal rod design. The authors are also studying the use of carbide fuels. The concept was developed in order to increase surface area and heat transfer to the propellant. The use of carbides would also raise the operating temperature of the reactor. It is hoped that this could lead to a higher thrust to weight nuclear thermal engine. This paper describes the modeling of neutronics, heat transfer, and fluid dynamics of this alternative nuclear fuel element geometry. Fabrication experiments of grooved rings from carbide refractory metals are also presented along with material characterization and interactions with a hot hydrogen environment. Results of experiments and associated analysis are desired densities with some success in material distribution and reaching a solid solution. Future work is needed to improve distribution of material, minimize oxidation during the milling process, and de ne a fabrication process that will serve for constructing grooved ring fuel rods for large system tests.

Semiconductor Radiation Detectors: Basic principles and some uses of a recent tool that has revolutionized nuclear physics are described.

PubMed

Goulding, F S; Stone, Y

1970-10-16

The past decade has seen the rapid development and exploitation of one of the most significant tools of nuclear physics, the semiconductor radiation detector. Applications of the device to the analysis of materials promises to be one of the major contributions of nuclear research to technology, and may even assist in some aspects of our environmental problems. In parallel with the development of these applications, further developments in detectors for nuclear research are taking place: the use of very thin detectors for heavyion identification, position-sensitive detectors for nuclear-reaction studies, and very pure germanium for making more satisfactory detectors for many applications suggest major future contributions to physics.

Development of a Si-PM based alpha camera for plutonium detection in nuclear fuel facilities

NASA Astrophysics Data System (ADS)

Morishita, Yuki; Yamamoto, Seiichi; Izaki, Kenji; Kaneko, Junichi H.; Toi, Kohei; Tsubota, Youichi

2014-05-01

Alpha particles are monitored for detecting nuclear fuel material (i.e., plutonium and uranium) at nuclear fuel facilities. Currently, for monitoring the airborne contamination of nuclear fuel, only energy information measured by Si-semiconductor detectors is used to distinguish nuclear fuel material from radon daughters. In some cases, however, such distinguishing is difficult when the radon concentration is high. In addition, a Si-semiconductor detector is generally sensitive to noise. In this study, we developed a new alpha-particle imaging system by combining a Si-PM array, which is insensitive to noise, with a Ce-doped Gd3Al2Ga3O12(GAGG) scintillator, and evaluated our developed system's fundamental performance. The scintillator was 0.1-mm thick, and the light guide was 3.0 mm thick. An 241Am source was used for all the measurements. We evaluated the spatial resolution by taking an image of a resolution chart. A 1.6 lp/mm slit was clearly resolved, and the spatial resolution was estimated to be less than 0.6-mm FWHM. The energy resolution was 13% FWHM. A slight distortion was observed in the image, and the uniformity near its center was within ±24%. We conclude that our developed alpha-particle imaging system is promising for plutonium detection at nuclear fuel facilities.

Radiochemical Processing Laboratory (RPL) at PNNL

DOE Office of Scientific and Technical Information (OSTI.GOV)

Peurrung, Tony; Clark, Sue; Bryan, Sam

2017-03-23

Nuclear research is one of the core components of PNNL's mission. The centerpiece of PNNL's nuclear research is the Radiochemical Processing Laboratory (RPL), a Category 2 nuclear facility with state-of-the-art instrumentation, scientific expertise, and specialized capabilities that enable research with significant quantities of fissionable materials and other radionuclides—from tritium to plutonium. High impact radiological research has been conducted in the RPL since the 1950's, when nuclear weapons and energy production at Hanford were at the forefront of national defense. Since then, significant investments have been made in the RPL to maintain it as a premier nuclear science research facility supportingmore » multiple programs. Most recently, PNNL is developing a world-class analytical electron microscopy facility dedicated to the characterization of radiological materials.« less

AN EVALUATION OF POTENTIAL LINER MATERIALS FOR ELIMINATING FCCI IN IRRADIATED METALLIC NUCLEAR FUEL ELEMENTS

DOE Office of Scientific and Technical Information (OSTI.GOV)

D. D. Keiser; J. I. Cole

2007-09-01

Metallic nuclear fuels are being looked at as part of the Global Nuclear Energy Program for transmuting longlive transuranic actinide isotopes contained in spent nuclear fuel into shorter-lived fission products. In order to optimize the performance of these fuels, the concept of using liners to eliminate the fuel/cladding chemical interactions that can occur during irradiation of a fuel element has been investigated. The potential liner materials Zr and V have been tested using solid-solid diffusion couples, consisting of liner materials butted against fuel alloys and against cladding materials. The couples were annealed at the relatively high temperature of 700°C. Thismore » temperature would be the absolute maximum temperature present at the fuel/cladding interface for a fuel element in-reactor. Analysis was performed using a scanning electron microscope equipped with energy-dispersive and wavelengthdispersive spectrometers (SEM/EDS/WDS) to evaluate any developed diffusion structures. At 700°C, minimal interaction was observed between the metallic fuels and either Zr or V. Similarly, limited interaction was observed between the Zr and V and the cladding materials. The best performing liner material appeared to be the V, based on amounts of interaction.« less

Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel

DOE PAGES

Bragg-Sitton, Shannon M.; Todosow, Michael; Montgomery, Robert; ...

2017-03-26

The safe, reliable, and economic operation of the nation’s nuclear power reactor fleet has always been a top priority for the nuclear industry. Continual improvement of technology, including advanced materials and nuclear fuels, remains central to the industry’s success. Enhancing the accident tolerance of light water reactors (LWRs) became a topic of serious discussion following the 2011 Great East Japan Earthquake, resulting tsunami, and subsequent damage to the Fukushima Daiichi nuclear power plant complex. The overall goal for the development of accident-tolerant fuel (ATF) for LWRs is to identify alternative fuel system technologies to further enhance the safety, competitiveness, andmore » economics of commercial nuclear power. Designed for use in the current fleet of commercial LWRs or in reactor concepts with design certifications (GEN-III+), fuels with enhanced accident tolerance would endure loss of active cooling in the reactor core for a considerably longer period of time than the current fuel system while maintaining or improving performance during normal operations. The complex multiphysics behavior of LWR nuclear fuel in the integrated reactor system makes defining specific material or design improvements difficult; as such, establishing desirable performance attributes is critical in guiding the design and development of fuels and cladding with enhanced accident tolerance. Research and development of ATF in the United States is conducted under the U.S. Department of Energy (DOE) Fuel Cycle Research and Development Advanced Fuels Campaign. The DOE is sponsoring multiple teams to develop ATF concepts within multiple national laboratories, universities, and the nuclear industry. Concepts under investigation offer both evolutionary and revolutionary changes to the current nuclear fuel system. This study summarizes the technical evaluation methodology proposed in the United States to aid in the optimization and prioritization of candidate ATF designs.« less

Nuclear programs in India and Pakistan

DOE Office of Scientific and Technical Information (OSTI.GOV)

Mian, Zia

India and Pakistan launched their respective nuclear programs in the 1940s and 1950s with considerable foreign technical support, especially from the United States Atoms for Peace Program. The technology and training that was acquired served as the platform for later nuclear weapon development efforts that included nuclear weapon testing in 1974 and in 1998 by India, and also in 1998 by Pakistan - which had illicitly acquired uranium enrichment technology especially from Europe and received assistance from China. As of 2013, both India and Pakistan were continuing to produce fissile material for weapons, in the case of India also formore » nuclear naval fuel, and were developing a diverse array of ballistic and cruise missiles. International efforts to restrain the South Asian nuclear build-up have been largely set aside over the past decade as Pakistani support became central for the U.S. war in Afghanistan and as U.S. geopolitical and economic interests in supporting the rise of India, in part as a counter to China, led to India being exempted both from U.S non-proliferation laws and international nuclear trade guidelines. In the absence of determined international action and with Pakistan blocking the start of talks on a fissile material cutoff treaty, nuclear weapon programs in South Asia are likely to keep growing for the foreseeable future.« less

Nuclear programs in India and Pakistan

NASA Astrophysics Data System (ADS)

Mian, Zia

2014-05-01

India and Pakistan launched their respective nuclear programs in the 1940s and 1950s with considerable foreign technical support, especially from the United States Atoms for Peace Program. The technology and training that was acquired served as the platform for later nuclear weapon development efforts that included nuclear weapon testing in 1974 and in 1998 by India, and also in 1998 by Pakistan - which had illicitly acquired uranium enrichment technology especially from Europe and received assistance from China. As of 2013, both India and Pakistan were continuing to produce fissile material for weapons, in the case of India also for nuclear naval fuel, and were developing a diverse array of ballistic and cruise missiles. International efforts to restrain the South Asian nuclear build-up have been largely set aside over the past decade as Pakistani support became central for the U.S. war in Afghanistan and as U.S. geopolitical and economic interests in supporting the rise of India, in part as a counter to China, led to India being exempted both from U.S non-proliferation laws and international nuclear trade guidelines. In the absence of determined international action and with Pakistan blocking the start of talks on a fissile material cutoff treaty, nuclear weapon programs in South Asia are likely to keep growing for the foreseeable future.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Schecker, Jay A

After a prolonged absence, the word 'nuclear' has returned to the lexicon of sustainable domestic energy resources. Due in no small part to its demonstrated reliability, nuclear power is poised to playa greater role in the nation's energy future, producing clean, carbon-neutral electricity and contributing even more to our energy security. To nuclear scientists, the resurgence presents an opportunity to inject new technologies into the industry to maximize the benefits that nuclear energy can provide. 'By developing new options for waste management and exploiting new materials to make key technological advances, we can significantly impact the use of nuclear energymore » in our future energy mix,' says Chris Stanek, a materials scientist at Los Alamos National Laboratory. Stanek approaches the big technology challenges by thinking way small, all the way down to the atoms. He and his colleagues are using cutting edge atomic-scale simulations to address a difficult aspect of nuclear waste -- predicting its behavior far into the future. Their research is part of a broader, coordinated effort on the part of the Laboratory to use its considerable experimental, theoretical, and computational capabilities to explore advanced materials central to not only waste issues, but to nuclear fuels as well.« less

Evaluation of the automatic optical authentication technologies for control systems of objects

NASA Astrophysics Data System (ADS)

Averkin, Vladimir V.; Volegov, Peter L.; Podgornov, Vladimir A.

2000-03-01

The report considers the evaluation of the automatic optical authentication technologies for the automated integrated system of physical protection, control and accounting of nuclear materials at RFNC-VNIITF, and for providing of the nuclear materials nonproliferation regime. The report presents the nuclear object authentication objectives and strategies, the methodology of the automatic optical authentication and results of the development of pattern recognition techniques carried out under the ISTC project #772 with the purpose of identification of unique features of surface structure of a controlled object and effects of its random treatment. The current decision of following functional control tasks is described in the report: confirmation of the item authenticity (proof of the absence of its substitution by an item of similar shape), control over unforeseen change of item state, control over unauthorized access to the item. The most important distinctive feature of all techniques is not comprehensive description of some properties of controlled item, but unique identification of item using minimum necessary set of parameters, properly comprising identification attribute of the item. The main emphasis in the technical approach is made on the development of rather simple technological methods for the first time intended for use in the systems of physical protection, control and accounting of nuclear materials. The developed authentication devices and system are described.

AGC 2 Irradiation Creep Strain Data Analysis

DOE Office of Scientific and Technical Information (OSTI.GOV)

Windes, William E.; Rohrbaugh, David T.; Swank, W. David

2016-08-01

The Advanced Reactor Technologies Graphite Research and Development Program is conducting an extensive graphite irradiation experiment to provide data for licensing of a high temperature reactor (HTR) design. In past applications, graphite has been used effectively as a structural and moderator material in both research and commercial high temperature gas cooled reactor designs. Nuclear graphite H-451, used previously in the United States for nuclear reactor graphite components, is no longer available. New nuclear graphite grades have been developed and are considered suitable candidates for new HTR reactor designs. To support the design and licensing of HTR core components within amore » commercial reactor, a complete properties database must be developed for these current grades of graphite. Quantitative data on in service material performance are required for the physical, mechanical, and thermal properties of each graphite grade, with a specific emphasis on data accounting for the life limiting effects of irradiation creep on key physical properties of the HTR candidate graphite grades. Further details on the research and development activities and associated rationale required to qualify nuclear grade graphite for use within the HTR are documented in the graphite technology research and development plan.« less

10 CFR 74.33 - Nuclear material control and accounting for uranium enrichment facilities authorized to produce...

Code of Federal Regulations, 2011 CFR

2011-01-01

... enrichment facilities authorized to produce special nuclear material of low strategic significance. 74.33... NUCLEAR MATERIAL Special Nuclear Material of Low Strategic Significance § 74.33 Nuclear material control... strategic significance. (a) General performance objectives. Each licensee who is authorized by this chapter...

Glass and Glass-Ceramic Materials from Simulated Composition of Lunar and Martian Soils: Selected Properties and Potential Applications

NASA Technical Reports Server (NTRS)

Ray, C. S.; Sen, S.; Reis, S. T.; Kim, C. W.

2005-01-01

In-situ resource processing and utilization on planetary bodies is an important and integral part of NASA's space exploration program. Within this scope and context, our general effort is primarily aimed at developing glass and glass-ceramic type materials using lunar and martian soils, and exploring various applications of these materials for planetary surface operations. Our preliminary work to date have demonstrated that glasses can be successfully prepared from melts of the simulated composition of both lunar and martian soils, and the melts have a viscosity-temperature window appropriate for drawing continuous glass fibers. The glasses are shown to have the potential for immobilizing certain types of nuclear wastes without deteriorating their chemical durability and thermal stability. This has a direct impact on successfully and economically disposing nuclear waste generated from a nuclear power plant on a planetary surface. In addition, these materials display characteristics that can be manipulated using appropriate processing protocols to develop glassy or glass-ceramic magnets. Also discussed in this presentation are other potential applications along with a few selected thermal, chemical, and structural properties as evaluated up to this time for these materials.

Progress in space nuclear reactor power systems technology development - The SP-100 program

NASA Technical Reports Server (NTRS)

Davis, H. S.

1984-01-01

Activities related to the development of high-temperature compact nuclear reactors for space applications had reached a comparatively high level in the U.S. during the mid-1950s and 1960s, although only one U.S. nuclear reactor-powered spacecraft was actually launched. After 1973, very little effort was devoted to space nuclear reactor and propulsion systems. In February 1983, significant activities toward the development of the technology for space nuclear reactor power systems were resumed with the SP-100 Program. Specific SP-100 Program objectives are partly related to the determination of the potential performance limits for space nuclear power systems in 100-kWe and 1- to 100-MW electrical classes. Attention is given to potential missions and applications, regimes of possible space power applicability, safety considerations, conceptual system designs, the establishment of technical feasibility, nuclear technology, materials technology, and prospects for the future.

10 CFR 73.72 - Requirement for advance notice of shipment of formula quantities of strategic special nuclear...

Code of Federal Regulations, 2012 CFR

2012-01-01

... quantities of strategic special nuclear material, special nuclear material of moderate strategic significance, or irradiated reactor fuel. 73.72 Section 73.72 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED... shipment of formula quantities of strategic special nuclear material, special nuclear material of moderate...

Nuclear Materials Focus Area Fiscal Year 2002 Mid Year Review

DOE Office of Scientific and Technical Information (OSTI.GOV)

Thiel, Elizabeth Chilcote

2002-05-01

The Nuclear Materials Focus Area (NMFA) held its annual mid-year review on February 12 and 14, 2002, in Santa Fe, New Mexico. The purpose of this review was to examine both the technical aspects and the programmatic aspects of its technology development program. The focus area activities were reviewed by a panel consisting of personnel representing the end users of the technologies, and technical experts in nuclear materials. This year's review was somewhat different than in the past, as the stress was on how well the various projects being managed through the NMFA aligned with the two thrust areas andmore » nine key goals and priorities recently issued by the Deputy Assistant Secretary for DOE's Office of Environmental Management (EM).« less

Nuclear Materials Focus Area Fiscal Year 2002 Mid Year Review

DOE Office of Scientific and Technical Information (OSTI.GOV)

Thiel, E.C.; Fuhrman, P.W.

2002-05-30

The Nuclear Materials Focus Area (NMFA) held its annual mid-year review on February 12 and 14, 2002, in Santa Fe, New Mexico. The purpose of this review was to examine both the technical aspects and the programmatic aspects of its technology development program. The focus area activities were reviewed by a panel consisting of personnel representing the end users of the technologies, and technical experts in nuclear materials. This year's review was somewhat different than in the past, as the stress was on how well the various projects being managed through the NMFA aligned with the two thrust areas andmore » nine key goals and priorities recently issued by the Deputy Assistant Secretary for DOE's Office of Environmental Management (EM).« less

Calibrating Nonlinear Soil Material Properties for Seismic Analysis Using Soil Material Properties Intended for Linear Analysis

DOE Office of Scientific and Technical Information (OSTI.GOV)

Spears, Robert Edward; Coleman, Justin Leigh

2015-08-01

Seismic analysis of nuclear structures is routinely performed using guidance provided in “Seismic Analysis of Safety-Related Nuclear Structures and Commentary (ASCE 4, 1998).” This document, which is currently under revision, provides detailed guidance on linear seismic soil-structure-interaction (SSI) analysis of nuclear structures. To accommodate the linear analysis, soil material properties are typically developed as shear modulus and damping ratio versus cyclic shear strain amplitude. A new Appendix in ASCE 4-2014 (draft) is being added to provide guidance for nonlinear time domain SSI analysis. To accommodate the nonlinear analysis, a more appropriate form of the soil material properties includes shear stressmore » and energy absorbed per cycle versus shear strain. Ideally, nonlinear soil model material properties would be established with soil testing appropriate for the nonlinear constitutive model being used. However, much of the soil testing done for SSI analysis is performed for use with linear analysis techniques. Consequently, a method is described in this paper that uses soil test data intended for linear analysis to develop nonlinear soil material properties. To produce nonlinear material properties that are equivalent to the linear material properties, the linear and nonlinear model hysteresis loops are considered. For equivalent material properties, the shear stress at peak shear strain and energy absorbed per cycle should match when comparing the linear and nonlinear model hysteresis loops. Consequently, nonlinear material properties are selected based on these criteria.« less

Hot Hydrogen Testing of Tungsten-Uranium Dioxide (W-UO2) CERMET Fuel Materials for Nuclear Thermal Propulsion

NASA Technical Reports Server (NTRS)

Hickman, Robert; Broadway, Jeramie

2014-01-01

CERMET fuel materials are being developed at the NASA Marshall Space Flight Center for a Nuclear Cryogenic Propulsion Stage. Recent work has resulted in the development and demonstration of a Compact Fuel Element Environmental Test (CFEET) System that is capable of subjecting depleted uranium fuel material samples to hot hydrogen. A critical obstacle to the development of an NCPS engine is the high-cost and safety concerns associated with developmental testing in nuclear environments. The purpose of this testing capability is to enable low-cost screening of candidate materials, fabrication processes, and further validation of concepts. The CERMET samples consist of depleted uranium dioxide (UO2) fuel particles in a tungsten metal matrix, which has been demonstrated on previous programs to provide improved performance and retention of fission products1. Numerous past programs have utilized hot hydrogen furnace testing to develop and evaluate fuel materials. The testing provides a reasonable simulation of temperature and thermal stress effects in a flowing hydrogen environment. Though no information is gained about radiation damage, the furnace testing is extremely valuable for development and verification of fuel element materials and processes. The current work includes testing of subscale W-UO2 slugs to evaluate fuel loss and stability. The materials are then fabricated into samples with seven cooling channels to test a more representative section of a fuel element. Several iterations of testing are being performed to evaluate fuel mass loss impacts from density, microstructure, fuel particle size and shape, chemistry, claddings, particle coatings, and stabilizers. The fuel materials and forms being evaluated on this effort have all been demonstrated to control fuel migration and loss. The objective is to verify performance improvements of the various materials and process options prior to expensive full scale fabrication and testing. Post test analysis will include weight percent fuel loss, microscopy, dimensional tolerance, and fuel stability.

New Brunswick Laboratory. Progress report, October 1995--September 1996

DOE Office of Scientific and Technical Information (OSTI.GOV)

NONE

Fiscal year (FY) 1996 was a very good year for New Brunswick Laboratory (NBL), whose major sponsor is the Office of Safeguards and Security (NN-51) in the US Department of Energy (DOE), Office of Nonproliferation and National Security, Office of Security Affairs. Several projects pertinent to the NBL mission were completed, and NBL`s interactions with partners and customers were encouraging. Among the partners with which NBL interacted in this report period were the International Atomic Energy Agency (IAEA), NN-51. Environmental Program Group of the DOE Chicago Operations Office, International Safeguards Project Office, Waste Isolation Pilot Plant (WIPP), Ukraine Working Group,more » Fissile Materials Assurance Working Group, National Institute of Standards and Technology (NIST), Nuclear Regulatory Commission (NRC), Institute for Reference Materials and Measurements (IRMM) in Belgium, Brazilian/Argentine Agency for Accounting and Control of Nuclear Materials (ABACC), Lockheed Idaho Technologies Company, and other DOE facilities and laboratories. NBL staff publications, participation in safeguards assistance and other nuclear programs, development of new reference materials, involvement in the updating and refinement of DOE documents, service in enhancing the science education of others, and other related activities enhanced NBL`s status among DOE laboratories and facilities. Noteworthy are the facts that NBL`s small inventory of nuclear materials is accurately accounted for, and, as in past years, its materials and human resources were used in peaceful nuclear activities worldwide.« less

A Delayed Neutron Counting System for the Analysis of Special Nuclear Materials

NASA Astrophysics Data System (ADS)

Sellers, Madison Theresa

Nuclear forensic analysis is a modem science that uses numerous analytical techniques to identify and attribute nuclear materials in the event of a nuclear explosion, radiological terrorist attack or the interception of illicit nuclear material smuggling. The Canadian Department of National Defence has participated in recent international exercises that have highlighted the Nation's requirement to develop nuclear forensics expertise, protocol and capabilities, specifically pertaining to the analysis of special nuclear materials (SNM). A delayed neutron counting (DNC) system has been designed and established at the Royal Military College of Canada (RMC) to enhance the Government's SNM analysis capabilities. This analytical technique complements those already at RMC by providing a rapid and non-destructive method for the analysis of the fissile isotopes of both uranium (U) and plutonium (Pu). The SLOWPOKE-2 reactor at RMC produces a predominately thermal neutron flux. These neutrons induce fission in the SNM isotopes 233U, 235U and 239Pu releasing prompt fast neutrons, energy and radioactive fission fragments. Some of these fission fragments undergo beta - decay and subsequently emit neutrons, which can be recorded by an array of sensitive 3He detectors. The significant time period between the fission process and the release of these neutrons results in their identification as 'delayed neutrons'. The recorded neutron spectrum varies with time and the count rate curve is unique to each fissile isotope. In-house software, developed by this project, can analyze this delayed neutron curve and provides the fissile mass in the sample. Extensive characterization of the DNC system has been performed with natural U samples with 235 U content ranging from 2--7 microg. The system efficiency and dead time behaviour determined by the natural uranium sample analyses were validated by depleted uranium samples with similar quantities of 235 U resulting in a typical relative error of 3.6%. The system has accurately determined 235U content over three orders of magnitude with 235U amounts as low as 10 ng. The results have also been proven to be independent of small variations in total analyte volume and geometry, indicating that it is an ideal technique for the analysis of samples containing SNM in a variety of different matrices. The Analytical Sciences Group at RMC plans to continue DNC system development to include 233U and 239pu analysis and mixtures of SNM isotopes. Keywords: delayed neutron counting, special nuclear materials, nuclear forensics.

Nuclear Forensics: A Methodology Applicable to Nuclear Security and to Non-Proliferation

NASA Astrophysics Data System (ADS)

Mayer, K.; Wallenius, M.; Lützenkirchen, K.; Galy, J.; Varga, Z.; Erdmann, N.; Buda, R.; Kratz, J.-V.; Trautmann, N.; Fifield, K.

2011-09-01

Nuclear Security aims at the prevention and detection of and response to, theft, sabotage, unauthorized access, illegal transfer or other malicious acts involving nuclear material. Nuclear Forensics is a key element of nuclear security. Nuclear Forensics is defined as a methodology that aims at re-establishing the history of nuclear material of unknown origin. It is based on indicators that arise from known relationships between material characteristics and process history. Thus, nuclear forensics analysis includes the characterization of the material and correlation with production history. To this end, we can make use of parameters such as the isotopic composition of the nuclear material and accompanying elements, chemical impurities, macroscopic appearance and microstructure of the material. In the present paper, we discuss the opportunities for attribution of nuclear material offered by nuclear forensics as well as its limitations. Particular attention will be given to the role of nuclear reactions. Such reactions include the radioactive decay of the nuclear material, but also reactions with neutrons. When uranium (of natural composition) is exposed to neutrons, plutonium is formed, as well as 236U. We will illustrate the methodology using the example of a piece of uranium metal that dates back to the German nuclear program in the 1940's. A combination of different analytical techniques and model calculations enables a nuclear forensics interpretation, thus correlating the material characteristics with the production history.

NEW DEVELOPMENTS AND APPLICATIONS OF SUPERHEATED EMULSIONS: WARHEAD VERIFICATION AND SPECIAL NUCLEAR MATERIAL INTERDICTION.

PubMed

d'Errico, F; Chierici, A; Gattas-Sethi, M; Philippe, S; Goldston, R; Glaser, A

2018-04-25

In recent years, neutron detection with superheated emulsions has received renewed attention thanks to improved detector manufacturing and read-out techniques, and thanks to successful applications in warhead verification and special nuclear material (SNM) interdiction. Detectors are currently manufactured with methods allowing high uniformity of the drop sizes, which in turn allows the use of optical read-out techniques based on dynamic light scattering. Small detector cartridges arranged in 2D matrices are developed for the verification of a declared warhead without revealing its design. For this application, the enabling features of the emulsions are that bubbles formed at different times cannot be distinguished from each other, while the passive nature of the detectors avoids the susceptibility to electronic snooping and tampering. Large modules of emulsions are developed to detect the presence of shielded special nuclear materials hidden in cargo containers 'interrogated' with high energy X-rays. In this case, the enabling features of the emulsions are photon discrimination, a neutron detection threshold close to 3 MeV and a rate-insensitive read-out.

Non-destructive research methods applied on materials for the new generation of nuclear reactors

NASA Astrophysics Data System (ADS)

Bartošová, I.; Slugeň, V.; Veterníková, J.; Sojak, S.; Petriska, M.; Bouhaddane, A.

2014-06-01

The paper is aimed on non-destructive experimental techniques applied on materials for the new generation of nuclear reactors (GEN IV). With the development of these reactors, also materials have to be developed in order to guarantee high standard properties needed for construction. These properties are high temperature resistance, radiation resistance and resistance to other negative effects. Nevertheless the changes in their mechanical properties should be only minimal. Materials, that fulfil these requirements, are analysed in this work. The ferritic-martensitic (FM) steels and ODS steels are studied in details. Microstructural defects, which can occur in structural materials and can be also accumulated during irradiation due to neutron flux or alpha, beta and gamma radiation, were analysed using different spectroscopic methods as positron annihilation spectroscopy and Barkhausen noise, which were applied for measurements of three different FM steels (T91, P91 and E97) as well as one ODS steel (ODS Eurofer).

Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms

DOE Office of Scientific and Technical Information (OSTI.GOV)

Weber, William J.; Zhang, Yanwen

This is the final report of the NEUP project “Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms.” This project started on July 1, 2012 and was successfully completed on June 30, 2016. This report provides an overview of the main achievements, results and findings through the duration of the project. Additional details can be found in the main body of this report and in the individual Quarterly Reports and associated Deliverables of this project, which have been uploaded in PICS-NE. The objective of this research was to advance understanding and develop validated models on the effectsmore » of self-radiation from beta and alpha decay on the response of used nuclear fuel and nuclear waste forms during high-temperature interim storage and long-term permanent disposition. To achieve this objective, model used-fuel materials and model waste form materials were identified, fabricated, and studied.« less

Microgravity

NASA Image and Video Library

1994-02-03

The objective of this facility is to investigate the potential of space grown semiconductor materials by the vapor transport technique and develop powdered metal and ceramic sintering techniques in microgravity. The materials processed or developed in the SEF have potential application for improving infrared detectors, nuclear particle detectors, photovoltaic cells, bearing cutting tools, electrical brushes and catalysts for chemical production. Flown on STS-60 Commercial Center: Consortium for Materials Development in Space - University of Alabama Huntsville (UAH)

Nuclear Safety

DOE Office of Scientific and Technical Information (OSTI.GOV)

Silver, E G

This document is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

Nuclear power in the 21st century: Challenges and possibilities.

PubMed

Horvath, Akos; Rachlew, Elisabeth

2016-01-01

The current situation and possible future developments for nuclear power--including fission and fusion processes--is presented. The fission nuclear power continues to be an essential part of the low-carbon electricity generation in the world for decades to come. There are breakthrough possibilities in the development of new generation nuclear reactors where the life-time of the nuclear waste can be reduced to some hundreds of years instead of the present time-scales of hundred thousand of years. Research on the fourth generation reactors is needed for the realisation of this development. For the fast nuclear reactors, a substantial research and development effort is required in many fields--from material sciences to safety demonstration--to attain the envisaged goals. Fusion provides a long-term vision for an efficient energy production. The fusion option for a nuclear reactor for efficient production of electricity has been set out in a focussed European programme including the international project of ITER after which a fusion electricity DEMO reactor is envisaged.

Proliferation of nuclear weapons: opportunities for control and abolition.

PubMed

Sidel, Victor W; Levy, Barry S

2007-09-01

Nuclear weapons pose a particularly destructive threat. Prevention of the proliferation and use of nuclear weapons is urgently important to public health. "Horizontal" proliferation refers to nation-states or nonstate entities that do not have, but are acquiring, nuclear weapons or developing the capability and materials for producing them. "Vertical" proliferation refers to nation-states that do possess nuclear weapons and are increasing their stockpiles of these weapons, improving the technical sophistication or reliability of their weapons, or developing new weapons. Because nation-states or other entities that wish to use or threaten to use nuclear weapons need methods for delivering those weapons, proliferation of delivery mechanisms must also be prevented. Controlling proliferation--and ultimately abolishing nuclear weapons--involves national governments, intergovernmental organizations, nongovernmental and professional organizations, and society at large.

Focused technology: Nuclear propulsion

NASA Technical Reports Server (NTRS)

Miller, Thomas J.

1991-01-01

The topics presented are covered in viewgraph form and include: nuclear thermal propulsion (NTP), which challenges (1) high temperature fuel and materials, (2) hot hydrogen environment, (3) test facilities, (4) safety, (5) environmental impact compliance, and (6) concept development, and nuclear electric propulsion (NEP), which challenges (1) long operational lifetime, (2) high temperature reactors, turbines, and radiators, (3) high fuel burn-up reactor fuels, and designs, (4) efficient, high temperature power conditioning, (5) high efficiency, and long life thrusters, (6) safety, (7) environmental impact compliance, and (8) concept development.

A Photofission Delayed γ-ray Spectra Calculation Tool for the Conception of a Nuclear Material Characterization Facility

NASA Astrophysics Data System (ADS)

Bernard, D.; Serot, O.; Simon, E.; Boucher, L.; Plumeri, S.

2018-01-01

The photon interrogation analysis is a nondestructive technique allowing to identify and quantify fissile materials in nuclear waste packages. This paper details an automatic procedure which has been developed to simulate the delayed γ-ray spectra for several actinide photofissions. This calculation tool will be helpful for the fine conception (collimation, shielding, noise background optimizations, etc.) and for the on-line analysis of such a facility.

Flexible Robotic Entry Device for nuclear materials production reactor

DOE Office of Scientific and Technical Information (OSTI.GOV)

Heckendorn, F.M.

1988-01-01

The Savannah River Laboratory (SRL) has developed and is implementing a Flexible Robotic Entry Device (FRED) for the nuclear materials production reactors at the Savannah River Plant (SRP). FRED is designed for rapid deployment into confinement areas of operating reactors to assess unknown conditions. A unique ''smart tether'' method has been incorporated into FRED for simultaneous bidirectional transmission of multiple video/audio/control/power signals over a single coaxial cable. 3 figs.

The Demonstration of the Feasibility of the Tuning and Stimulation of Nuclear Radiation.

DTIC Science & Technology

1988-10-31

line, or the center of a resonance pattern, is called the isomer shift. It is due to the electrostatic interaction of the nucleus with the electron ...magnetic moment due to the presence of unpaired electrons , the material is either paramagnetic or ferromagnetic. In paramagnetic materials these moments...capture and fission.4,5,8 A very fertile interdisciplinary area of nuclear quantum electronics 7 appeared to be developing, encouraged by the

Consortium for materials development in space

NASA Technical Reports Server (NTRS)

1990-01-01

The status of the Consortium for Materials Development in Space (CMDS) is reviewed. Individual CMDS materials projects and flight opportunities on suborbital and orbital carriers are outlined. Projects include: surface coatings and catalyst production; non-linear optical organic materials; physical properties of immiscible polymers; nuclear track detectors; powdered metal sintering; iron-carbon solidification; high-temperature superconductors; physical vapor transport crystal growth; materials preparation and longevity in hyperthermal oxygen; foam formation; measurement of the microgravity environment; and commercial management of space fluids.

Worldwide Emerging Environmental Issues Affecting the U.S. Military. March 2011 Report

DTIC Science & Technology

2011-03-01

nuclear plant http://abcnews.go.com/Business/wireStory?id=13241596 Detection of radioactive material in the soil in Fukushima Daiichi Nuclear Power...and Nuclear Disasters in Japan The important reassessments following the Tōhoku earthquake and tsunami that hit Japan‟s northeast coast on March 11...and the nuclear waste issues are still not solved; hence, the Fukushima disaster might trigger important regime and development changes, such as

Applications of polymeric smart materials to environmental problems.

PubMed Central

Gray, H N; Bergbreiter, D E

1997-01-01

New methods for the reduction and remediation of hazardous wastes like carcinogenic organic solvents, toxic materials, and nuclear contamination are vital to environmental health. Procedures for effective waste reduction, detection, and removal are important components of any such methods. Toward this end, polymeric smart materials are finding useful applications. Polymer-bound smart catalysts are useful in waste minimization, catalyst recovery, and catalyst reuse. Polymeric smart coatings have been developed that are capable of both detecting and removing hazardous nuclear contaminants. Such applications of smart materials involving catalysis chemistry, sensor chemistry, and chemistry relevant to decontamination methodology are especially applicable to environmental problems. PMID:9114277

The challenge of developing structural materials for fusion power systems

NASA Astrophysics Data System (ADS)

Bloom, Everett E.

1998-10-01

Nuclear fusion can be one of the most attractive sources of energy from the viewpoint of safety and minimal environmental impact. Central in the goal of designing a safe, environmentally benign, and economically competitive fusion power system is the requirement for high performance, low activation materials. The general performance requirements for such materials have been defined and it is clear that materials developed for other applications (e.g. aerospace, nuclear fission, fossil energy systems) will not fully meet the needs of fusion. Advanced materials, with composition and microstructure tailored to yield properties that will satisfy the specific requirements of fusion must be developed. The international fusion programs have made significant progress towards this goal. Compositional requirements for low activation lead to a focus of development efforts on silicon carbide composites, vanadium alloys, and advanced martensitic steels as candidate structural material systems. Control of impurities will be critically important in actually achieving low activation but this appears possible. Neutron irradiation produces significant changes in the mechanical and physical properties of each of these material systems raising feasibility questions and design limitations. A focus of the research and development effort is to understand these effects, and through the development of specific compositions and microstructures, produce materials with improved and adequate performance. Other areas of research that are synergistic with the development of radiation resistant materials include fabrication, joining technology, chemical compatibility with coolants and tritium breeders and specific questions relating to the unique characteristics of a given material (e.g. coatings to reduce gas permeation in SiC composites) or design concept (e.g. electrical insulator coatings for liquid metal concepts).

10 CFR 1017.9 - Nuclear material determinations.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 4 2014-01-01 2014-01-01 false Nuclear material determinations. 1017.9 Section 1017.9... NUCLEAR INFORMATION Initially Determining What Information Is Unclassified Controlled Nuclear Information § 1017.9 Nuclear material determinations. (a) The Secretary may determine that a material other than...

10 CFR 1017.9 - Nuclear material determinations.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Nuclear material determinations. 1017.9 Section 1017.9... NUCLEAR INFORMATION Initially Determining What Information Is Unclassified Controlled Nuclear Information § 1017.9 Nuclear material determinations. (a) The Secretary may determine that a material other than...

10 CFR 1017.9 - Nuclear material determinations.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 4 2012-01-01 2012-01-01 false Nuclear material determinations. 1017.9 Section 1017.9... NUCLEAR INFORMATION Initially Determining What Information Is Unclassified Controlled Nuclear Information § 1017.9 Nuclear material determinations. (a) The Secretary may determine that a material other than...

10 CFR 1017.9 - Nuclear material determinations.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 4 2013-01-01 2013-01-01 false Nuclear material determinations. 1017.9 Section 1017.9... NUCLEAR INFORMATION Initially Determining What Information Is Unclassified Controlled Nuclear Information § 1017.9 Nuclear material determinations. (a) The Secretary may determine that a material other than...

10 CFR 1017.9 - Nuclear material determinations.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 4 2011-01-01 2011-01-01 false Nuclear material determinations. 1017.9 Section 1017.9... NUCLEAR INFORMATION Initially Determining What Information Is Unclassified Controlled Nuclear Information § 1017.9 Nuclear material determinations. (a) The Secretary may determine that a material other than...

Materials and Chemical Sciences Division annual report, 1987

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

1988-07-01

Research programs from Lawrence Berkeley Laboratory in materials science, chemical science, nuclear science, fossil energy, energy storage, health and environmental sciences, program development funds, and work for others is briefly described. (CBS)

Novel fabrication of silicon carbide based ceramics for nuclear applications

NASA Astrophysics Data System (ADS)

Singh, Abhishek Kumar

Advances in nuclear reactor technology and the use of gas-cooled fast reactors require the development of new materials that can operate at the higher temperatures expected in these systems. These materials include refractory alloys based on Nb, Zr, Ta, Mo, W, and Re; ceramics and composites such as SiC--SiCf; carbon--carbon composites; and advanced coatings. Besides the ability to handle higher expected temperatures, effective heat transfer between reactor components is necessary for improved efficiency. Improving thermal conductivity of the fuel can lower the center-line temperature and, thereby, enhance power production capabilities and reduce the risk of premature fuel pellet failure. Crystalline silicon carbide has superior characteristics as a structural material from the viewpoint of its thermal and mechanical properties, thermal shock resistance, chemical stability, and low radioactivation. Therefore, there have been many efforts to develop SiC based composites in various forms for use in advanced energy systems. In recent years, with the development of high yield preceramic precursors, the polymer infiltration and pyrolysis (PIP) method has aroused interest for the fabrication of ceramic based materials, for various applications ranging from disc brakes to nuclear reactor fuels. The pyrolysis of preceramic polymers allow new types of ceramic materials to be processed at relatively low temperatures. The raw materials are element-organic polymers whose composition and architecture can be tailored and varied. The primary focus of this study is to use a pyrolysis based process to fabricate a host of novel silicon carbide-metal carbide or oxide composites, and to synthesize new materials based on mixed-metal silicocarbides that cannot be processed using conventional techniques. Allylhydridopolycarbosilane (AHPCS), which is an organometal polymer, was used as the precursor for silicon carbide. Inert gas pyrolysis of AHPCS produces near-stoichiometric amorphous silicon carbide (a-SiC) at 900--1150 °C. Results indicated that this processing technique can be effectively used to fabricate various silicon carbide composites with UC or UO2 as the nuclear component.

Production of nuclear grade zirconium: A review

NASA Astrophysics Data System (ADS)

Xu, L.; Xiao, Y.; van Sandwijk, A.; Xu, Q.; Yang, Y.

2015-11-01

Zirconium is an ideal material for nuclear reactors due to its low absorption cross-section for thermal neutrons, whereas the typically contained hafnium with strong neutron-absorption is very harmful for zirconium as a fuel cladding material. This paper provides an overview of the processes for nuclear grade zirconium production with emphasis on the methods of Zr-Hf separation. The separation processes are roughly classified into hydro- and pyrometallurgical routes. The known pyrometallurgical Zr-Hf separation methods are discussed based on the following reaction features: redox characteristics, volatility, electrochemical properties and molten salt-metal equilibrium. In the present paper, the available Zr-Hf separation technologies are compared. The advantages and disadvantages as well as future directions of research and development for nuclear grade zirconium production are discussed.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Pestovich, Kimberly Shay

Harnessing the power of the nuclear sciences for national security and to benefit others is one of Los Alamos National Laboratory’s missions. MST-8 focuses on manipulating and studying how the structure, processing, properties, and performance of materials interact at the atomic level under nuclear conditions. Within this group, single crystal scintillators contribute to the safety and reliability of weapons, provide global security safeguards, and build on scientific principles that carry over to medical fields for cancer detection. Improved cladding materials made of ferritic-martensitic alloys support the mission of DOE-NE’s Fuel Cycle Research and Development program to close the nuclear fuelmore » cycle, aiming to solve nuclear waste management challenges and thereby increase the performance and safety of current and future reactors.« less

Structural Materials and Fuels for Space Power Plants

NASA Technical Reports Server (NTRS)

Bowman, Cheryl; Busby, Jeremy; Porter, Douglas

2008-01-01

A fission reactor combined with Stirling convertor power generation is one promising candidate in on-going Fission Surface Power (FSP) studies for future lunar and Martian bases. There are many challenges for designing and qualifying space-rated nuclear power plants. In order to have an affordable and sustainable program, NASA and DOE designers want to build upon the extensive foundation in nuclear fuels and structural materials. This talk will outline the current Fission Surface Power program and outline baseline design options for a lunar power plant with an emphasis on materials challenges. NASA first organized an Affordable Fission Surface Power System Study Team to establish a reference design that could be scrutinized for technical and fiscal feasibility. Previous papers and presentations have discussed this study process in detail. Considerations for the reference design included that no significant nuclear technology, fuels, or material development were required for near term use. The desire was to build upon terrestrial-derived reactor technology including conventional fuels and materials. Here we will present an overview of the reference design, Figure 1, and examine the materials choices. The system definition included analysis and recommendations for power level and life, plant configuration, shielding approach, reactor type, and power conversion type. It is important to note that this is just one concept undergoing refinement. The design team, however, understands that materials selection and improvement must be an integral part of the system development.

Radiation Resistant Electrical Insulation Materials for Nuclear Reactors: Final Report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Duckworth, Robert C.; Aytug, Tolga; Paranthaman, M. Parans

The instrument and control cables in future nuclear reactors will be exposed to temperatures, dose rates, and accumulated doses exceeding those originally anticipated for the 40-year operational life of the nuclear power plant fleet. The use of nanocomposite dielectrics as insulating material for such cables has been considered a route to performance improvement. In this project, nanoparticles were developed and successfully included in three separate material systems [cross-linked polyvinyl alcohol (PVA/XLPVA), cross-linked polyethylene (PE/XLPE), and polyimide (PI)], and the chemical, electrical, and mechanical performance of each was analyzed as a function of environmental exposure and composition. Improvements were found inmore » each material system; however, refinement of each processing pathway is needed, and the consequences of these refinements in the context of thermal, radiation, and moisture exposures should be evaluated before transferring knowledge to industry.« less

Applications of nuclear physics

NASA Astrophysics Data System (ADS)

Hayes, A. C.

2017-02-01

Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applications of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.

Applications of nuclear physics

DOE PAGES

Hayes-Sterbenz, Anna Catherine

2017-01-10

Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applicationsmore » of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Lastly, each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.« less

Applications of nuclear physics.

PubMed

Hayes, A C

2017-02-01

Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applications of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.

Applications of nuclear physics

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hayes-Sterbenz, Anna Catherine

Today the applications of nuclear physics span a very broad range of topics and fields. This review discusses a number of aspects of these applications, including selected topics and concepts in nuclear reactor physics, nuclear fusion, nuclear non-proliferation, nuclear-geophysics, and nuclear medicine. The review begins with a historic summary of the early years in applied nuclear physics, with an emphasis on the huge developments that took place around the time of World War II, and that underlie the physics involved in designs of nuclear explosions, controlled nuclear energy, and nuclear fusion. The review then moves to focus on modern applicationsmore » of these concepts, including the basic concepts and diagnostics developed for the forensics of nuclear explosions, the nuclear diagnostics at the National Ignition Facility, nuclear reactor safeguards, and the detection of nuclear material production and trafficking. The review also summarizes recent developments in nuclear geophysics and nuclear medicine. The nuclear geophysics areas discussed include geo-chronology, nuclear logging for industry, the Oklo reactor, and geo-neutrinos. The section on nuclear medicine summarizes the critical advances in nuclear imaging, including PET and SPECT imaging, targeted radionuclide therapy, and the nuclear physics of medical isotope production. Lastly, each subfield discussed requires a review article unto itself, which is not the intention of the current review; rather, the current review is intended for readers who wish to get a broad understanding of applied nuclear physics.« less

Testing in Support of Fission Surface Power System Qualification

NASA Technical Reports Server (NTRS)

Houts, Mike; Bragg-Sitton, Shannon; Godfroy, Tom; Martin, Jim; Pearson, Boise; VanDyke, Melissa

2007-01-01

The strategy for qualifying a FSP system could have a significant programmatic impact. The US has not qualified a space fission power system since launch of the SNAP-10A in 1965. This paper explores cost-effective options for obtaining data that would be needed for flight qualification of a fission system. Qualification data could be obtained from both nuclear and non-nuclear testing. The ability to perform highly realistic nonnuclear testing has advanced significantly throughout the past four decades. Instrumented thermal simulators were developed during the 1970s and 1980s to assist in the development, operation, and assessment of terrestrial fission systems. Instrumented thermal simulators optimized for assisting in the development, operation, and assessment of modern FSP systems have been under development (and utilized) since 1998. These thermal simulators enable heat from fission to be closely mimicked (axial power profile, radial power profile, temperature, heat flux, etc.) and extensive data to be taken from the core region. For transient testing, pin power during a transient is calculated based on the reactivity feedback that would occur given measured values of test article temperature and/or dimensional changes. The reactivity feedback coefficients needed for the test are either calculated or measured using cold/warm zero-power criticals. In this way non-nuclear testing can be used to provide very realistic information related to nuclear operation. Non-nuclear testing can be used at all levels, including component, subsystem, and integrated system testing. FSP fuels and materials are typically chosen to ensure very high confidence in operation at design burnups, fluences, and temperatures. However, facilities exist (e.g. ATR, HFIR) for affordably performing in-pile fuel and materials irradiations, if such testing is desired. Ex-core materials and components (such as alternator materials, control drum drives, etc.) could be irradiated in university or DOE reactors to ensure adequate radiation resistance. Facilities also exist for performing warm and cold zero-power criticals.

77 FR 14445 - Leakage Tests on Packages for Shipment of Radioactive Material

Federal Register 2010, 2011, 2012, 2013, 2014

2012-03-09

... NUCLEAR REGULATORY COMMISSION [NRC-2011-0045] Leakage Tests on Packages for Shipment of..., ``Leakage Tests on Packages for Radioactive Material.'' ADDRESSES: You can access publicly available... Materials--Leakage Tests on Packages for Shipment'' approved February 1998. The NRC staff developed and...

Nuclear reference materials to meet the changing needs of the global nuclear community

DOE Office of Scientific and Technical Information (OSTI.GOV)

Martin, H.R.; Gradle, C.G.; Narayanan, U.I.

New Brunswick Laboratory (NBL) serves as the US Government`s Certifying Authority for nuclear reference materials and measurement calibration standards. In this role, NBL provides nuclear reference materials certified for chemical and/or isotopic compositions traceable to a nationally accepted, internationally compatible reference base. Emphasis is now changing as to the types of traceable nuclear reference materials needed as operations change within the Department of Energy (DOE) complex and at nuclear facilities around the world. Environmental and waste minimization issues, facilities and materials transitioning from processing to storage modes with corresponding changes in the types of measurements being performed, emphasis on requirementsmore » for characterization of waste materials, difficulties in transporting nuclear materials, and International factors, including International Atomic Energy Agency (IAEA) inspection of excess US nuclear materials, are all contributing influences. During these changing times, ft is critical that traceable reference materials be provided for calibration or validation of the performance of measurement systems. This paper will describe actions taken and planned to meet the changing reference material needs of the global nuclear community.« less

10 CFR 70.42 - Transfer of special nuclear material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Transfer of special nuclear material. 70.42 Section 70.42 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.42 Transfer of special...

10 CFR 74.17 - Special nuclear material physical inventory summary report.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Special nuclear material physical inventory summary report. 74.17 Section 74.17 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL General Reporting and Recordkeeping Requirements § 74.17 Special nuclear...

10 CFR 70.41 - Authorized use of special nuclear material.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Authorized use of special nuclear material. 70.41 Section 70.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.41 Authorized use of special...

10 CFR 70.41 - Authorized use of special nuclear material.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Authorized use of special nuclear material. 70.41 Section 70.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.41 Authorized use of special...

10 CFR 74.17 - Special nuclear material physical inventory summary report.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Special nuclear material physical inventory summary report. 74.17 Section 74.17 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL General Reporting and Recordkeeping Requirements § 74.17 Special nuclear...

10 CFR 11.15 - Application for special nuclear material access authorization.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 1 2013-01-01 2013-01-01 false Application for special nuclear material access authorization. 11.15 Section 11.15 Energy NUCLEAR REGULATORY COMMISSION CRITERIA AND PROCEDURES FOR DETERMINING ELIGIBILITY FOR ACCESS TO OR CONTROL OVER SPECIAL NUCLEAR MATERIAL Requirements for Special Nuclear Material...

10 CFR 74.17 - Special nuclear material physical inventory summary report.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Special nuclear material physical inventory summary report. 74.17 Section 74.17 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL General Reporting and Recordkeeping Requirements § 74.17 Special nuclear...

10 CFR 11.15 - Application for special nuclear material access authorization.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 1 2012-01-01 2012-01-01 false Application for special nuclear material access authorization. 11.15 Section 11.15 Energy NUCLEAR REGULATORY COMMISSION CRITERIA AND PROCEDURES FOR DETERMINING ELIGIBILITY FOR ACCESS TO OR CONTROL OVER SPECIAL NUCLEAR MATERIAL Requirements for Special Nuclear Material...

10 CFR 70.42 - Transfer of special nuclear material.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Transfer of special nuclear material. 70.42 Section 70.42 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.42 Transfer of special...

10 CFR 70.42 - Transfer of special nuclear material.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Transfer of special nuclear material. 70.42 Section 70.42 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.42 Transfer of special...

10 CFR 74.17 - Special nuclear material physical inventory summary report.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Special nuclear material physical inventory summary report. 74.17 Section 74.17 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL General Reporting and Recordkeeping Requirements § 74.17 Special nuclear...

10 CFR 70.41 - Authorized use of special nuclear material.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Authorized use of special nuclear material. 70.41 Section 70.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.41 Authorized use of special...

10 CFR 70.42 - Transfer of special nuclear material.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Transfer of special nuclear material. 70.42 Section 70.42 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.42 Transfer of special...

10 CFR 70.42 - Transfer of special nuclear material.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Transfer of special nuclear material. 70.42 Section 70.42 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.42 Transfer of special...

10 CFR 70.41 - Authorized use of special nuclear material.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Authorized use of special nuclear material. 70.41 Section 70.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.41 Authorized use of special...

10 CFR 70.41 - Authorized use of special nuclear material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Authorized use of special nuclear material. 70.41 Section 70.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Acquisition, Use and Transfer of Special Nuclear Material, Creditors' Rights § 70.41 Authorized use of special...

10 CFR 74.17 - Special nuclear material physical inventory summary report.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Special nuclear material physical inventory summary report. 74.17 Section 74.17 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL General Reporting and Recordkeeping Requirements § 74.17 Special nuclear...

10 CFR 11.15 - Application for special nuclear material access authorization.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Application for special nuclear material access authorization. 11.15 Section 11.15 Energy NUCLEAR REGULATORY COMMISSION CRITERIA AND PROCEDURES FOR DETERMINING ELIGIBILITY FOR ACCESS TO OR CONTROL OVER SPECIAL NUCLEAR MATERIAL Requirements for Special Nuclear Material...

10 CFR 11.15 - Application for special nuclear material access authorization.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 1 2011-01-01 2011-01-01 false Application for special nuclear material access authorization. 11.15 Section 11.15 Energy NUCLEAR REGULATORY COMMISSION CRITERIA AND PROCEDURES FOR DETERMINING ELIGIBILITY FOR ACCESS TO OR CONTROL OVER SPECIAL NUCLEAR MATERIAL Requirements for Special Nuclear Material...

10 CFR 11.15 - Application for special nuclear material access authorization.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 1 2014-01-01 2014-01-01 false Application for special nuclear material access authorization. 11.15 Section 11.15 Energy NUCLEAR REGULATORY COMMISSION CRITERIA AND PROCEDURES FOR DETERMINING ELIGIBILITY FOR ACCESS TO OR CONTROL OVER SPECIAL NUCLEAR MATERIAL Requirements for Special Nuclear Material...

Potential for recycling of slightly radioactive metals arising from decommissioning within nuclear sector in Slovakia.

PubMed

Hrncir, Tomas; Strazovec, Roman; Zachar, Matej

2017-09-07

The decommissioning of nuclear installations represents a complex process resulting in the generation of large amounts of waste materials containing various concentrations of radionuclides. Selection of an appropriate strategy of management of the mentioned materials strongly influences the effectiveness of decommissioning process keeping in mind safety, financial and other relevant aspects. In line with international incentives for optimization of radioactive material management, concepts of recycling and reuse of materials are widely discussed and applications of these concepts are analysed. Recycling of some portion of these materials within nuclear sector (e.g. scrap metals or concrete rubble) seems to be highly desirable from economical point of view and may lead to conserve some disposal capacity. However, detailed safety assessment along with cost/benefit calculations and feasibility study should be developed in order to prove the safety, practicality and cost effectiveness of possible recycling scenarios. Paper discussed the potential for recycling of slightly radioactive metals arising from decommissioning of NPPs within nuclear sector in Slovakia. Various available recycling scenarios are introduced and method for overall assessment of various recycling scenarios is outlined including the preliminary assessment of safety and financial aspects. Copyright © 2017 Elsevier Ltd. All rights reserved.

Development of a simple-material discrimination method with three plastic scintillator strips for visualizing nuclear reactors

NASA Astrophysics Data System (ADS)

Takamatsu, k.; Tanaka, h.; Shoji, d.

2012-04-01

The Fukushima Daiichi nuclear disaster is a series of equipment failures and nuclear meltdowns, following the T¯o hoku earthquake and tsunami on 11 March 2011. We present a new method for visualizing nuclear reactors. Muon radiography based on the multiple Coulomb scattering of cosmic-ray muons has been performed. In this work, we discuss experimental results obtained with a cost-effective simple detection system assembled with three plastic scintillator strips. Actually, we counted the number of muons that were not largely deflected by restricting the zenith angle in one direction to 0.8o. The system could discriminate Fe, Pb and C. Materials lighter than Pb can be also discriminated with this system. This method only resolves the average material distribution along the muon path. Therefore the user must make assumptions or interpretations about the structure, or must use more than one detector to resolve the three dimensional material distribution. By applying this method to time-dependent muon radiography, we can detect changes with time, rendering the method suitable for real-time monitoring applications, possibly providing useful information about the reaction process in a nuclear reactor such as burnup of fuels. In nuclear power technology, burnup (also known as fuel utilization) is a measure of how much energy is extracted from a primary nuclear fuel source. Monitoring the burnup of fuels as a nondestructive inspection technique can contribute to safer operation. In nuclear reactor, the total mass is conserved so that the system cannot be monitored by conventional muon radiography. A plastic scintillator is relatively small and easy to setup compared to a gas or layered scintillation system. Thus, we think this simple radiographic method has the potential to visualize a core directly in cases of normal operations or meltdown accidents. Finally, we considered only three materials as a first step in this work. Further research is required to improve the ability of imaging the material distribution in a mass-conserved system.

Recent progress in research on tungsten materials for nuclear fusion applications in Europe

NASA Astrophysics Data System (ADS)

Rieth, M.; Dudarev, S. L.; Gonzalez de Vicente, S. M.; Aktaa, J.; Ahlgren, T.; Antusch, S.; Armstrong, D. E. J.; Balden, M.; Baluc, N.; Barthe, M.-F.; Basuki, W. W.; Battabyal, M.; Becquart, C. S.; Blagoeva, D.; Boldyryeva, H.; Brinkmann, J.; Celino, M.; Ciupinski, L.; Correia, J. B.; De Backer, A.; Domain, C.; Gaganidze, E.; García-Rosales, C.; Gibson, J.; Gilbert, M. R.; Giusepponi, S.; Gludovatz, B.; Greuner, H.; Heinola, K.; Höschen, T.; Hoffmann, A.; Holstein, N.; Koch, F.; Krauss, W.; Li, H.; Lindig, S.; Linke, J.; Linsmeier, Ch.; López-Ruiz, P.; Maier, H.; Matejicek, J.; Mishra, T. P.; Muhammed, M.; Muñoz, A.; Muzyk, M.; Nordlund, K.; Nguyen-Manh, D.; Opschoor, J.; Ordás, N.; Palacios, T.; Pintsuk, G.; Pippan, R.; Reiser, J.; Riesch, J.; Roberts, S. G.; Romaner, L.; Rosiński, M.; Sanchez, M.; Schulmeyer, W.; Traxler, H.; Ureña, A.; van der Laan, J. G.; Veleva, L.; Wahlberg, S.; Walter, M.; Weber, T.; Weitkamp, T.; Wurster, S.; Yar, M. A.; You, J. H.; Zivelonghi, A.

2013-01-01

The current magnetic confinement nuclear fusion power reactor concepts going beyond ITER are based on assumptions about the availability of materials with extreme mechanical, heat, and neutron load capacity. In Europe, the development of such structural and armour materials together with the necessary production, machining, and fabrication technologies is pursued within the EFDA long-term fusion materials programme. This paper reviews the progress of work within the programme in the area of tungsten and tungsten alloys. Results, conclusions, and future projections are summarized for each of the programme's main subtopics, which are: (1) fabrication, (2) structural W materials, (3) W armour materials, and (4) materials science and modelling. It gives a detailed overview of the latest results on materials research, fabrication processes, joining options, high heat flux testing, plasticity studies, modelling, and validation experiments.

National Labs and Nuclear Emergency Response

NASA Astrophysics Data System (ADS)

Budil, Kimberly

2015-04-01

The DOE national laboratories, and in particular the three NNSA national security laboratories, have long supported a broad suite of national nuclear security missions for the U.S. government. The capabilities, infrastructure and base of expertise developed to support the U.S. nuclear weapons stockpile have been applied to such challenges as stemming nuclear proliferation, understanding the nuclear capabilities of adversaries, and assessing and countering nuclear threats including essential support to nuclear emergency response. This talk will discuss the programs that are underway at the laboratories and the essential role that science and technology plays therein. Nuclear scientists provide expertise, fundamental understanding of nuclear materials, processes and signatures, and tools and technologies to aid in the identification and mitigation of nuclear threats as well as consequence management. This talk will also discuss the importance of direct engagement with the response community, which helps to shape research priorities and to enable development of useful tools and techniques for responders working in the field. National Labs and Nuclear Emergency Response.

10 CFR 70.11 - Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory...

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission contracts. 70.11 Section 70.11 Energy NUCLEAR... using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission...

10 CFR 70.11 - Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory...

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission contracts. 70.11 Section 70.11 Energy NUCLEAR... using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission...

10 CFR 70.11 - Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory...

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission contracts. 70.11 Section 70.11 Energy NUCLEAR... using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission...

10 CFR 70.11 - Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory...

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission contracts. 70.11 Section 70.11 Energy NUCLEAR... using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission...

10 CFR 70.11 - Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory...

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission contracts. 70.11 Section 70.11 Energy NUCLEAR... using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission...

Thermal control of high energy nuclear waste, space option. [mathematical models

NASA Technical Reports Server (NTRS)

Peoples, J. A.

1979-01-01

Problems related to the temperature and packaging of nuclear waste material for disposal in space are explored. An approach is suggested for solving both problems with emphasis on high energy density waste material. A passive cooling concept is presented which utilized conduction rods that penetrate the inner core. Data are presented to illustrate the effectiveness of the rods and the limit of their capability. A computerized thermal model is discussed and developed for the cooling concept.

Basic Research Needs for Advanced Nuclear Systems. Report of the Basic Energy Sciences Workshop on Basic Research Needs for Advanced Nuclear Energy Systems, July 31-August 3, 2006

DOE Office of Scientific and Technical Information (OSTI.GOV)

Roberto, J.; Diaz de la Rubia, T.; Gibala, R.

2006-10-01

The global utilization of nuclear energy has come a long way from its humble beginnings in the first sustained nuclear reaction at the University of Chicago in 1942. Today, there are over 440 nuclear reactors in 31 countries producing approximately 16% of the electrical energy used worldwide. In the United States, 104 nuclear reactors currently provide 19% of electrical energy used nationally. The International Atomic Energy Agency projects significant growth in the utilization of nuclear power over the next several decades due to increasing demand for energy and environmental concerns related to emissions from fossil plants. There are 28 newmore » nuclear plants currently under construction including 10 in China, 8 in India, and 4 in Russia. In the United States, there have been notifications to the Nuclear Regulatory Commission of intentions to apply for combined construction and operating licenses for 27 new units over the next decade. The projected growth in nuclear power has focused increasing attention on issues related to the permanent disposal of nuclear waste, the proliferation of nuclear weapons technologies and materials, and the sustainability of a once-through nuclear fuel cycle. In addition, the effective utilization of nuclear power will require continued improvements in nuclear technology, particularly related to safety and efficiency. In all of these areas, the performance of materials and chemical processes under extreme conditions is a limiting factor. The related basic research challenges represent some of the most demanding tests of our fundamental understanding of materials science and chemistry, and they provide significant opportunities for advancing basic science with broad impacts for nuclear reactor materials, fuels, waste forms, and separations techniques. Of particular importance is the role that new nanoscale characterization and computational tools can play in addressing these challenges. These tools, which include DOE synchrotron X-ray sources, neutron sources, nanoscale science research centers, and supercomputers, offer the opportunity to transform and accelerate the fundamental materials and chemical sciences that underpin technology development for advanced nuclear energy systems. The fundamental challenge is to understand and control chemical and physical phenomena in multi-component systems from femto-seconds to millennia, at temperatures to 1000?C, and for radiation doses to hundreds of displacements per atom (dpa). This is a scientific challenge of enormous proportions, with broad implications in the materials science and chemistry of complex systems. New understanding is required for microstructural evolution and phase stability under relevant chemical and physical conditions, chemistry and structural evolution at interfaces, chemical behavior of actinide and fission-product solutions, and nuclear and thermomechanical phenomena in fuels and waste forms. First-principles approaches are needed to describe f-electron systems, design molecules for separations, and explain materials failure mechanisms. Nanoscale synthesis and characterization methods are needed to understand and design materials and interfaces with radiation, temperature, and corrosion resistance. Dynamical measurements are required to understand fundamental physical and chemical phenomena. New multiscale approaches are needed to integrate this knowledge into accurate models of relevant phenomena and complex systems across multiple length and time scales.« less

Detection of special nuclear materials with the associate particle technique

NASA Astrophysics Data System (ADS)

Carasco, Cédric; Deyglun, Clément; Pérot, Bertrand; Eléon, Cyrille; Normand, Stéphane; Sannié, Guillaume; Boudergui, Karim; Corre, Gwenolé; Konzdrasovs, Vladimir; Pras, Philippe

2013-04-01

In the frame of the French trans-governmental R&D program against chemical, biological, radiological, nuclear and explosives (CBRN-E) threats, CEA is studying the detection of Special Nuclear Materials (SNM) by neutron interrogation with fast neutrons produced by an associated particle sealed tube neutron generator. The deuterium-tritium fusion reaction produces an alpha particle and a 14 MeV neutron almost back to back, allowing tagging neutron emission both in time and direction with an alpha particle position-sensitive sensor embedded in the generator. Fission prompt neutrons and gamma rays induced by tagged neutrons which are tagged by an alpha particle are detected in coincidence with plastic scintillators. This paper presents numerical simulations performed with the MCNP-PoliMi Monte Carlo computer code and with post processing software developed with the ROOT data analysis package. False coincidences due to neutron and photon scattering between adjacent detectors (cross talk) are filtered out to increase the selectivity between nuclear and benign materials. Accidental coincidences, which are not correlated to an alpha particle, are also taken into account in the numerical model, as well as counting statistics, and the time-energy resolution of the data acquisition system. Such realistic calculations show that relevant quantities of SNM (few kg) can be distinguished from cargo and shielding materials in 10 min acquisitions. First laboratory tests of the system under development in CEA laboratories are also presented.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

This document is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Winstanley, J. L.

In August 1945, U.S. Navy Captain William Parsons served as the weaponeer aboard the Enola Gay for the mission to Hiroshima (Shelton 1988). In view of the fact that four B-29s had crashed and burned on takeoff from Tinian the night before, Captain Parsons made the decision to arm the gun-type weapon after takeoff for safety reasons (15 kilotons of TNT equivalent). Although he had no control over the success of the takeoff, he could prevent the possibility of a nuclear detonation on Tinian by controlling what we now call the nuclear explosive. As head of the Ordnance Division atmore » Los Alamos and a former gunnery officer, Captain Parsons clearly understood the role of safety in his work. The advent of the pre-assembled implosion weapon where the high explosive and nuclear materials are always in an intimate configuration meant that nuclear explosive safety became a reality at a certain point in development and production not just at the time of delivery by the military. This is the only industry where nuclear materials are intentionally put in contact with high explosives. The agency of the U.S. Government responsible for development and production of U.S. nuclear weapons is the Department of Energy (DOE) (and its predecessor agencies). This paper will be limited to nuclear explosive safety as it is currently practiced within the DOE nuclear weapons« less

Class notes from the first international training course on the physical protection of nuclear facilities and materials

DOE Office of Scientific and Technical Information (OSTI.GOV)

Herrington, P.B.

1979-05-01

The International Training Course on Physical Protection of Nuclear Facilities and Materials was intended for representatives from the developing countries who are responsible for preparing regulations and designing and assessing physical protection systems. The first part of the course consists of lectures on the objectives, organizational characteristics, and licensing and regulations requirements of a state system of physical protection. Since the participants may have little experience in nuclear energy, background information is provided on the topics of nuclear materials, radiation hazards, reactor systems, and reactor operations. Transportation of nuclear materials is addressed and emphasis is placed on regulations. Included inmore » these discussions are presentations by guest speakers from countries outside the United States of America who present their countries' threat to nuclear facilities. Effectiveness evaluation methodology is introduced to the participants by means of instructions which teach them how to use logic trees and the EASI (Estimate of Adversary Sequence Interruption) program. The following elements of a physical protection system are discussed: barriers, protective force, intrusion detection systems, communications, and entry-control systems. Total systems concepts of physical protection system design are emphasized throughout the course. Costs, manpower/technology trade-offs, and other practical considerations are discussed. Approximately one-third of the course is devoted to practical exercises during which the attendees participatein problem solving. A hypothetical nuclear facility is introduced, and the attendees participate in the conceptual design of a physical protection system for the facility.« less

Proliferation of Nuclear Weapons: Opportunities for Control and Abolition

PubMed Central

Sidel, Victor W.; Levy, Barry S.

2007-01-01

Nuclear weapons pose a particularly destructive threat. Prevention of the proliferation and use of nuclear weapons is urgently important to public health. “Horizontal” proliferation refers to nation-states or nonstate entities that do not have, but are acquiring, nuclear weapons or developing the capability and materials for producing them. “Vertical” proliferation refers to nation-states that do possess nuclear weapons and are increasing their stockpiles of these weapons, improving the technical sophistication or reliability of their weapons, or developing new weapons. Because nation-states or other entities that wish to use or threaten to use nuclear weapons need methods for delivering those weapons, proliferation of delivery mechanisms must also be prevented. Controlling proliferation—and ultimately abolishing nuclear weapons—involves national governments, intergovernmental organizations, nongovernmental and professional organizations, and society at large. PMID:17666690

Taking Steps to Protect Against the Insider Threat

DOE Office of Scientific and Technical Information (OSTI.GOV)

Pope, Noah Gale; Williams, Martha; Lewis, Joel

2015-10-16

Research reactors are required (in accordance with the Safeguards Agreement between the State and the IAEA) to maintain a system of nuclear material accounting and control for reporting quantities of nuclear material received, shipped, and held on inventory. Enhancements to the existing accounting and control system can be made at little additional cost to the facility, and these enhancements can make nuclear material accounting and control useful for nuclear security. In particular, nuclear material accounting and control measures can be useful in protecting against an insider who is intent on unauthorized removal or misuse of nuclear material or misuse ofmore » equipment. An enhanced nuclear material accounting and control system that responds to nuclear security is described in NSS-25G, Use of Nuclear Material Accounting and Control for Nuclear Security Purposes at Facilities, which is scheduled for distribution by the IAEA Department of Nuclear Security later this year. Accounting and control measures that respond to the insider threat are also described in NSS-33, Establishing a System for Control of Nuclear Material for Nuclear Security Purposes at a Facility During Storage, Use and Movement, and in NSS-41, Preventive and Protective Measures against Insider Threats (originally issued as NSS-08), which are available in draft form. This paper describes enhancements to existing material control and accounting systems that are specific to research reactors, and shows how they are important to nuclear security and protecting against an insider.« less

10 CFR 70.20 - General license to own special nuclear material.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false General license to own special nuclear material. 70.20 Section 70.20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20 General license to own special nuclear material. A general license is...

10 CFR 70.20 - General license to own special nuclear material.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false General license to own special nuclear material. 70.20 Section 70.20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20 General license to own special nuclear material. A general license is...

10 CFR 70.20 - General license to own special nuclear material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false General license to own special nuclear material. 70.20 Section 70.20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20 General license to own special nuclear material. A general license is...

10 CFR 110.9 - List of Nuclear Material under NRC export licensing authority.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false List of Nuclear Material under NRC export licensing authority. 110.9 Section 110.9 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL General Provisions § 110.9 List of Nuclear Material under NRC export licensing...

10 CFR 110.9 - List of Nuclear Material under NRC export licensing authority.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false List of Nuclear Material under NRC export licensing authority. 110.9 Section 110.9 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL General Provisions § 110.9 List of Nuclear Material under NRC export licensing...

10 CFR 70.20 - General license to own special nuclear material.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false General license to own special nuclear material. 70.20 Section 70.20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20 General license to own special nuclear material. A general license is...

10 CFR 110.9 - List of Nuclear Material under NRC export licensing authority.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false List of Nuclear Material under NRC export licensing authority. 110.9 Section 110.9 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL General Provisions § 110.9 List of Nuclear Material under NRC export licensing...

10 CFR 70.20 - General license to own special nuclear material.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false General license to own special nuclear material. 70.20 Section 70.20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20 General license to own special nuclear material. A general license is...

10 CFR 110.9 - List of Nuclear Material under NRC export licensing authority.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false List of Nuclear Material under NRC export licensing authority. 110.9 Section 110.9 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL General Provisions § 110.9 List of Nuclear Material under NRC export licensing...

10 CFR 110.9 - List of Nuclear Material under NRC export licensing authority.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false List of Nuclear Material under NRC export licensing authority. 110.9 Section 110.9 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL General Provisions § 110.9 List of Nuclear Material under NRC export licensing...

Fourth Collaborative Materials Exercise of the Nuclear Forensics International Technical Working Group

DOE Office of Scientific and Technical Information (OSTI.GOV)

Schwantes, J. M.; Marsden, O.; Reilly, D.

Abstract The Nuclear Forensics International Technical Working Group is a community of nuclear forensic practitioners who respond to incidents involving nuclear and other radioactive material out of regulatory control. The Group is dedicated to advancing nuclear forensic science in part through periodic participation in materials exercises. The Group completed its fourth Collaborative Materials Exercise in 2015 in which laboratories from 15 countries and one multinational organization analyzed three samples of special nuclear material in support of a mock nuclear forensic investigation. This special section of the Journal for Radioanalytical and Nuclear Chemistry is devoted to summarizing highlights from this exercise.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Doyle, Jamie L.; Kuhn, Kevin John; Byerly, Benjamin

Nuclear forensic publications, performance tests, and research and development efforts typically target the bulk global inventory of intentionally safeguarded materials, such as plutonium (Pu) and uranium (U). Other materials, such as neptunium (Np), pose a nuclear security risk as well. Trafficking leading to recovery of an interdicted Np sample is a realistic concern especially for materials originating in countries that reprocesses fuel. Using complementary forensic methods, potential signatures for an unknown Np oxide sample were investigated. Measurement results were assessed against published Np processes to present hypotheses as to the original intended use, method of production, and origin for thismore » Np oxide.« less

New Brunswick Laboratory: Progress report, October 1987--September 1988

DOE Office of Scientific and Technical Information (OSTI.GOV)

Not Available

NBL has been tasked by the DOE Office of Safeguards and Security, Defense Programs (OSS/DP) to assure the application of accurate and reliable measurement technology for the safeguarding of special nuclear materials. NBL is fulfilling its mission responsibilities by identifying and addressing the measurement and measurement-related needs of the nuclear material safeguards community. These responsibilities are being addressed by activities in the following program areas: (1) reference and calibration materials, (2) measurement development, (3) measurement services, (4) measurement evaluation, (5) safeguards assessment, and (6) site-specific assistance. Highlights of each of these programs areas are provided in this summary.

Development of Nanomaterials for Nuclear Energetics

NASA Astrophysics Data System (ADS)

Petrunin, V. F.

Structure and properties peculiarities of the nanocrystalline powders give the opportunity to design new and to develop a modernization of nuclear energy industry materials. It was shown experimentally, that addition of 5-10% uranium dioxide nanocrystalline powder to traditional coarse powder allows to decrease the sintering temperature or to increase the fuel tablets size of grain. Similar perspectives for the technology of neutron absorbing tablets of control-rod modernization are shown by nanopowder of dysprosium hafnate changing instead now using boron carbide. It is powders in nanocrystalline state get an opportunity to sinter them and to receive compact tablet with 8,2-8,4 g/cm2 density for automatic defence system of nuclear reactor. Resource of dysprosium hafnate ceramics can be 18-20 years instead 4-5 years for boron carbide. To step up the radiation-damage stability of fuel element jacket material was suggested to strengthen a heat-resistant ferrite-martensite steel by Y2O3 nanocrystalline powder addition. Nanopowder with size of particles 560 nm and crystallite size 9 nm was prepeared by chemical coprecipitation method. To make lighter the container for transport and provisional disposal of exposed fuel from nuclear reactor a new boron-aluminium alloy called as boral was developed. This composite armed with nanopowders of boron-containing materials and heavy metals oxides can replace succesburnt-up corrosion-resistant steels.

Nuclear reference materials to meet the changing needs of the global nuclear community

DOE Office of Scientific and Technical Information (OSTI.GOV)

Martin, H.R.; Gradle, C.G.; Narayanan, U.I.

New Brunswick Laboratory (NBL) serves as the U.S. Government`s certifying authority for nuclear reference materials and measurement calibration standards. In this role, NBL provides nuclear reference materials certified for chemical and/or isotopic compositions traceable to a nationally accepted, internationally compatible reference base. Emphasis is now changing as to the types of traceable nuclear reference materials needed as operations change within the Department of Energy complex and at nuclear facilities around the world. New challenges include: environmental and waste minimization issues, facilities and materials transitioning from processing to storage modes with corresponding changes in the types of measurements being performed, emphasismore » on requirements for characterization of waste materials, and difficulties in transporting nuclear materials and international factors, including IAEA influences. During these changing times, it is critical that traceable reference materials be provided for calibration or validation of the performance of measurement systems. This paper will describe actions taken and planned to meet the changing reference material needs of the global nuclear community.« less

Structural materials issues for the next generation fission reactors

NASA Astrophysics Data System (ADS)

Chant, I.; Murty, K. L.

2010-09-01

Generation-IV reactor design concepts envisioned thus far cater to a common goal of providing safer, longer lasting, proliferation-resistant, and economically viable nuclear power plants. The foremost consideration in the successful development and deployment of Gen-W reactor systems is the performance and reliability issues involving structural materials for both in-core and out-of-core applications. The structural materials need to endure much higher temperatures, higher neutron doses, and extremely corrosive environments, which are beyond the experience of the current nuclear power plants. Materials under active consideration for use in different reactor components include various ferritic/martensitic steels, austenitic stainless steels, nickel-base superalloys, ceramics, composites, etc. This article addresses the material requirements for these advanced fission reactor types, specifically addressing structural materials issues depending on the specific application areas.

Dynamic nuclear polarization solid-state NMR in heterogeneous catalysis research

DOE PAGES

Kobayashi, Takeshi; Perras, Frédéric A.; Slowing, Igor I.; ...

2015-10-20

In this study, a revolution in solid-state nuclear magnetic resonance (SSNMR) spectroscopy is taking place, attributable to the rapid development of high-field dynamic nuclear polarization (DNP), a technique yielding sensitivity improvements of 2–3 orders of magnitude. This higher sensitivity in SSNMR has already impacted materials research, and the implications of new methods on catalytic sciences are expected to be profound.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Barty, Christopher P.J.

Lasers and laser-based sources are now routinely used to control and manipulate nuclear processes, e.g. fusion, fission and resonant nuclear excitation. Two such “nuclear photonics” activities with the potential for profound societal impact will be reviewed in this presentation: the pursuit of laser-driven inertial confinement fusion at the National Ignition Facility and the development of laser-based, mono-energetic gamma-rays for isotope-specific detection, assay and imaging of materials.

Fundamental considerations in dynamic fracture in nuclear materials

NASA Astrophysics Data System (ADS)

Cady, Carl; Eastwood, David; Bourne, Neil; Pei, Ruizhi; Mummery, Paul; Rau, Christoph

2017-06-01

The structural integrity of components used in nuclear power plants is the biggest concern of operators. A diverse range of materials, loading, prior histories and environmental conditions, leads to a complex operating environment. An experimental technique has been developed to characterize brittle materials and using linear elastic fracture mechanics, has given accurate measurements of the fracture toughness of materials. X-ray measurements were used to track the crack front as a function of loading parameters as well as determine the crack surface area as loads increased. This X-ray tomographic study of dynamic fracture in beryllium indicates the onset of damage within the target as load is increased. Similarly, measurements on nuclear graphite were conducted to evaluate the technique. This new, quantitative information obtained using the X-ray techniques has shown application in other materials. These materials exhibited a range of brittle and ductile responses that will test our modelling schemes for fracture. Further visualization of crack front advance and the correlated strain fields that are generated during the experiment for the two distinct deformation processes provide a vital step in validating new multiscale predicative modelling.

10 CFR Appendix M to Part 110 - Categorization of Nuclear Material d

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Categorization of Nuclear Material d M Appendix M to Part 110 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Pt. 110, App. M Appendix M to Part 110—Categorization of Nuclear Material d [From IAEA INFCIRC/225...

10 CFR 70.20a - General license to possess special nuclear material for transport.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false General license to possess special nuclear material for transport. 70.20a Section 70.20a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20a General license to possess special nuclear material for...

10 CFR Appendix M to Part 110 - Categorization of Nuclear Material d

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Categorization of Nuclear Material d M Appendix M to Part 110 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Pt. 110, App. M Appendix M to Part 110—Categorization of Nuclear Material d [From IAEA INFCIRC/225...

10 CFR 110.21 - General license for the export of special nuclear material.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false General license for the export of special nuclear material. 110.21 Section 110.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Licenses § 110.21 General license for the export of special nuclear material. (a...

10 CFR 110.21 - General license for the export of special nuclear material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false General license for the export of special nuclear material. 110.21 Section 110.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Licenses § 110.21 General license for the export of special nuclear material. (a...

10 CFR 70.20a - General license to possess special nuclear material for transport.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false General license to possess special nuclear material for transport. 70.20a Section 70.20a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20a General license to possess special nuclear material for...

10 CFR 70.20a - General license to possess special nuclear material for transport.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false General license to possess special nuclear material for transport. 70.20a Section 70.20a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20a General license to possess special nuclear material for...

10 CFR 110.21 - General license for the export of special nuclear material.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false General license for the export of special nuclear material. 110.21 Section 110.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Licenses § 110.21 General license for the export of special nuclear material. (a...

10 CFR 70.20a - General license to possess special nuclear material for transport.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false General license to possess special nuclear material for transport. 70.20a Section 70.20a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20a General license to possess special nuclear material for...

10 CFR Appendix M to Part 110 - Categorization of Nuclear Material d

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Categorization of Nuclear Material d M Appendix M to Part 110 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Pt. 110, App. M Appendix M to Part 110—Categorization of Nuclear Material d [From IAEA INFCIRC/225...

10 CFR 70.20a - General license to possess special nuclear material for transport.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false General license to possess special nuclear material for transport. 70.20a Section 70.20a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL General Licenses § 70.20a General license to possess special nuclear material for...

10 CFR 110.21 - General license for the export of special nuclear material.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false General license for the export of special nuclear material. 110.21 Section 110.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Licenses § 110.21 General license for the export of special nuclear material. (a...

10 CFR 110.21 - General license for the export of special nuclear material.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false General license for the export of special nuclear material. 110.21 Section 110.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Licenses § 110.21 General license for the export of special nuclear material. (a...

10 CFR Appendix M to Part 110 - Categorization of Nuclear Material d

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Categorization of Nuclear Material d M Appendix M to Part 110 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Pt. 110, App. M Appendix M to Part 110—Categorization of Nuclear Material d [From IAEA INFCIRC/225...

10 CFR Appendix M to Part 110 - Categorization of Nuclear Material d

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Categorization of Nuclear Material d M Appendix M to Part 110 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Pt. 110, App. M Appendix M to Part 110—Categorization of Nuclear Material d [From IAEA INFCIRC/225...

Management of the aging of critical safety-related concrete structures in light-water reactor plants

DOE Office of Scientific and Technical Information (OSTI.GOV)

Naus, D.J.; Oland, C.B.; Arndt, E.G.

1990-01-01

The Structural Aging Program has the overall objective of providing the USNRC with an improved basis for evaluating nuclear power plant safety-related structures for continued service. The program consists of a management task and three technical tasks: materials property data base, structural component assessment/repair technology, and quantitative methodology for continued-service determinations. Objectives, accomplishments, and planned activities under each of these tasks are presented. Major program accomplishments include development of a materials property data base for structural materials as well as an aging assessment methodology for concrete structures in nuclear power plants. Furthermore, a review and assessment of inservice inspection techniquesmore » for concrete materials and structures has been complete, and work on development of a methodology which can be used for performing current as well as reliability-based future condition assessment of concrete structures is well under way. 43 refs., 3 tabs.« less

10 CFR 1.42 - Office of Nuclear Material Safety and Safeguards.

Code of Federal Regulations, 2014 CFR

2014-01-01

... responsible for regulation and licensing of recycling technologies intended to reduce the amount of waste to... an appropriate regulatory framework, in recycling during development, demonstration, and deployment of new advanced recycling technologies that recycle nuclear fuel in a manner which does not produce...

10 CFR 1.42 - Office of Nuclear Material Safety and Safeguards.

Code of Federal Regulations, 2013 CFR

2013-01-01

... responsible for regulation and licensing of recycling technologies intended to reduce the amount of waste to... an appropriate regulatory framework, in recycling during development, demonstration, and deployment of new advanced recycling technologies that recycle nuclear fuel in a manner which does not produce...

10 CFR 1.42 - Office of Nuclear Material Safety and Safeguards.

Code of Federal Regulations, 2011 CFR

2011-01-01

... responsible for regulation and licensing of recycling technologies intended to reduce the amount of waste to... an appropriate regulatory framework, in recycling during development, demonstration, and deployment of new advanced recycling technologies that recycle nuclear fuel in a manner which does not produce...

10 CFR 1.42 - Office of Nuclear Material Safety and Safeguards.

Code of Federal Regulations, 2010 CFR

2010-01-01

... responsible for regulation and licensing of recycling technologies intended to reduce the amount of waste to... an appropriate regulatory framework, in recycling during development, demonstration, and deployment of new advanced recycling technologies that recycle nuclear fuel in a manner which does not produce...

10 CFR 1.42 - Office of Nuclear Material Safety and Safeguards.

Code of Federal Regulations, 2012 CFR

2012-01-01

... responsible for regulation and licensing of recycling technologies intended to reduce the amount of waste to... an appropriate regulatory framework, in recycling during development, demonstration, and deployment of new advanced recycling technologies that recycle nuclear fuel in a manner which does not produce...

Background studies in support of a feasibility assessment on the use of copper-base materials for nuclear waste packages in a repository in tuff

DOE Office of Scientific and Technical Information (OSTI.GOV)

Van Konynenburg, R.A.; Kundig, K.J.A.; Lyman, W.S.

1990-06-01

This report combines six work units performed in FY`85--86 by the Copper Development Association and the International Copper Research Association under contract with the University of California. The work includes literature surveys and state-of-the-art summaries on several considerations influencing the feasibility of the use of copper-base materials for fabricating high-level nuclear waste packages for the proposed repository in tuff rock at Yucca Mountain, Nevada. The general conclusion from this work was that copper-base materials are viable candidates for inclusion in the materials selection process for this application. 55 refs., 48 figs., 22 tabs.

Studies of neutron and proton nuclear activation in low-Earth orbit

NASA Technical Reports Server (NTRS)

Laird, C. E.

1982-01-01

The expected induced radioactivity of experimental material in low Earth orbit was studied for characteristics of activating particles such as cosmic rays, high energy Earth albedo neutrons, trapped protons, and secondary protons and neutrons. The activation cross sections for the production of long lived radioisotopes and other existing nuclear data appropriate to the study of these reactions were compiled. Computer codes which are required to calculate the expected activation of orbited materials were developed. The decreased computer code used to predict the activation of trapped protons of materials placed in the expected orbits of LDEF and Spacelab II. Techniques for unfolding the fluxes of activating particles from the measured activation of orbited materials are examined.

48 CFR 904.401 - Definitions.

Code of Federal Regulations, 2010 CFR

2010-10-01

... for access to, or control over, special nuclear material. Applicant means an individual who has... facility is eligible to access, produce, use or store classified information, or special nuclear material... of special nuclear material; or use of special nuclear material in the production of energy, but...

Nuclear Materials Science

NASA Astrophysics Data System (ADS)

Whittle, Karl

2016-06-01

Concerns around global warming have led to a nuclear renaissance in many countries, meanwhile the nuclear industry is warning already of a need to train more nuclear engineers and scientists, who are needed in a range of areas from healthcare and radiation detection to space exploration and advanced materials as well as for the nuclear power industry. Here Karl Whittle provides a solid overview of the intersection of nuclear engineering and materials science at a level approachable by advanced students from materials, engineering and physics. The text explains the unique aspects needed in the design and implementation of materials for use in demanding nuclear settings. In addition to material properties and their interaction with radiation the book covers a range of topics including reactor design, fuels, fusion, future technologies and lessons learned from past incidents. Accompanied by problems, videos and teaching aids the book is suitable for a course text in nuclear materials and a reference for those already working in the field.

DEVELOPMENT, INSTALLATION AND OPERATION OF THE MPC&A OPERATIONS MONITORING (MOM) SYSTEM AT THE JOINT INSTITUTE FOR NUCLEAR RESEARCH (JINR) DUBNA, RUSSIA

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kartashov,V.V.; Pratt,W.; Romanov, Y.A.

The Material Protection, Control and Accounting (MPC&A) Operations Monitoring (MOM) systems handling at the International Intergovernmental Organization - Joint Institute for Nuclear Research (JINR) is described in this paper. Category I nuclear material (plutonium and uranium) is used in JINR research reactors, facilities and for scientific and research activities. A monitoring system (MOM) was installed at JINR in April 2003. The system design was based on a vulnerability analysis, which took into account the specifics of the Institute. The design and installation of the MOM system was a collaborative effort between JINR, Brookhaven National Laboratory (BNL) and the U.S. Departmentmore » of Energy (DOE). Financial support was provided by DOE through BNL. The installed MOM system provides facility management with additional assurance that operations involving nuclear material (NM) are correctly followed by the facility personnel. The MOM system also provides additional confidence that the MPC&A systems continue to perform effectively.« less

The Infrastructure Necessary to Support a Sustainable Material Protection, Control and Accounting (MPC&A) Program in Russia

DOE Office of Scientific and Technical Information (OSTI.GOV)

Bachner, Katherine M.; Mladineo, Stephen V.

The NNSA Material Protection, Control, and Accounting (MPC&A) program has been engaged for fifteen years in upgrading the security of nuclear materials in Russia. Part of the effort has been to establish the conditions necessary to ensure the long-term sustainability of nuclear security. A sustainable program of nuclear security requires the creation of an indigenous infrastructure, starting with sustained high level government commitment. This includes organizational development, training, maintenance, regulations, inspections, and a strong nuclear security culture. The provision of modern physical protection, control, and accounting equipment to the Russian Federation alone is not sufficient. Comprehensive infrastructure projects support themore » Russian Federation's ability to maintain the risk reduction achieved through upgrades to the equipment. To illustrate the contributions to security, and challenges of implementation, this paper discusses the history and next steps for an indigenous Tamper Indication Device (TID) program, and a Radiation Portal Monitoring (RPM) program.« less

Ablation study of tungsten-based nuclear thermal rocket fuel

NASA Astrophysics Data System (ADS)

Smith, Tabitha Elizabeth Rose

The research described in this thesis has been performed in order to support the materials research and development efforts of NASA Marshall Space Flight Center (MSFC), of Tungsten-based Nuclear Thermal Rocket (NTR) fuel. The NTR was developed to a point of flight readiness nearly six decades ago and has been undergoing gradual modification and upgrading since then. Due to the simplicity in design of the NTR, and also in the modernization of the materials fabrication processes of nuclear fuel since the 1960's, the fuel of the NTR has been upgraded continuously. Tungsten-based fuel is of great interest to the NTR community, seeking to determine its advantages over the Carbide-based fuel of the previous NTR programs. The materials development and fabrication process contains failure testing, which is currently being conducted at MSFC in the form of heating the material externally and internally to replicate operation within the nuclear reactor of the NTR, such as with hot gas and RF coils. In order to expand on these efforts, experiments and computational studies of Tungsten and a Tungsten Zirconium Oxide sample provided by NASA have been conducted for this dissertation within a plasma arc-jet, meant to induce ablation on the material. Mathematical analysis was also conducted, for purposes of verifying experiments and making predictions. The computational method utilizes Anisimov's kinetic method of plasma ablation, including a thermal conduction parameter from the Chapman Enskog expansion of the Maxwell Boltzmann equations, and has been modified to include a tangential velocity component. Experimental data matches that of the computational data, in which plasma ablation at an angle shows nearly half the ablation of plasma ablation at no angle. Fuel failure analysis of two NASA samples post-testing was conducted, and suggestions have been made for future materials fabrication processes. These studies, including the computational kinetic model at an angle and the ablation of the NASA sample, could be applied to an atmospheric reentry body, reentering at a ballistic trajectory at hypersonic velocities.

Termination of Safeguards for Accountable Nuclear Materials at the Idaho National Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

Michael Holzemer; Alan Carvo

2012-04-01

Termination of safeguards ends requirements of Nuclear Material Control and Accountability (MC&A) and thereby removes the safeguards basis for applying physical protection requirements for theft and diversion of nuclear material, providing termination requirements are met as described. Department of Energy (DOE) M 470.4 6 (Nuclear Material Control and Accountability [8/26/05]) stipulates: 1. Section A, Chapter I (1)( q) (1): Safeguards can be terminated on nuclear materials provided the following conditions are met: (a) 'If the material is special nuclear material (SNM) or protected as SNM, it must be attractiveness level E and have a measured value.' (b) 'The material hasmore » been determined by DOE line management to be of no programmatic value to DOE.' (c) 'The material is transferred to the control of a waste management organization where the material is accounted for and protected in accordance with waste management regulations. The material must not be collocated with other accountable nuclear materials.' Requirements for safeguards termination depend on the safeguards attractiveness levels of the material. For attractiveness level E, approval has been granted from the DOE Idaho Operations Office (DOE ID) to Battelle Energy Alliance, LLC (BEA) Safeguards and Security (S&S). In some cases, it may be necessary to dispose of nuclear materials of attractiveness level D or higher. Termination of safeguards for such materials must be approved by the Departmental Element (this is the DOE Headquarters Office of Nuclear Energy) after consultation with the Office of Security.« less

The Interface of Safety and Security in Transport: A Regional Perspective

DOE Office of Scientific and Technical Information (OSTI.GOV)

Welch, Tim; Duhamel, David A; Nandakumar, A. N.

Security of nuclear and other radioactive material in transport continues to be a challenge for States that are working on strengthening their nuclear security regime. One reason for this is that State regulatory agencies and other organizations lack the resources and trained personnel to dedicate to this field. For over 50 years safety has been a major focus in the use, storage and transport of radioactive material. Only recently, since the late 1990s, has dedicated focus been given to the field of security. One way to assist States to advance nuclear security is to reach out to safety workers (regulators,more » inspectors, and safety compliance personnel) and showcase the need to better integrate safety and security practices. A recent IAEA regional workshop in Bangkok, Thailand (June 2015) yielded profound results when subject matter experts lectured on both the safety and the security of radioactive material in transport. These experts presented and discussed experiences and best practices for: 1) developing and implementing safety requirements and security recommendations for radioactive material in transport; 2) national and international cooperation; and 3) preventing shipment delays/denials of radioactive material. The workshop participants, who were predominantly from safety organizations, shared that they received the following from this event: 1. A clear understanding of the objectives of the IAEA safety requirements and security recommendations for radioactive material in transport. 2. A general understanding of and appreciation for the similarities and differences between safety requirements and security recommendations for radioactive material in transport. 3. A greater appreciation of the interface between transport safety and security and potential impacts of this interface on the efforts to strengthen the compliance assurance regime for the safe transport of radioactive material. 4. A general understanding of assessing the transport security scenarios and developing transport security plans. Many participants also reported their appreciation of the workshop exercises that specifically focused on practical aspects of safety and security of transport of radioactive material. These workshop outcomes highlight the important role professionals can offer when they receive additional safety training and education for radioactive material in transport. Moreover, these professionals can help to increase capacity in countries with developing nuclear security regimes. This paper explores workshop outcomes and transportation regulations and guidelines for radioactive material.« less

Believing Your Eyes: Strengthening the Reliability of Tags and Seals

DOE Office of Scientific and Technical Information (OSTI.GOV)

Brim, Cornelia P.; Denlinger, Laura S.

2013-07-01

NNSA’s Office of Nonproliferation and International Security (NIS) is working together with scientific experts at the DOE national laboratories to develop the tools needed to safeguard and secure nuclear material from diversion, theft, and sabotage--tasks critical to support future arms control treaties that may involve the new challenge of monitoring nuclear weapons dismantlement. Use of optically stimulated luminescent material is one method to enhance the security and robustness of existing tamper indicating devices such as tags and seals.

Enterprise SRS: leveraging ongoing operations to advance nuclear fuel cycles research and development programs

DOE Office of Scientific and Technical Information (OSTI.GOV)

Murray, A.M.; Marra, J.E.; Wilmarth, W.R.

2013-07-01

The Savannah River Site (SRS) is re-purposing its vast array of assets (including H Canyon - a nuclear chemical separation plant) to solve issues regarding advanced nuclear fuel cycle technologies, nuclear materials processing, packaging, storage and disposition. The vehicle for this transformation is Enterprise SRS which presents a new, radical view of SRS as a united endeavor for 'all things nuclear' as opposed to a group of distinct and separate entities with individual missions and organizations. Key among the Enterprise SRS strategic initiatives is the integration of research into SRS facilities but also in other facilities in conjunction with on-goingmore » missions to provide researchers from other national laboratories, academic institutions, and commercial entities the opportunity to demonstrate their technologies in a relevant environment and scale prior to deployment. To manage that integration of research demonstrations into site facilities, a center for applied nuclear materials processing and engineering research has been established in SRS.« less

48 CFR 970.4402-4 - Nuclear material transfers.

Code of Federal Regulations, 2014 CFR

2014-10-01

... 48 Federal Acquisition Regulations System 5 2014-10-01 2014-10-01 false Nuclear material transfers... 970.4402-4 Nuclear material transfers. (a) Management and operating contractors, in preparing... nuclear material, shall be required to assure that each such subcontract or agreement contains a— (1...

48 CFR 970.4402-4 - Nuclear material transfers.

Code of Federal Regulations, 2011 CFR

2011-10-01

... 48 Federal Acquisition Regulations System 5 2011-10-01 2011-10-01 false Nuclear material transfers... 970.4402-4 Nuclear material transfers. (a) Management and operating contractors, in preparing... nuclear material, shall be required to assure that each such subcontract or agreement contains a— (1...

48 CFR 970.4402-4 - Nuclear material transfers.

Code of Federal Regulations, 2013 CFR

2013-10-01

... 48 Federal Acquisition Regulations System 5 2013-10-01 2013-10-01 false Nuclear material transfers... 970.4402-4 Nuclear material transfers. (a) Management and operating contractors, in preparing... nuclear material, shall be required to assure that each such subcontract or agreement contains a— (1...

48 CFR 970.4402-4 - Nuclear material transfers.

Code of Federal Regulations, 2010 CFR

2010-10-01

... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Nuclear material transfers... 970.4402-4 Nuclear material transfers. (a) Management and operating contractors, in preparing... nuclear material, shall be required to assure that each such subcontract or agreement contains a— (1...

48 CFR 970.4402-4 - Nuclear material transfers.

Code of Federal Regulations, 2012 CFR

2012-10-01

... 48 Federal Acquisition Regulations System 5 2012-10-01 2012-10-01 false Nuclear material transfers... 970.4402-4 Nuclear material transfers. (a) Management and operating contractors, in preparing... nuclear material, shall be required to assure that each such subcontract or agreement contains a— (1...

TOWARD THE DEVELOPMENT OF A CONSENSUS MATERIALS DATABASE FOR PRESSURE TECHNOLGY APPLICATIONS

DOE Office of Scientific and Technical Information (OSTI.GOV)

Swindeman, Robert W; Ren, Weiju

The ASME construction code books specify materials and fabrication procedures that are acceptable for pressure technology applications. However, with few exceptions, the materials properties provided in the ASME code books provide no statistics or other information pertaining to material variability. Such information is central to the prediction and prevention of failure events. Many sources of materials data exist that provide variability information but such sources do not necessarily represent a consensus of experts with respect to the reported trends that are represented. Such a need has been identified by the ASME Standards Technology, LLC and initial steps have been takenmore » to address these needs: however, these steps are limited to project-specific applications only, such as the joint DOE-ASME project on materials for Generation IV nuclear reactors. In contrast to light-water reactor technology, the experience base for the Generation IV nuclear reactors is somewhat lacking and heavy reliance must be placed on model development and predictive capability. The database for model development is being assembled and includes existing code alloys such as alloy 800H and 9Cr-1Mo-V steel. Ownership and use rights are potential barriers that must be addressed.« less

Validation of pharmaceutical potency determinations by quantitative nuclear magnetic resonance spectrometry.

PubMed

Webster, Gregory K; Marsden, Ian; Pommerening, Cynthia A; Tyrakowski, Christina M

2010-05-01

With the changing development paradigms in the pharmaceutical industry, laboratories are challenged to release materials for clinical studies with rapid turnaround times. To minimize cost demands, many businesses are looking to develop ways of using early Good Manufacturing Practice (GMP) materials of active pharmaceutical ingredients (API) for Good Laboratory Practice (GLP) toxicology studies. To make this happen, the analytical laboratory releases the material by one of three scenarios: (1) holding the GLP release until full GMP testing is ready, (2) issuing a separate lot number for a portion of the GMP material and releasing the material for GLP use, or (3) releasing the lot of material for GLP using alternate (equivalent) method(s) not specified for GMP release testing. Many companies are finding the third scenario to be advantageous in terms of cost and efficiency through the use of quantitative nuclear magnetic resonance (q-NMR). The use of q-NMR has proved to be a single-point replacement for routine early development testing that previously combined elements of identity testing, chromatographic assay, moisture analysis, residual solvent analysis, and elemental analysis. This study highlights that q-NMR can be validated to meet current regulatory analytical method guidelines for routine pharmaceutical analysis.

10 CFR 8.4 - Interpretation by the General Counsel: AEC jurisdiction over nuclear facilities and materials...

Code of Federal Regulations, 2012 CFR

2012-01-01

... over nuclear facilities and materials under the Atomic Energy Act. 8.4 Section 8.4 Energy NUCLEAR... nuclear facilities and materials under the Atomic Energy Act. (a) By virtue of the Atomic Energy Act of... Atomic Energy Act of 1954 sets out a pattern for licensing and regulation of certain nuclear materials...

10 CFR 73.6 - Exemptions for certain quantities and kinds of special nuclear material.

Code of Federal Regulations, 2013 CFR

2013-01-01

... nuclear material. 73.6 Section 73.6 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION... special nuclear material. A licensee is exempt from the requirements of 10 CFR part 26 and §§ 73.20, 73.25, 73.26, 73.27, 73.45, 73.46, 73.70 and 73.72 with respect to the following special nuclear material...

10 CFR 73.6 - Exemptions for certain quantities and kinds of special nuclear material.

Code of Federal Regulations, 2014 CFR

2014-01-01

... nuclear material. 73.6 Section 73.6 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION... special nuclear material. A licensee is exempt from the requirements of 10 CFR part 26 and §§ 73.20, 73.25, 73.26, 73.27, 73.45, 73.46, 73.70 and 73.72 with respect to the following special nuclear material...

10 CFR 73.6 - Exemptions for certain quantities and kinds of special nuclear material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... nuclear material. 73.6 Section 73.6 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION... special nuclear material. A licensee is exempt from the requirements of 10 CFR part 26 and §§ 73.20, 73.25, 73.26, 73.27, 73.45, 73.46, 73.70 and 73.72 with respect to the following special nuclear material...

10 CFR 73.6 - Exemptions for certain quantities and kinds of special nuclear material.

Code of Federal Regulations, 2012 CFR

2012-01-01

... nuclear material. 73.6 Section 73.6 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION... special nuclear material. A licensee is exempt from the requirements of 10 CFR part 26 and §§ 73.20, 73.25, 73.26, 73.27, 73.45, 73.46, 73.70 and 73.72 with respect to the following special nuclear material...

10 CFR 73.6 - Exemptions for certain quantities and kinds of special nuclear material.

Code of Federal Regulations, 2011 CFR

2011-01-01

... nuclear material. 73.6 Section 73.6 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION... special nuclear material. A licensee is exempt from the requirements of 10 CFR part 26 and §§ 73.20, 73.25, 73.26, 73.27, 73.45, 73.46, 73.70 and 73.72 with respect to the following special nuclear material...

10 CFR 8.4 - Interpretation by the General Counsel: AEC jurisdiction over nuclear facilities and materials...

Code of Federal Regulations, 2010 CFR

2010-01-01

... over nuclear facilities and materials under the Atomic Energy Act. 8.4 Section 8.4 Energy NUCLEAR... nuclear facilities and materials under the Atomic Energy Act. (a) By virtue of the Atomic Energy Act of... Atomic Energy Act of 1954 sets out a pattern for licensing and regulation of certain nuclear materials...

10 CFR 8.4 - Interpretation by the General Counsel: AEC jurisdiction over nuclear facilities and materials...

Code of Federal Regulations, 2011 CFR

2011-01-01

... over nuclear facilities and materials under the Atomic Energy Act. 8.4 Section 8.4 Energy NUCLEAR... nuclear facilities and materials under the Atomic Energy Act. (a) By virtue of the Atomic Energy Act of... Atomic Energy Act of 1954 sets out a pattern for licensing and regulation of certain nuclear materials...

Advanced Ultrafast Spectroscopy for Chemical Detection of Nuclear Fuel Cycle Materials

DOE Office of Scientific and Technical Information (OSTI.GOV)

Villa-Aleman, E.; Houk, A.; Spencer, W.

The development of new signatures and observables from processes related to proliferation activities are often related to the development of technologies. In our physical world, the intensity of observables is linearly related to the input drivers (light, current, voltage, etc.). Ultrafast lasers with high peak energies, opens the door to a new regime where the intensity of the observables is not necessarily linear with the laser energy. Potential nonlinear spectroscopic applications include chemical detection via remote sensing through filament generation, material characterization and processing, chemical reaction specificity, surface phenomena modifications, X-ray production, nuclear fusion, etc. The National Security Directorate lasermore » laboratory is currently working to develop new tools for nonproliferation research with femtosecond and picosecond lasers. Prior to this project, we could only achieve laser energies in the 5 nano-Joule range, preventing the study of nonlinear phenomena. To advance our nonproliferation research into the nonlinear regime we require laser pulses in the milli-Joule (mJ) energy range. We have procured and installed a 35 fs-7 mJ laser, operating at one-kilohertz repetition rate, to investigate elemental and molecular detection of materials in the laboratory with potential applications in remote sensing. Advanced, nonlinear Raman techniques will be used to study materials of interest that are in a matrix of many materials and currently with these nonlinear techniques we can achieve greater than three orders of magnitude signal enhancement. This work studying nuclear fuel cycle materials with nonlinear spectroscopies will advance SRNL research capabilities and grow a core capability within the DOE complex.« less

Infrastructure development for radioactive materials at the NSLS-II

DOE Office of Scientific and Technical Information (OSTI.GOV)

Sprouster, D. J.; Weidner, R.; Ghose, S. K.

2018-02-01

The X-ray Powder Diffraction (XPD) Beamline at the National Synchrotron Light Source-II is a multipurpose instrument designed for high-resolution, high-energy X-ray scattering techniques. In this article, the capabilities, opportunities and recent developments in the characterization of radioactive materials at XPD are described. The overarching goal of this work is to provide researchers access to advanced synchrotron techniques suited to the structural characterization of materials for advanced nuclear energy systems. XPD is a new beamline providing high photon flux for X-ray Diffraction, Pair Distribution Function analysis and Small Angle X-ray Scattering. The infrastructure and software described here extend the existing capabilitiesmore » at XPD to accommodate radioactive materials. Such techniques will contribute crucial information to the characterization and quantification of advanced materials for nuclear energy applications. We describe the automated radioactive sample collection capabilities and recent X-ray Diffraction and Small Angle X-ray Scattering results from neutron irradiated reactor pressure vessel steels and oxide dispersion strengthened steels.« less

Infrastructure development for radioactive materials at the NSLS-II

DOE PAGES

Sprouster, David J.; Weidner, R.; Ghose, S. K.; ...

2017-11-04

The X-ray Powder Diffraction (XPD) Beamline at the National Synchrotron Light Source-II is a multipurpose instrument designed for high-resolution, high-energy X-ray scattering techniques. In this paper, the capabilities, opportunities and recent developments in the characterization of radioactive materials at XPD are described. The overarching goal of this work is to provide researchers access to advanced synchrotron techniques suited to the structural characterization of materials for advanced nuclear energy systems. XPD is a new beamline providing high photon flux for X-ray Diffraction, Pair Distribution Function analysis and Small Angle X-ray Scattering. The infrastructure and software described here extend the existing capabilitiesmore » at XPD to accommodate radioactive materials. Such techniques will contribute crucial information to the characterization and quantification of advanced materials for nuclear energy applications. Finally, we describe the automated radioactive sample collection capabilities and recent X-ray Diffraction and Small Angle X-ray Scattering results from neutron irradiated reactor pressure vessel steels and oxide dispersion strengthened steels.« less

10 CFR Appendix E to Part 73 - Levels of Physical Protection To Be Applied in International Transport of Nuclear Material 1

Code of Federal Regulations, 2010 CFR

2010-01-01

... material are synonymous: Category I is a formula quantity of strategic special nuclear material; Category II is special nuclear material of moderate strategic significance or irradiated fuel; and Category III is special nuclear material of low strategic significance. (Verbatim from Annex I to the...

Statistical methods for nuclear material management

DOE Office of Scientific and Technical Information (OSTI.GOV)

Bowen W.M.; Bennett, C.A.

1988-12-01

This book is intended as a reference manual of statistical methodology for nuclear material management practitioners. It describes statistical methods currently or potentially important in nuclear material management, explains the choice of methods for specific applications, and provides examples of practical applications to nuclear material management problems. Together with the accompanying training manual, which contains fully worked out problems keyed to each chapter, this book can also be used as a textbook for courses in statistical methods for nuclear material management. It should provide increased understanding and guidance to help improve the application of statistical methods to nuclear material managementmore » problems.« less

Active Interrogation using Photofission Technique for Nuclear Materials Control and Accountability

DOE Office of Scientific and Technical Information (OSTI.GOV)

Yang, Haori

2016-03-31

Innovative systems with increased sensitivity and resolution are in great demand to detect diversion and to prevent misuse in support of nuclear materials management for the U.S. fuel cycle. Nuclear fission is the most important multiplicative process involved in non-destructive active interrogation. This process produces the most easily recognizable signature for nuclear materials. In addition to thermal or high-energy neutrons, high-energy gamma rays can also excite a nucleus and cause fission through a process known as photofission. Electron linear accelerators (linacs) are widely used as the interrogating photon sources for inspection methods involving photofission technique. After photofission reactions, prompt signalsmore » are much stronger than the delayed signals, but it is difficult to quantify them in practical measurements. Delayed signals are easily distinguishable from the interrogating radiation. Linac-based, advanced inspection techniques utilizing the delayed signals after photofission have been extensively studied for homeland security applications. Previous research also showed that a unique delayed gamma ray energy spectrum exists for each fissionable isotope. In this work, high-energy delayed γ-rays were demonstrated to be signatures for detection, identification, and quantification of special nuclear materials. Such γ-rays were measured in between linac pulses using independent data acquisition systems. A list-mode system was developed to measure low-energy delayed γ-rays after irradiation. Photofission product yields of 238U and 239Pu were determined based on the measured delayed γ-ray spectra. The differential yields of delayed γ-rays were also proven to be able to discriminate nuclear from non-nuclear materials. The measurement outcomes were compared with Monte Carlo simulation results. It was demonstrated that the current available codes have capabilities and limitations in the simulation of photofission process. A two-fold approach was used to address the high-rate challenge in used nuclear fuel assay based on photofission technique. First, a standard HPGe preamplifier was modified to improve its capabilities in high-rate pulsed photofission environment. Second, advanced pulse processing algorithms were shown to greatly improve throughput rate without large sacrifice in energy resolution at ultra-high input count rate. Two customized gamma spectroscopy systems were also developed in real-time on FPGAs. They were shown to have promising performance matching available commercial units.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Giaquinto, Joseph M.; Younkin, James R.

The purpose of this letter report is to document the response for an Expression of Interest (EOI) sent to the European Safeguards and research and development (R&D) scientific communities for the distribution of small amounts of high purity 233U materials for use in safeguards, nonproliferation, and basic R&D in the nuclear disciplines. The intent for the EOI was to gauge the level of international interest for these materials from government and research institutions with programmatic missions in the nuclear security or nuclear R&D arena. The information contained herein is intended to provide information to assist key decision makers in DOEmore » as to the ultimate disposition path for the high purity materials currently being recovered at Oak Ridge National Laboratory (ORNL) and only those items for which there is no United States (U.S.) sponsor identified.« less

Calculation of the nuclear material inventory in a sealed vault by 3D radiation mapping

DOE Office of Scientific and Technical Information (OSTI.GOV)

Adsley, Ian; Klepikov, Alexander; Tur, Yevgeniy

2013-07-01

The paper relates to the determination of the amount of nuclear material contained in a closed, concrete lined vault at the Aktau fast breeder reactor in Kazakhstan. This material had been disposed into the vault after examination in an experimental hot cell directly above the vault. In order to comply with IAEA Safeguards requirements it was necessary to determine the total quantities of nuclear materials - enriched uranium and plutonium - that were held with Kazakhstan. Although it was possible to determine the inventory of all of the accessible nuclear material - the quantity remaining in the vault was unknown.more » As part of the Global Threat Reduction Programme the UK Government funded a project to determine the inventory of these nuclear materials in this vault. This involved drilling three penetrations through the concrete lined roof of the vault; this enabled the placement of lights and a camera into the vault through two penetrations; while the third penetration enabled a lightweight manipulator arm to be introduced into the vault. This was used to provide a detailed 3D mapping of the dose rate within the vault and it also enabled the collection of samples for radionuclide analysis. The deconvolution of the 3D dose rate profile within the vault enabled the determination of the gamma emitting source distribution on the floor and walls of the vault. The samples were analysed to determine the fingerprint of those radionuclides producing the gamma dose - namely {sup 137}Cs and {sup 60}Co - to the nuclear materials. The combination of the dose rate source terms on the surfaces of the vault and the fingerprint then enabled the quantities of nuclear materials to be determined. The project was a major success and enabled the Kazakhstan Government to comply with IAEA Safeguards requirements. It also enabled the UK DECC Ministry to develop a technology of national (and international) use. Finally the technology was well received by IAEA Safeguards as an acceptable methodology for future studies. (authors)« less

412th Brookhaven Lecture

ScienceCinema

Peter Vanier

2017-12-09

With new radiation detectors, finding smuggled nuclear materials in a huge container among thousands of others in a busy port becomes possible. To learn about these new detectors from a specialist who has spent several years developing these technologies, watch the 412th Brookhaven Lecture, "Advanced Neutron Detection Methods: New Tools for Countering Nuclear Terrorism."

Accelerated development of Zr-containing new generation ferritic steels for advanced nuclear reactors

DOE Office of Scientific and Technical Information (OSTI.GOV)

Tan, Lizhen; Yang, Ying; Sridharan, K.

2015-12-01

The mission of the Nuclear Energy Enabling Technologies (NEET) program is to develop crosscutting technologies for nuclear energy applications. Advanced structural materials with superior performance at elevated temperatures are always desired for nuclear reactors, which can improve reactor economics, safety margins, and design flexibility. They benefit not only new reactors, including advanced light water reactors (LWRs) and fast reactors such as the sodium-cooled fast reactor (SFR) that is primarily designed for management of high-level wastes, but also life extension of the existing fleet when component exchange is needed. Developing and utilizing the modern materials science tools (experimental, theoretical, and computationalmore » tools) is an important path to more efficient alloy development and process optimization. The ultimate goal of this project is, with the aid of computational modeling tools, to accelerate the development of Zr-bearing ferritic alloys that can be fabricated using conventional steelmaking methods. The new alloys are expected to have superior high-temperature creep performance and excellent radiation resistance as compared to Grade 91. The designed alloys were fabricated using arc-melting and drop-casting, followed by hot rolling and conventional heat treatments. Comprehensive experimental studies have been conducted on the developed alloys to evaluate their hardness, tensile properties, creep resistance, Charpy impact toughness, and aging resistance, as well as resistance to proton and heavy ion (Fe 2+) irradiation.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Shipwash, Jacqueline L; Kovacic, Donald N

Infrastructure Preparedness and Vietnam Jacqueline L. Shipwash and Donald N. Kovacic (shipwashjl@ornl.gov, 865-241-9129, and kovacicdn@ornl.gov, 865-576-1459) Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 The global expansion of nuclear energy will require international cooperation to ensure that nuclear materials, facilities, and sensitive technologies are not diverted to non-peaceful uses. Developing countries will require assistance to ensure the effective regulation, management, and operation of their nuclear programs to achieve best practices in nuclear nonproliferation. A developing nation has many hurdles to pass before it can give assurances to the international community that it is capable of implementing a sustainable nuclear energymore » program. In August of this year, the U.S. Department of Energy and the Ministry of Science and Technology of the Socialist Republic of Vietnam signed an arrangement for Information Exchange and Cooperation on the Peaceful Uses of Nuclear Energy. This event signals an era of cooperation between the U.S. and Vietnam in the area of nuclear nonproliferation. This paper will address how DOE is supporting the development of secure and sustainable infrastructures in emerging nuclear nations such as Vietnam.« less

29 CFR 1910.1096 - Ionizing radiation.

Code of Federal Regulations, 2012 CFR

2012-07-01

... material, as defined in the Atomic Energy Act of 1954, as amended, under a license issued by the Nuclear... material, byproduct material, or special nuclear material, as defined in the Atomic Energy Act of 1954, as... source material, byproduct material, or special nuclear material, as defined in the Atomic Energy Act of...

29 CFR 1910.1096 - Ionizing radiation.

Code of Federal Regulations, 2011 CFR

2011-07-01

... material, as defined in the Atomic Energy Act of 1954, as amended, under a license issued by the Nuclear... material, byproduct material, or special nuclear material, as defined in the Atomic Energy Act of 1954, as... source material, byproduct material, or special nuclear material, as defined in the Atomic Energy Act of...

29 CFR 1910.1096 - Ionizing radiation.

Code of Federal Regulations, 2014 CFR

2014-07-01

... material, as defined in the Atomic Energy Act of 1954, as amended, under a license issued by the Nuclear... material, byproduct material, or special nuclear material, as defined in the Atomic Energy Act of 1954, as... source material, byproduct material, or special nuclear material, as defined in the Atomic Energy Act of...

Nuclear energy: Where do we go from here?

NASA Astrophysics Data System (ADS)

Muslim, Dato'Noramly, Dr

2015-04-01

As Malaysia progresses towards 2020, the depleting resource of oil and gas has forced a re-look at alternatives to replace fossil fuels as energy sources. Among the viable options is nuclear energy, enabling us to meet energy needs and sustain national development in the twenty-first century. Three essential steps Malaysia must take to introduce nuclear power into its energy mix are: energy planning, infrastructure development, and deployment. Malaysia has to face a series of challenges, including public acceptance, waste management, minimizing proliferation risk, and ensuring the security of nuclear plants and materials. Timely development of qualified and competent manpower is a key limiting factor in the development and transfer of nuclear technologies — and education and training take time, effort and money. There is a need for political will. Within the Asian region, China, Korea and Japan are in the forefront in utilizing nuclear power to meet electricity demands. Countries such as UAE, Bangladesh, Vietnam and Turkey are moving ahead with the nuclear option for electricity generation and they have begun planning and construction of nuclear power plants. Against this backdrop, what are Malaysia's moves? This paper discusses various options and challenges, obstacles and repercussions in meeting future energy demands.

5 CFR 842.208 - Firefighters, law enforcement officers, and nuclear materials couriers.

Code of Federal Regulations, 2010 CFR

2010-01-01

..., and nuclear materials couriers. 842.208 Section 842.208 Administrative Personnel OFFICE OF PERSONNEL... ANNUITY Eligibility § 842.208 Firefighters, law enforcement officers, and nuclear materials couriers. (a... enforcement officer or nuclear materials courier totaling 25 years; or (2) After becoming age 50 and...

Special nuclear materials cutoff exercise: Issues and lessons learned. Volume 3

DOE Office of Scientific and Technical Information (OSTI.GOV)

Libby, R.A.; Segal, J.E.; Stanbro, W.D.

1995-08-01

This document is appendices D-J for the Special Nuclear Materials Cutoff Exercise: Issues and Lessons Learned. Included are discussions of the US IAEA Treaty, safeguard regulations for nuclear materials, issue sheets for the PUREX process, and the LANL follow up activity for reprocessing nuclear materials.

Risk ranking of LANL nuclear material storage containers for repackaging prioritization.

PubMed

Smith, Paul H; Jordan, Hans; Hoffman, Jenifer A; Eller, P Gary; Balkey, Simon

2007-05-01

Safe handling and storage of nuclear material at U.S. Department of Energy facilities relies on the use of robust containers to prevent container breaches and subsequent worker contamination and uptake. The U.S. Department of Energy has no uniform requirements for packaging and storage of nuclear materials other than those declared excess and packaged to DOE-STD-3013-2000. This report describes a methodology for prioritizing a large inventory of nuclear material containers so that the highest risk containers are repackaged first. The methodology utilizes expert judgment to assign respirable fractions and reactivity factors to accountable levels of nuclear material at Los Alamos National Laboratory. A relative risk factor is assigned to each nuclear material container based on a calculated dose to a worker due to a failed container barrier and a calculated probability of container failure based on material reactivity and container age. This risk-based methodology is being applied at LANL to repackage the highest risk materials first and, thus, accelerate the reduction of risk to nuclear material handlers.

Annual Report to Congress of the Atomic Energy Commission for 1965

DOE Office of Scientific and Technical Information (OSTI.GOV)

Seaborg, Glenn T.

1966-01-31

The document represents the 1965 Annual Report of the Atomic Energy Commission (AEC) to Congress. The report opens with a Foreword - a letter from President Lyndon B. Johnson. The main portion is divided into 3 major sections for 1965, plus 10 appendices and the index. Section names and chapters are as follows. Part One reports on Developmental and Promotional Activities with the following chapters: (1) The Atomic Energy Program - 1965; (2) The Industrial Base ; (3) Industrial Relations; (4) Operational Safety; (5) Source and Special Nuclear Materials Production; (6) The Nuclear Defense Effort; (7) Civilian Nuclear Power; (8)more » Nuclear Space Applications; (9) Auxiliary Electrical Power for Land and Sea; (10) Military Reactors; (11) Advanced Reactor Technology and Nuclear Safety Research; (12) The Plowshare Program; (13) Isotopes and Radiation Development; (14) Facilities and Projects for Basic Research; (15) International Cooperation; and, (16) Nuclear Education and Information. Part Two reports on Regulatory Activities with the following chapters: (1) Licensing and Regulating the Atom; (2) Reactors and other Nuclear Facilities; and, (3) Control of Radioactive Materials. Part Three reports on Adjudicatory Activities.« less

Non-Nuclear Testing of Space Nuclear Systems at NASA MSFC

NASA Technical Reports Server (NTRS)

Houts, Michael G.; Pearson, Boise J.; Aschenbrenner, Kenneth C.; Bradley, David E.; Dickens, Ricky; Emrich, William J.; Garber, Anne; Godfroy, Thomas J.; Harper, Roger T.; Martin, Jim J.;

The Tripartite Seminars at the Russian Methodological and Training Center: An Overview of Progress in Nuclear Materials Control and Accounting in the Russian Federation

DOE Office of Scientific and Technical Information (OSTI.GOV)

Pshakin, Gennady; Dickman, Deborah A.; Ryazanov, Boris

2003-09-16

The development of the Russian Methodological and Training Center (RMTC) has been an important element of collaboration between the Russian Federation (RF), the European Union and the US. The RMTC, located at the Institute of Physics and Power Engineering (IPPE) in Obninsk, Russia has been designated by the Russian Ministry of Atomic Energy (Minatom) to provide nuclear materials protection, control and Accounting training to Minatom and the Federal Nuclear and Radiation Safety Authority (Gosatomnadzor) personnel. In addition, the RMTC was chartered with the responsibility of providing a venue for exchange of experiences and information between Russian and international specialists.

Novel Scintillating Materials Based on Phenyl-Polysiloxane for Neutron Detection and Monitoring

NASA Astrophysics Data System (ADS)

Degerlier, M.; Carturan, S.; Gramegna, F.; Marchi, T.; Palma, M. Dalla; Cinausero, M.; Maggioni, G.; Quaranta, A.; Collazuol, G.; Bermudez, J.

Neutron detectors are extensively used at many nuclear research facilities across Europe. Their application range covers many topics in basic and applied nuclear research: in nuclear structure and reaction dynamics (reaction reconstruction and decay studies); in nuclear astrophysics (neutron emission probabilities); in nuclear technology (nuclear data measurements and in-core/off-core monitors); in nuclear medicine (radiation monitors, dosimeters); in materials science (neutron imaging techniques); in homeland security applications (fissile materials investigation and cargo inspection). Liquid scintillators, widely used at present, have however some drawbacks given by toxicity, flammability, volatility and sensitivity to oxygen that limit their duration and quality. Even plastic scintillators are not satisfactory because they have low radiation hardness and low thermal stability. Moreover organic solvents may affect their optical properties due to crazing. In order to overcome these problems, phenyl-polysiloxane based scintillators have been recently developed at Legnaro National Laboratory. This new solution showed very good chemical and thermal stability and high radiation hardness. The results on the different samples performance will be presented, paying special attention to a characterization comparison between synthesized phenyl containing polysiloxane resins where a Pt catalyst has been used and a scintillating material obtained by condensation reaction, where tin based compounds are used as catalysts. Different structural arrangements as a result of different substituents on the main chain have been investigated by High Resolution X-Ray Diffraction, while the effect of improved optical transmittance on the scintillation yield has been elucidated by a combination of excitation/fluorescence measurements and scintillation yield under exposure to alpha and γ-rays.

Basic and Applied Materials Science Research Efforts at MSFC Germane to NASA Goals

NASA Technical Reports Server (NTRS)

2003-01-01

Presently, a number of investigations are ongoing that blend basic research with engineering applications in support of NASA goals. These include (1) "Pore Formation and Mobility (PFMI) " An ISS Glovebox Investigation" NASA Selected Project - 400-34-3D; (2) "Interactions Between Rotating Bodies" Center Director's Discretionary Fund (CDDF) Project - 279-62-00-16; (3) "Molybdenum - Rhenium (Mo-Re) Alloys for Nuclear Fuel Containment" TD Collaboration - 800-11-02; (4) "Fabrication of Alumina - Metal Composites for Propulsion Components" ED Collaboration - 090-50-10; (5) "Radiation Shielding for Deep-Space Missions" SD Effort; (6) "Other Research". In brief, "Pore Formation and Mobility" is an experiment to be conducted in the ISS Microgravity Science Glovebox that will systematically investigate the development, movement, and interactions of bubbles (porosity) during the controlled directional solidification of a transparent material. In addition to promoting our general knowledge of porosity physics, this work will serve as a guide to future ISS experiments utilizing metal alloys. "Interactions Between Rotating Bodies" is a CDDF sponsored project that is critically examining, through theory and experiment, claims of "new" physics relating to gravity modification and electric field effects. "Molybdenum - Rhenium Alloys for Nuclear Fuel Containment" is a TD collaboration in support of nuclear propulsion. Mo-Re alloys are being evaluated and developed for nuclear fuel containment. "Fabrication of Alumina - Metal Composites for Propulsion Components" is an ED collaboration with the intent of increasing strength and decreasing weight of metal engine components through the incorporation of nanometer-sized alumina fibers. "Radiation Shielding for Deep-Space Missions" is an SD effort aimed at minimizing the health risk from radiation to human space voyagers; work to date has been primarily programmatic but experiments to develop hydrogen-rich materials for shielding are planned. "Other Research" includes: BUNDLE (Bridgman Unidirectional Dendrite in a Liquid Experiment) activities (primarily crucible development), vibrational float-zone processing (with Vanderbilt University), use of ultrasonics in materials processing (with UAH), rotational effects on microstructural development, and application of magnetic fields for mixing.

Developing 226Ra and 227Ac age-dating techniques for nuclear forensics to gain insight from concordant and non-concordant radiochronometers

DOE PAGES

Kayzar, Theresa M.; Williams, Ross W.

2015-09-26

The model age or ‘date of purification’ of a nuclear material is an important nuclear forensic signature. In this study, chemical separation and MC-ICP-MS measurement techniques were developed for 226 Ra and 227Ac: grand-daughter nuclides in the 238U and 235U decay chains respectively. The 230Th- 234U, 226Ra- 238U, 231Pa- 235U, and 227Ac- 235U radiochronometers were used to calculate model ages for CRM-U100 standard reference material and two highly-enriched pieces of uranium metal from the International Technical Working Group Round Robin 3 Exercise. In conclusion, the results demonstrate the accuracy of the 226Ra- 238U and 227Ac- 235U chronometers and provide informationmore » about nuclide migration during uranium processing.« less

Developing 226Ra and 227Ac age-dating techniques for nuclear forensics to gain insight from concordant and non-concordant radiochronometers

DOE Office of Scientific and Technical Information (OSTI.GOV)

Kayzar, Theresa M.; Williams, Ross W.

The model age or ‘date of purification’ of a nuclear material is an important nuclear forensic signature. In this study, chemical separation and MC-ICP-MS measurement techniques were developed for 226 Ra and 227Ac: grand-daughter nuclides in the 238U and 235U decay chains respectively. The 230Th- 234U, 226Ra- 238U, 231Pa- 235U, and 227Ac- 235U radiochronometers were used to calculate model ages for CRM-U100 standard reference material and two highly-enriched pieces of uranium metal from the International Technical Working Group Round Robin 3 Exercise. In conclusion, the results demonstrate the accuracy of the 226Ra- 238U and 227Ac- 235U chronometers and provide informationmore » about nuclide migration during uranium processing.« less

10 CFR 72.74 - Reports of accidental criticality or loss of special nuclear material.

Code of Federal Regulations, 2014 CFR

2014-01-01

... nuclear material. 72.74 Section 72.74 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR... accidental criticality or loss of special nuclear material. (a) Each licensee shall notify the NRC Operations...

10 CFR 72.74 - Reports of accidental criticality or loss of special nuclear material.

Code of Federal Regulations, 2013 CFR

2013-01-01

... nuclear material. 72.74 Section 72.74 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR... accidental criticality or loss of special nuclear material. (a) Each licensee shall notify the NRC Operations...

10 CFR 72.74 - Reports of accidental criticality or loss of special nuclear material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... nuclear material. 72.74 Section 72.74 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR... accidental criticality or loss of special nuclear material. (a) Each licensee shall notify the NRC Operations...

10 CFR 72.74 - Reports of accidental criticality or loss of special nuclear material.

Code of Federal Regulations, 2012 CFR

2012-01-01

... nuclear material. 72.74 Section 72.74 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR... accidental criticality or loss of special nuclear material. (a) Each licensee shall notify the NRC Operations...

10 CFR 72.74 - Reports of accidental criticality or loss of special nuclear material.

Code of Federal Regulations, 2011 CFR

2011-01-01

... nuclear material. 72.74 Section 72.74 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR... accidental criticality or loss of special nuclear material. (a) Each licensee shall notify the NRC Operations...

Low Cost Nuclear Thermal Rocket Cermet Fuel Element Environment Testing

NASA Technical Reports Server (NTRS)

Bradley, D. E.; Mireles, O. R.; Hickman, R. R.

2011-01-01

Deep space missions with large payloads require high specific impulse and relatively high thrust to achieve mission goals in reasonable time frames.1,2 Conventional storable propellants produce average specific impulse. Nuclear thermal rockets capable of producing high specific impulse are proposed. Nuclear thermal rockets employ heat produced by fission reaction to heat and therefore accelerate hydrogen, which is then forced through a rocket nozzle providing thrust. Fuel element temperatures are very high (up to 3000 K), and hydrogen is highly reactive with most materials at high temperatures. Data covering the effects of high-temperature hydrogen exposure on fuel elements are limited.3 The primary concern is the mechanical failure of fuel elements that employ high-melting-point metals, ceramics, or a combination (cermet) as a structural matrix into which the nuclear fuel is distributed. The purpose of the testing is to obtain data to assess the properties of the non-nuclear support materials, as-fabricated, and determine their ability to survive and maintain thermal performance in a prototypical NTR reactor environment of exposure to hydrogen at very high temperatures. The fission process of the planned fissile material and the resulting heating performance is well known and does not therefore require that active fissile material be integrated in this testing. A small-scale test bed designed to heat fuel element samples via non-contact radio frequency heating and expose samples to hydrogen is being developed to assist in optimal material and manufacturing process selection without employing fissile material. This paper details the test bed design and results of testing conducted to date.

LATIN AMERICAN AND CARIBBEAN WORKSHOP ON THE SUSTAINABILITY OF RADIOACTIVE SOURCE PHYSICAL PROTECTION UPGRADES HOSTED IN GUATEMALA

DOE Office of Scientific and Technical Information (OSTI.GOV)

Greenberg, Raymond; Watson, Erica E.; Morris, Frederic A.

2009-10-07

The Global Threat Reduction Initiative (GTRI) reduces and protects vulnerable nuclear and radiological material located at civilian sites worldwide. The GTRI program has worked successfully to remove and protect nuclear and radioactive materials, including orphaned and disused high-activity sources, and is now working to ensure sustainability. Internationally, over 40 countries are cooperating with GTRI to enhance the security of radiological materials. GTRI is now seeking to develop and enhance sustainability by coordinating its resources with those of the partner country, other donor countries, and international organizations such as the International Atomic Energy Agency (IAEA).

Neutron and Gamma Imaging for National Security Applications

NASA Astrophysics Data System (ADS)

Hornback, Donald

2017-09-01

The Department of Energy, National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation Research and Development (DNN R&D/NA-22) possesses, in part, the mission to develop technologies in support of nuclear security efforts in coordination with other U.S. government entities, such as the Department of Defense and the Department of Homeland Security. DNN R&D has long supported research in nuclear detection at national labs, universities, and through the small business innovation research (SBIR) program. Research topics supported include advanced detector materials and electronics, detection algorithm development, and advanced gamma/neutron detection systems. Neutron and gamma imaging, defined as the directional detection of radiation as opposed to radiography, provides advanced detection capabilities for the NNSA mission in areas of emergency response, international safeguards, and nuclear arms control treaty monitoring and verification. A technical and programmatic overview of efforts in this field of research will be summarized.

OECD/NEA Ongoing activities related to the nuclear fuel cycle

DOE Office of Scientific and Technical Information (OSTI.GOV)

Cornet, S.M.; McCarthy, K.; Chauvin, N.

2013-07-01

As part of its role in encouraging international collaboration, the OECD Nuclear Energy Agency is coordinating a series of projects related to the Nuclear Fuel Cycle. The Nuclear Science Committee (NSC) Working Party on Scientific Issues of the Nuclear Fuel Cycle (WPFC) comprises five different expert groups covering all aspects of the fuel cycle from front to back-end. Activities related to fuels, materials, physics, separation chemistry, and fuel cycles scenarios are being undertaken. By publishing state-of-the-art reports and organizing workshops, the groups are able to disseminate recent research advancements to the international community. Current activities mainly focus on advanced nuclearmore » systems, and experts are working on analyzing results and establishing challenges associated to the adoption of new materials and fuels. By comparing different codes, the Expert Group on Advanced Fuel Cycle Scenarios is aiming at gaining further understanding of the scientific issues and specific national needs associated with the implementation of advanced fuel cycles. At the back end of the fuel cycle, separation technologies (aqueous and pyrochemical processing) are being assessed. Current and future activities comprise studies on minor actinides separation and post Fukushima studies. Regular workshops are also organized to discuss recent developments on Partitioning and Transmutation. In addition, the Nuclear Development Committee (NDC) focuses on the analysis of the economics of nuclear power across the fuel cycle in the context of changes of electricity markets, social acceptance and technological advances and assesses the availability of the nuclear fuel and infrastructure required for the deployment of existing and future nuclear power. The Expert Group on the Economics of the Back End of the Nuclear Fuel Cycle (EBENFC), in particular, is looking at assessing economic and financial issues related to the long term management of spent nuclear fuel. (authors)« less

The solid state physics programme at ISOLDE: recent developments and perspectives

NASA Astrophysics Data System (ADS)

Johnston, Karl; Schell, Juliana; Correia, J. G.; Deicher, M.; Gunnlaugsson, H. P.; Fenta, A. S.; David-Bosne, E.; Costa, A. R. G.; Lupascu, Doru C.

2017-10-01

Solid state physics (SSP) research at ISOLDE has been running since the mid-1970s and accounts for about 10%-15% of the overall physics programme. ISOLDE is the world flagship for the on-line production of exotic radioactive isotopes, with high yields, high elemental selectivity and isotopic purity. Consequently, it hosts a panoply of state-of-the-art nuclear techniques which apply nuclear methods to research on life sciences, material science and bio-chemical physics. The ease of detecting radioactivity—<1 ppm concentrations—is one of the features which distinguishes the use of radioisotopes for materials science research. The manner in which nuclear momenta of excited nuclear states interact with their local electronic and magnetic environment, or how charged emitted particles interact with the crystalline lattices allow the determination of the location, its action and the role of the selected impurity element at the nanoscopic state. ISOLDE offers an unrivalled range of available radioactive elements and this is attracting an increasing user community in the field of nuclear SSP research and brings together a community of materials scientists and specialists in nuclear solid state techniques. This article describes the current status of this programme along with recent illustrative results, predicting a bright future for these unique research methods and collaborations.

Source Recertification, Refurbishment, and Transfer Logistics

DOE Office of Scientific and Technical Information (OSTI.GOV)

Gastelum, Zoe N.; Duckworth, Leesa L.; Greenfield, Bryce A.

2013-09-01

The 2012 Gap Analysis of Department of Energy Radiological Sealed Sources, Standards, and Materials for Safeguards Technology Development [1] report, and the subsequent Reconciliation of Source Needs and Surpluses across the U.S. Department of Energy National Laboratory Complex [2] report, resulted in the identification of 33 requests for nuclear or radiological sealed sources for which there was potentially available, suitable material from within the U.S. Department of Energy (DOE) complex to fill the source need. Available, suitable material was defined by DOE laboratories as material slated for excess, or that required recertification or refurbishment before being used for safeguards technologymore » development. This report begins by outlining the logistical considerations required for the shipment of nuclear and radiological materials between DOE laboratories. Then, because of the limited need for transfer of matching sources, the report also offers considerations for an alternative approach – the shipment of safeguards equipment between DOE laboratories or technology testing centers. Finally, this report addresses repackaging needs for the two source requests for which there was available, suitable material within the DOE complex.« less

An Overview of the Cooperative Effort between the United States Department of Energy and the China Atomic Energy Authority to Enhance MPC&A Inspections for Civil Nuclear Facilities in China

DOE Office of Scientific and Technical Information (OSTI.GOV)

Ahern, Keith; Daming, Liu; Hanley, Tim

The United States Department of Energy, National Nuclear Security Administration (DOE/NNSA) and the China Atomic Energy Authority (CAEA) are cooperating to enhance the domestic regulatory inspections capacity for special nuclear material protection, control and accounting (MPC&A) requirements for civil nuclear facilities in China. This cooperation is conducted under the auspices of the Agreement between the Department of Energy of the United States of America and the State Development and Planning Commission of the People s Republic of China on Cooperation Concerning Peaceful Uses of Nuclear Technology. This initial successful effort was conducted in three phases. Phase I focused on introducingmore » CAEA personnel to DOE and U. S. Nuclear Regulatory Commission inspection methods for U. S. facilities. This phase was completed in January 2008 during meetings in Beijing. Phase II focused on developing physical protection and material control and accounting inspection exercises that enforced U. S. inspection methods identified during Phase 1. Hands on inspection activities were conducted in the United States over a two week period in July 2009. Simulated deficiencies were integrated into the inspection exercises. The U. S. and Chinese participants actively identified and discussed deficiencies noted during the two week training course. The material control and accounting inspection exercises were conducted at the Paducah Gaseous Diffusion Plant (PGDP) in Paducah, KY. The physical protection inspection exercises were conducted at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, TN. Phase III leveraged information provided under Phase I and experience gained under Phase II to develop a formal inspection guide that incorporates a systematic approach to training for Chinese MPC&A field inspectors. Additional hands on exercises that are applicable to Chinese regulations were incorporated into the Phase III training material. Phase III was completed in May 2010 at the China Institute of Atomic Energy (CIAE) in Beijing. This paper provides details of the successful cooperation between DOE/NNSA and CAEA for all phases of the cooperative effort to enhance civil domestic MPC&A inspections in China.« less

10 CFR 74.33 - Nuclear material control and accounting for uranium enrichment facilities authorized to produce...

Code of Federal Regulations, 2010 CFR

2010-01-01

... and special nuclear material in the accounting records are based on measured values; (3) A measurement... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for uranium... Section 74.33 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL...

76 FR 63672 - Notice of Acceptance of Application for Special Nuclear Materials License From Passport Systems...

Federal Register 2010, 2011, 2012, 2013, 2014

2011-10-13

... Application for Special Nuclear Materials License From Passport Systems, Inc., Opportunity To Request a... special nuclear material (SNM), submitted by Passport Systems, Inc. (Passport or the Applicant). The..., if approved, would authorize Passport to possess and use special nuclear materials under 10 CFR Part...

10 CFR 73.28 - Security background checks for secure transfer of nuclear materials.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Security background checks for secure transfer of nuclear materials. 73.28 Section 73.28 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF PLANTS AND MATERIALS Physical Protection of Special Nuclear Material in Transit § 73.28 Security...

10 CFR 73.28 - Security background checks for secure transfer of nuclear materials.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Security background checks for secure transfer of nuclear materials. 73.28 Section 73.28 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF PLANTS AND MATERIALS Physical Protection of Special Nuclear Material in Transit § 73.28 Security...

10 CFR 74.33 - Nuclear material control and accounting for uranium enrichment facilities authorized to produce...

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Nuclear material control and accounting for uranium enrichment facilities authorized to produce special nuclear material of low strategic significance. 74.33 Section 74.33 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL...

10 CFR 73.28 - Security background checks for secure transfer of nuclear materials.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Security background checks for secure transfer of nuclear materials. 73.28 Section 73.28 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF PLANTS AND MATERIALS Physical Protection of Special Nuclear Material in Transit § 73.28 Security...

Neutron interrogation system using high gamma ray signature to detect contraband special nuclear materials in cargo

DOEpatents

Slaughter, Dennis R.; Pohl, Bertram A.; Dougan, Arden D.; Bernstein, Adam; Prussin, Stanley G.; Norman, Eric B.

2008-04-15

A system for inspecting cargo for the presence of special nuclear material. The cargo is irradiated with neutrons. The neutrons produce fission products in the special nuclear material which generate gamma rays. The gamma rays are detecting indicating the presence of the special nuclear material.

10 CFR 73.28 - Security background checks for secure transfer of nuclear materials.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Security background checks for secure transfer of nuclear materials. 73.28 Section 73.28 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF PLANTS AND MATERIALS Physical Protection of Special Nuclear Material in Transit § 73.28 Security...

10 CFR 74.33 - Nuclear material control and accounting for uranium enrichment facilities authorized to produce...

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Nuclear material control and accounting for uranium enrichment facilities authorized to produce special nuclear material of low strategic significance. 74.33 Section 74.33 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL...

10 CFR 74.33 - Nuclear material control and accounting for uranium enrichment facilities authorized to produce...

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Nuclear material control and accounting for uranium enrichment facilities authorized to produce special nuclear material of low strategic significance. 74.33 Section 74.33 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL...

10 CFR 73.28 - Security background checks for secure transfer of nuclear materials.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Security background checks for secure transfer of nuclear materials. 73.28 Section 73.28 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF PLANTS AND MATERIALS Physical Protection of Special Nuclear Material in Transit § 73.28 Security...

Validation of reference materials for uranium radiochronometry in the frame of nuclear forensic investigations

DOE PAGES

Varga, Z.; Mayer, K.; Bonamici, C. E.; ...

2015-05-11

The results of a joint effort by expert nuclear forensic laboratories in the area of age dating of uranium, i.e. the elapsed time since the last chemical purification of the material are presented and discussed. Completely separated uranium materials of known production date were distributed among the laboratories, and the samples were dated according to routine laboratory procedures by the measurement of the ²²⁰Th/²³⁴U ratio. The measurement results were in good agreement with the known production date showing that the concept for preparing uranium age dating reference material based on complete separation is valid. Detailed knowledge of the laboratory proceduresmore » used for uranium age dating allows the identification of possible improvements in the current protocols and the development of improved practice in the future. The availability of age dating reference materials as well as the evolvement of the age dating best-practice protocol will increase the relevance and applicability of age dating as part of the tool-kit available for nuclear forensic investigations.« less

Validation of reference materials for uranium radiochronometry in the frame of nuclear forensic investigations

DOE Office of Scientific and Technical Information (OSTI.GOV)

Varga, Z.; Mayer, K.; Bonamici, C. E.

The results of a joint effort by expert nuclear forensic laboratories in the area of age dating of uranium, i.e. the elapsed time since the last chemical purification of the material are presented and discussed. Completely separated uranium materials of known production date were distributed among the laboratories, and the samples were dated according to routine laboratory procedures by the measurement of the ²²⁰Th/²³⁴U ratio. The measurement results were in good agreement with the known production date showing that the concept for preparing uranium age dating reference material based on complete separation is valid. Detailed knowledge of the laboratory proceduresmore » used for uranium age dating allows the identification of possible improvements in the current protocols and the development of improved practice in the future. The availability of age dating reference materials as well as the evolvement of the age dating best-practice protocol will increase the relevance and applicability of age dating as part of the tool-kit available for nuclear forensic investigations.« less

Detection of special nuclear materials using prompt gamma-rays from fast and slow neutron-induced fission

NASA Astrophysics Data System (ADS)

Kane, Steven Ze

A complete system has been simulated using experimentally obtained input parameters for the detection of special nuclear materials (SNM). A variation of the associated particle imaging (API) technique, referred to as reverse associated particle imaging detection (RAPID), has been developed in the context of detecting 5-kg spherical samples of U-235 in cargo containers uniformly filled with wood (low-Z) or iron (high-Z) at densities ranging from 0.1 g/cm3 to 0.4 g/cm3, the maximal density for a uniformly fully loaded 40-ft standard cargo container. In addition, samples were located at the center of a given container to study worst-case scenarios. The RAPID technique allows for the interrogation of containers at neutron production rates between 1x108 neutrons/s and 4x108 neutrons/s, depending on cargo material and density. These rates are low enough to prevent transmutation of materials in cargo and radiation safety hazards are limited. The merit of performance for the system is the time to detect the threat material with 95% probability of detection and 10-4 false positive rate per interrogated voxel of cargo. The detection of 5-kg of U-235 was chosen because this quantity of material is near the lower limit of the amount of special nuclear material that might be used in a nuclear weapon. This is in contrast to the 25-kg suggested sensitivity proposed by the International Atomic Energy Agency (IAEA).

10 CFR 2.103 - Action on applications for byproduct, source, special nuclear material, facility and operator...

Code of Federal Regulations, 2013 CFR

2013-01-01

... nuclear material, facility and operator licenses. (a) If the Director, Office of Nuclear Reactor... repository operations area under parts 60 or 63 of this chapter, the Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Nuclear Material Safety and Safeguards, or...

10 CFR 2.103 - Action on applications for byproduct, source, special nuclear material, facility and operator...

Code of Federal Regulations, 2014 CFR

2014-01-01

... nuclear material, facility and operator licenses. (a) If the Director, Office of Nuclear Reactor... repository operations area under parts 60 or 63 of this chapter, the Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Nuclear Material Safety and Safeguards, or...

Material science as basis for nuclear medicine: Holmium irradiation for radioisotopes production

NASA Astrophysics Data System (ADS)

Usman, Ahmed Rufai; Khandaker, Mayeen Uddin; Haba, Hiromitsu; Otuka, Naohiko

2018-05-01

Material Science, being an interdisciplinary field, plays important roles in nuclear science. These applications are seen in weaponry, armoured vehicles, accelerator structure and development, semiconductor detectors, nuclear medicine and many more. Present study presents the applications of some metals in nuclear medicine (radioisotope production). The charged-particle-induced nuclear reactions by using cyclotrons or accelerators have become a very vital feature of the modern nuclear medicine. Realising the importance of excitation functions for the efficient production of medical radionuclides, some very high purity holmium metals are generally prepared or purchased for bombardment in nuclear accelerators. In the present work, various methods to obtain pure holmium for radioisotope production have been discussed while also presenting details of our present studies. From the experimental work of the present studies, some very high purity holmium foils have been used in the work for a comprehensive study of residual radionuclides production cross-sections. The study was performed using a stacked-foil activation technique combined with γ-ray spectrometry. The stack was bombarded with 50.4 MeV alpha particle beam from AVF cyclotron of RI Beam Factory, Nishina Centre for Accelerator-Based Science, RIKEN, Japan. The work produced thulium radionuclides useful in nuclear medicine.

LONG TERM OPERATION ISSUES FOR ELECTRICAL CABLE SYSTEMS IN NUCLEAR POWER PLANTS

DOE Office of Scientific and Technical Information (OSTI.GOV)

Fifield, Dr Leonard S; Duckworth, Robert C; Glass III, Dr. Samuel W.

Nuclear power plants contain hundreds of kilometers of electrical cables including cables used for power, for instrumentation, and for control. It is essential that safety-related cable systems continue to perform following a design-basis event. Wholesale replacement of electrical cables in existing plants facing licensing period renewal is both impractical and cost-prohibitive. It is therefore important to understand the long term aging of cable materials to have confidence that aged cables will perform when needed. It is equally important in support of cable aging management to develop methods to evaluate the health of installed cables and inform selective cable replacement decisions.more » The most common insulation materials for electrical cables in nuclear power plants are cross-linked polyethylene and ethylene-propylene rubber. The mechanical properties of these materials degrade over time in the presence of environmental stresses including heat, gamma irradiation, and moisture. Mechanical degradation of cable insulation beyond a certain threshold is unacceptable because it can lead to insulation cracking, exposure of energized conductors, arcing and burning or loss of the ability of the cable system to function during a design-basis accident. While thermal-, radiation-, and moisture-related degradation of polymer insulation materials has been extensively studied over the last few decades, questions remain regarding the long-term performance of cable materials in nuclear plant-specific environments. Identified knowledge gaps include an understanding of the temperature-dependence of activation energies for thermal damage and an understanding of the synergistic effects of radiation and thermal stress on polymer degradation. Many of the outstanding questions in the aging behavior of cable materials relate to the necessity of predicting long-term field degradation using accelerated aging results from the laboratory. Materials degrade faster under more extreme conditions, but extension of behavior to long term degradation under more mild conditions, such as those experienced by most installed cables in nuclear power plants, is complicated by the fact that different degradation mechanisms may be involved in extreme and mild scenarios. The discrepancy in predicted results from short term, more extreme exposure and actual results from longer term, more mild exposures can be counter intuitive. For instance, due to the attenuation of oxidation penetration in material samples rapidly aged through exposure to high temperatures, the bulk of the samples may be artificially protected from thermal aging. In another example, simultaneous exposure of cable insulation material to heat and radiation may actually lead to less damage at higher temperatures than may be observed at lower temperatures. The Light Water Reactor Sustainability program of the United States (US) Department of Energy Office (DOE) of Nuclear Energy is funding research to increase the predictive understanding of electrical cable material aging and degradation in existing nuclear power plants in support of continued safe operation of plants beyond their initial license periods. This research includes the evaluation and development of methods to assess installed cable condition.« less

Possibilities for Nuclear Photo-Science with Intense Lasers

DOE Office of Scientific and Technical Information (OSTI.GOV)

Barty, C J; Hartemann, F V; McNabb, D P

2006-06-26

The interaction of intense laser light with relativistic electrons can produce unique sources of high-energy x rays and gamma rays via Thomson scattering. ''Thomson-Radiated Extreme X-ray'' (T-REX) sources with peak photon brightness (photons per unit time per unit bandwidth per unit solid angle per unit area) that exceed that available from world's largest synchrotrons by more than 15 orders of magnitude are possible from optimally designed systems. Such sources offer the potential for development of ''nuclear photo-science'' applications in which the primary photon-atom interaction is with the nucleons and not the valence electrons. Applications include isotope-specific detection and imaging ofmore » materials, inverse density radiography, transmutation of nuclear waste and fundamental studies of nuclear structure. Because Thomson scattering cross sections are small, < 1 barn, the output from a T-REX source is optimized when the laser spot size and the electron spot size are minimized and when the electron and laser pulse durations are similar and short compared to the transit time through the focal region. The principle limitation to increased x-ray or gamma-ray brightness is ability to focus the electron beam. The effects of space charge on electron beam focus decrease approximately linearly with electron beam energy. For this reason, T-REX brightness increases rapidly as a function of the electron beam energy. As illustrated in Figure 1, above 100 keV these sources are unique in their ability to produce bright, narrow-beam, tunable, narrow-band gamma rays. New, intense, short-pulse, laser technologies for advanced T-REX sources are currently being developed at LLNL. The construction of a {approx}1 MeV-class machine with this technology is underway and will be used to excite nuclear resonance fluorescence in variety of materials. Nuclear resonance fluorescent spectra are unique signatures of each isotope and provide an ideal mechanism for identification of nuclear materials. With TREX it is possible to use NRF to provide high spatial resolution (micron scale) images of the isotopic distribution of all materials in a given object. Because of the high energy of the photons, imaging through dense and/or thick objects is possible. This technology will have applicability in many arenas including the survey of cargo for the presence of clandestine nuclear materials. It is also possible to address the more general radiographic challenge of imaging low-density objects that are shielded or placed behind high density objects. In this case, it is the NRF cross section and not the electron density of the material that provides contrast. Extensions of T-REX technology will be dependent upon the evolution of short pulse laser technology to high average powers. Concepts for sources that would produce 10's of kWs of gamma-rays by utilizing MW-class average-power, diode-pumped, short pulse lasers and energy recovery LINAC technology have been developed.« less

A Guide to Nuclear Weapons Phenomena and Effects Literature

DTIC Science & Technology

1984-10-31

and Disarmament Agency. An article entitled "Limited Nuclear War" in Scientific American (Reference ECE-14) is also of interest because of its rela... Sistems and the Aemosphere’-BCj=9. 43 Personne l; .-EP)- / 47 Civilian .S’ector and the .Environment, (ECE) 50 5 SPECIAL REFERENCE MATERIALS (R) ’<ൾ...approximations. DNA has sponsored the development of software for scientific and military applications of nuclear weapon phenomena and effects information

Development of MMC Gamma Detectors for Nuclear Analysis

NASA Astrophysics Data System (ADS)

Bates, C. R.; Pies, C.; Kempf, S.; Gastaldo, L.; Fleischmann, A.; Enss, C.; Friedrich, S.

2014-09-01

Non-destructive assay (NDA) of nuclear materials would benefit from gamma detectors with improved energy resolution in cases where line overlap in current Ge detectors limits NDA accuracy. We are developing metallic magnetic calorimeter gamma-detectors for this purpose by electroplating 150 m thick Au absorbers into microfabricated molds on top of Au:Er sensors. Initial tests under non-optimized conditions show an energy resolution of 200 eV FWHM at 60 keV. Monte Carlo simulations illustrate that this resolution is starting to be sufficient for direct detection of Pu in plutonium separated from spent nuclear fuel.

Performance of coincidence-based PSD on LiF/ZnS Detectors for Multiplicity Counting

DOE Office of Scientific and Technical Information (OSTI.GOV)

Robinson, Sean M.; Stave, Sean C.; Lintereur, Azaree

Abstract: Mass accountancy measurement is a nuclear nonproliferation application which utilizes coincidence and multiplicity counters to verify special nuclear material declarations. With a well-designed and efficient detector system, several relevant parameters of the material can be verified simultaneously. 6LiF/ZnS scintillating sheets may be used for this purpose due to a combination of high efficiency and short die-away times in systems designed with this material, but involve choices of detector geometry and exact material composition (e.g., the addition of Ni-quenching in the material) that must be optimized for the application. Multiplicity counting for verification of declared nuclear fuel mass involves neutronmore » detection in conditions where several neutrons arrive in a short time window, with confounding gamma rays. This paper considers coincidence-based Pulse-Shape Discrimination (PSD) techniques developed to work under conditions of high pileup, and the performance of these algorithms with different detection materials. Simulated and real data from modern LiF/ZnS scintillator systems are evaluated with these techniques and the relationship between the performance under pileup and material characteristics (e.g., neutron peak width and total light collection efficiency) are determined, to allow for an optimal choice of detector and material.« less

Development and characterization of lubricants for use near nuclear reactors in space vehicles

NASA Technical Reports Server (NTRS)

Robinson, G. L.; Akawie, R. I.; Gardos, M. N.; Krening, K. C.

1972-01-01

The synthesis and evaluation program was conducted to develop wide-temperature range lubricants suitable for use in space vehicles particularly in the vicinity of nuclear reactors. Synthetic approaches resulted in nonpolymeric, large molecular weight materials, all based on some combination of siloxane and aromatic groups. Evaluation of these materials indicated that certain tetramethyl and hexamethyl disiloxanes containing phenyl thiophenyl substituents are extremely promising with respect to radiation stability, wide temperature range, good lubricity, oxidation resistance and additive acceptance. The synthesis of fluids is discussed, and the equipment and methods used in evaluation are described, some of which were designed to evaluate micro-quantities of the synthesized lubricants.

Structural integrity of a confinement vessel for testing nuclear fuels for space propulsion

NASA Astrophysics Data System (ADS)

Bergmann, V. L.

Nuclear propulsion systems for rockets could significantly reduce the travel time to distant destinations in space. However, long before such a concept can become reality, a significant effort must be invested in analysis and ground testing to guide the development of nuclear fuels. Any testing in support of development of nuclear fuels for space propulsion must be safely contained to prevent the release of radioactive materials. This paper describes analyses performed to assess the structural integrity of a test confinement vessel. The confinement structure, a stainless steel pressure vessel with bolted flanges, was designed for operating static pressures in accordance with the ASME Boiler and Pressure Vessel Code. In addition to the static operating pressures, the confinement barrier must withstand static overpressures from off-normal conditions without releasing radioactive material. Results from axisymmetric finite element analyses are used to evaluate the response of the confinement structure under design and accident conditions. For the static design conditions, the stresses computed from the ASME code are compared with the stresses computed by the finite element method.

75 FR 44072 - Export and Import of Nuclear Equipment and Material; Updates and Clarifications

Federal Register 2010, 2011, 2012, 2013, 2014

2010-07-28

... Energy Act. Retransfers of special nuclear material produced through the use of U.S.-obligated material... the Atomic Energy Act that apply to imports of special nuclear, source or byproduct material are... NUCLEAR REGULATORY COMMISSION 10 CFR Part 110 [NRC-2008-0567] RIN 3150-AI16 Export and Import of...

Production of an English/Russian glossary of terminology for nuclear materials control and accounting

DOE Office of Scientific and Technical Information (OSTI.GOV)

Schachowskoj, S.; Smith, H.A. Jr.

The program plans for Former Soviet Union National Nuclear Materials Control and Accounting (MC and A) Systems Enhancements call for the development of an English/Russian Glossary of MC and A terminology. This glossary was envisioned as an outgrowth of the many interactions, training sessions, and other talking and writing exercises that would transpire in the course of carrying out these programs. This report summarizes the status of the production of this glossary, the most recent copy of which is attached to this report. The glossary contains over 950 terms and acronyms associated with nuclear material control and accounting for safeguardsmore » and nonproliferation. This document is organized as follows: English/Russian glossary of terms and acronyms; Russian/English glossary of terms and acronyms; English/Russian glossary of acronyms; and Russian/English glossary of acronyms.« less

Developing an in-situ Detector of Neutron-Induced Fission for Actinide Sputtering Characterization

NASA Astrophysics Data System (ADS)

Fellers, Deion

2016-09-01

The physical mechanism describing the transfer of large amounts of energy due to fission in a material is not well understood and represents one of the modern challenges facing nuclear scientists, with applications including nuclear energy and national defense. Fission fragments cause damage to the material from sputtering of matter as they pass through or near the material's surface. We have developed a new technique at the Los Alamos Neutron Science Center for characterizing the ejecta by using ultracold neutrons (neutrons with kinetic energy less than 300 neV) to induce fission at finely controlled depths in an actinide. This program will ultimately provide a detailed description of the properties of the sputtered particles as a function of the depth of the fission in the material. A key component of this project is accurately quantifying the number of neutron induced fissions in the sample. This poster depicts the development of an in-situ detector of neutron-induced fission for the AShES (Actinide Sputtering from ultracold neutron Exposure at the Surface) experiment.

Emissivity of Candidate Materials for VHTR Applicationbs: Role of Oxidation and Surface Modification Treatments

DOE Office of Scientific and Technical Information (OSTI.GOV)

Sridharan, Kumar; Allen, Todd; Anderson, Mark

The Generation IV (GEN IV) Nuclear Energy Systems Initiative was instituted by the Department of Energy (DOE) with the goal of researching and developing technologies and materials necessary for various types of future reactors. These GEN IV reactors will employ advanced fuel cycles, passive safety systems, and other innovative systems, leading to significant differences between these future reactors and current water-cooled reactors. The leading candidate for the Next Generation Nuclear Plant (NGNP) to be built at Idaho National Lab (INL) in the United States is the Very High Temperature Reactor (VHTR). Due to the high operating temperatures of the VHTR,more » the Reactor Pressure Vessel (RPV) will partially rely on heat transfer by radiation for cooling. Heat expulsion by radiation will become all the more important during high temperature excursions during off-normal accident scenarios. Radiant power is dictated by emissivity, a material property. The NGNP Materials Research and Development Program Plan [1] has identified emissivity and the effects of high temperature oxide formation on emissivity as an area of research towards the development of the VHTR.« less

Historical perspectives - The role of the NASA Lewis Research Center in the national space nuclear power programs

NASA Technical Reports Server (NTRS)

Bloomfield, H. S.; Sovie, R. J.

1991-01-01

The history of the NASA Lewis Research Center's role in space nuclear power programs is reviewed. Lewis has provided leadership in research, development, and the advancement of space power and propulsion systems. Lewis' pioneering efforts in nuclear reactor technology, shielding, high temperature materials, fluid dynamics, heat transfer, mechanical and direct energy conversion, high-energy propellants, electric propulsion and high performance rocket fuels and nozzles have led to significant technical and management roles in many natural space nuclear power and propulsion programs.

Historical perspectives: The role of the NASA Lewis Research Center in the national space nuclear power programs

NASA Technical Reports Server (NTRS)

Bloomfield, H. S.; Sovie, R. J.

1991-01-01

The history of the NASA Lewis Research Center's role in space nuclear power programs is reviewed. Lewis has provided leadership in research, development, and the advancement of space power and propulsion systems. Lewis' pioneering efforts in nuclear reactor technology, shielding, high temperature materials, fluid dynamics, heat transfer, mechanical and direct energy conversion, high-energy propellants, electric propulsion and high performance rocket fuels and nozzles have led to significant technical and management roles in many national space nuclear power and propulsion programs.

Nuclear Fuels & Materials Spotlight Volume 5

DOE Office of Scientific and Technical Information (OSTI.GOV)

Petti, David Andrew

2016-10-01

As the nation's nuclear energy laboratory, Idaho National Laboratory brings together talented people and specialized nuclear research capability to accomplish our mission. This edition of the Nuclear Fuels and Materials Division Spotlight provides an overview of some of our recent accomplishments in research and capability development. These accomplishments include: • Evaluation and modeling of light water reactor accident tolerant fuel concepts • Status and results of recent TRISO-coated particle fuel irradiations, post-irradiation examinations, high-temperature safety testing to demonstrate the accident performance of this fuel system, and advanced microscopy to improve the understanding of fission product transport in this fuel system.more » • Improvements in and applications of meso and engineering scale modeling of light water reactor fuel behavior under a range of operating conditions and postulated accidents (e.g., power ramping, loss of coolant accident, and reactivity initiated accidents) using the MARMOT and BISON codes. • Novel measurements of the properties of nuclear (actinide) materials under extreme conditions, (e.g. high pressure, low/high temperatures, high magnetic field) to improve the scientific understanding of these materials. • Modeling reactor pressure vessel behavior using the GRIZZLY code. • New methods using sound to sense temperature inside a reactor core. • Improved experimental capabilities to study the response of fusion reactor materials to a tritium plasma. Throughout Spotlight, you'll find examples of productive partnerships with academia, industry, and government agencies that deliver high-impact outcomes. The work conducted at Idaho National Laboratory helps spur innovation in nuclear energy applications that drive economic growth and energy security. We appreciate your interest in our work here at Idaho National Laboratory, and hope that you find this issue informative.« less

Nuclear materials stewardship: Our enduring mission

DOE Office of Scientific and Technical Information (OSTI.GOV)

Isaacs, T.H.

1998-12-31

The US Department of Energy (DOE) and its predecessors have handled a remarkably wide variety of nuclear materials over the past 50 yr. Two fundamental changes have occurred that shape the current landscape regarding nuclear materials. If one recognizes the implications and opportunities, one sees that the stewardship of nuclear materials will be a fundamental and important job of the DOE for the foreseeable future. The first change--the breakup of the Soviet Union and the resulting end to the nuclear arms race--altered US objectives. Previously, the focus was on materials production, weapon design, nuclear testing, and stockpile enhancements. Now themore » attention is on dismantlement of weapons, excess special nuclear material inventories, accompanying increased concern over the protection afforded to such materials; new arms control measures; and importantly, maintenance of the safety and reliability of the remaining arsenal without testing. The second change was the raised consciousness and sense of responsibility for dealing with the environmental legacies of past nuclear arms programs. Recognition of the need to clean up radioactive contamination, manage the wastes, conduct current operations responsibly, and restore the environment have led to the establishment of what is now the largest program in the DOE. Two additional features add to the challenge and drive the need for recognition of nuclear materials stewardship as a fundamental, enduring, and compelling mission of the DOE. The first is the extraordinary time frames. No matter what the future of nuclear weapons and no matter what the future of nuclear power, the DOE will be responsible for most of the country`s nuclear materials and wastes for generations. Even if the Yucca Mountain program is successful and on schedule, it will last more than 100 yr. Second, the use, management, and disposition of nuclear materials and wastes affect a variety of nationally important and diverse objectives, from national security to the future of nuclear power in this country and abroad, to the care of the environment. Sometimes these objectives are in concert, but often they are seen as competing or being in conflict. By recognizing the corporate responsibility for these materials and the accompanying programs, national decision making will be improved.« less

DOE Office of Scientific and Technical Information (OSTI.GOV)

Muslim, Dato’ Dr Noramly, E-mail: noramlymuslim@yahoo.com

As Malaysia progresses towards 2020, the depleting resource of oil and gas has forced a re-look at alternatives to replace fossil fuels as energy sources. Among the viable options is nuclear energy, enabling us to meet energy needs and sustain national development in the twenty-first century. Three essential steps Malaysia must take to introduce nuclear power into its energy mix are: energy planning, infrastructure development, and deployment. Malaysia has to face a series of challenges, including public acceptance, waste management, minimizing proliferation risk, and ensuring the security of nuclear plants and materials. Timely development of qualified and competent manpower ismore » a key limiting factor in the development and transfer of nuclear technologies — and education and training take time, effort and money. There is a need for political will. Within the Asian region, China, Korea and Japan are in the forefront in utilizing nuclear power to meet electricity demands. Countries such as UAE, Bangladesh, Vietnam and Turkey are moving ahead with the nuclear option for electricity generation and they have begun planning and construction of nuclear power plants. Against this backdrop, what are Malaysia’s moves? This paper discusses various options and challenges, obstacles and repercussions in meeting future energy demands.« less

MC and A instrumentation catalog

DOE Office of Scientific and Technical Information (OSTI.GOV)

Neymotin, L.; Sviridova, V.

1998-06-01

In 1981 and 1985, two editions of a catalog of non-destructive nuclear measurement instrumentation, and material control and surveillance equipment, were published by Brookhaven National Laboratory (BNL). The last edition of the catalog included one hundred and twenty-five entries covering a wide range of devices developed in the US and abroad. More than ten years have elapsed since the publication of the more recent Catalog. Devices described in it have undergone significant modifications, and new devices have been developed. Therefore, in order to assist specialists in the field of Material Control and Accounting (MC and A), a new catalog hasmore » been created. Work on this instrumentation catalog started in 1997 as a cooperative effort of Brookhaven National Laboratory (BNL), operated by Brookhaven Science Associates under contract to the US Department of Energy, and the All-Russian Research Institute of Automatics (VNIIA), subordinate institute of the Atomic Energy Ministry of the Russian Federation, within the collaborative US-Russia Material Protection, Control, and Accounting (MPC and A) Program. Most of the equipment included in the Catalog are non-destructive assay (NDA) measurement devices employed for purposes of accounting, confirmation, and verification of nuclear materials. Other devices also included in the Catalog are employed in the detection and deterrence of unauthorized access to or removal of nuclear materials (material control: containment and surveillance). Equipment found in the Catalog comprises either: (1) complete devices or systems that can be used for MC and A applications; or (2) parts or components of complete systems, such as multi-channel analyzers, detectors, neutron generators, and software. All devices are categorized by their status of development--from prototype to serial production.« less

Material Protection, Accounting, and Control Technologies (MPACT) Advanced Integration Roadmap

DOE Office of Scientific and Technical Information (OSTI.GOV)

Miller, Mike; Cipiti, Ben; Demuth, Scott Francis

2017-01-30

The development of sustainable advanced nuclear fuel cycles is a long-term goal of the Office of Nuclear Energy’s (DOE-NE) Fuel Cycle Technologies program. The Material Protection, Accounting, and Control Technologies (MPACT) campaign is supporting research and development (R&D) of advanced instrumentation, analysis tools, and integration methodologies to meet this goal (Miller, 2015). This advanced R&D is intended to facilitate safeguards and security by design of fuel cycle facilities. The lab-scale demonstration of a virtual facility, distributed test bed, that connects the individual tools being developed at National Laboratories and university research establishments, is a key program milestone for 2020. Thesemore » tools will consist of instrumentation and devices as well as computer software for modeling, simulation and integration.« less

Material Protection, Accounting, and Control Technologies (MPACT) Advanced Integration Roadmap

DOE Office of Scientific and Technical Information (OSTI.GOV)

Durkee, Joe W.; Cipiti, Ben; Demuth, Scott Francis

The development of sustainable advanced nuclear fuel cycles is a long-term goal of the Office of Nuclear Energy’s (DOE-NE) Fuel Cycle Technologies program. The Material Protection, Accounting, and Control Technologies (MPACT) campaign is supporting research and development (R&D) of advanced instrumentation, analysis tools, and integration methodologies to meet this goal (Miller, 2015). This advanced R&D is intended to facilitate safeguards and security by design of fuel cycle facilities. The lab-scale demonstration of a virtual facility, distributed test bed, that connects the individual tools being developed at National Laboratories and university research establishments, is a key program milestone for 2020. Thesemore » tools will consist of instrumentation and devices as well as computer software for modeling, simulation and integration.« less

Development of ASTM Standard for SiC-SiC Joint Testing Final Scientific/Technical Report

DOE Office of Scientific and Technical Information (OSTI.GOV)

Jacobsen, George; Back, Christina

2015-10-30

As the nuclear industry moves to advanced ceramic based materials for cladding and core structural materials for a variety of advanced reactors, new standards and test methods are required for material development and licensing purposes. For example, General Atomics (GA) is actively developing silicon carbide (SiC) based composite cladding (SiC-SiC) for its Energy Multiplier Module (EM2), a high efficiency gas cooled fast reactor. Through DOE funding via the advanced reactor concept program, GA developed a new test method for the nominal joint strength of an endplug sealed to advanced ceramic tubes, Fig. 1-1, at ambient and elevated temperatures called themore » endplug pushout (EPPO) test. This test utilizes widely available universal mechanical testers coupled with clam shell heaters, and specimen size is relatively small, making it a viable post irradiation test method. The culmination of this effort was a draft of an ASTM test standard that will be submitted for approval to the ASTM C28 ceramic committee. Once the standard has been vetted by the ceramics test community, an industry wide standard methodology to test joined tubular ceramic components will be available for the entire nuclear materials community.« less

Probabilistic accident consequence uncertainty analysis -- Uncertainty assessment for deposited material and external doses. Volume 2: Appendices

DOE Office of Scientific and Technical Information (OSTI.GOV)

Goossens, L.H.J.; Kraan, B.C.P.; Cooke, R.M.

1997-12-01

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the Commission of the European Communities began cosponsoring a joint uncertainty analysis of the two codes. The ultimate objective of this joint effort was to systematically develop credible and traceable uncertainty distributions for the respective code input variables. A formal expert judgment elicitation and evaluation process was identified as the best technology available for developing a library ofmore » uncertainty distributions for these consequence parameters. This report focuses on the results of the study to develop distribution for variables related to the MACCS and COSYMA deposited material and external dose models. This volume contains appendices that include (1) a summary of the MACCS and COSYMA consequence codes, (2) the elicitation questionnaires and case structures, (3) the rationales and results for the panel on deposited material and external doses, (4) short biographies of the experts, and (5) the aggregated results of their responses.« less

In-pile Thermal Conductivity Characterization with Time Resolved Raman

DOE Office of Scientific and Technical Information (OSTI.GOV)

Wang, Xinwei; Hurley, David H.

The project is designed to achieve three objectives: (1) Develop a novel time resolved Raman technology for direct measurement of fuel and cladding thermal conductivity. (2) Validate and improve the technology development by measuring ceramic materials germane to the nuclear industry. (3) Conduct instrumentation development to integrate optical fiber into our sensing system for eventual in-pile measurement. We have developed three new techniques: time-domain differential Raman (TD-Raman), frequency-resolved Raman (FR-Raman), and energy transport state-resolved Raman (ET-Raman). The TD-Raman varies the laser heating time and does simultaneous Raman thermal probing, the FR-Raman probes the material’s thermal response under periodical laser heatingmore » of different frequencies, and the ET-Raman probes the thermal response under steady and pulsed laser heating. The measurement capacity of these techniques have been fully assessed and verified by measuring micro/nanoscale materials. All these techniques do not need the data of laser absorption and absolute material temperature rise, yet still be able to measure the thermal conductivity and thermal diffusivity with unprecedented accuracy. It is expected they will have broad applications for in-pile thermal characterization of nuclear materials based on pure optical heating and sensing.« less

Nuclear thermal propulsion technology: Results of an interagency panel in FY 1991

NASA Technical Reports Server (NTRS)

Clark, John S.; Mcdaniel, Patrick; Howe, Steven; Helms, Ira; Stanley, Marland

1993-01-01

NASA LeRC was selected to lead nuclear propulsion technology development for NASA. Also participating in the project are NASA MSFC and JPL. The U.S. Department of Energy will develop nuclear technology and will conduct nuclear component, subsystem, and system testing at appropriate DOE test facilities. NASA program management is the responsibility of NASA/RP. The project includes both nuclear electric propulsion (NEP) and nuclear thermal propulsion (NTP) technology development. This report summarizes the efforts of an interagency panel that evaluated NTP technology in 1991. Other panels were also at work in 1991 on other aspects of nuclear propulsion, and the six panels worked closely together. The charters for the other panels and some of their results are also discussed. Important collaborative efforts with other panels are highlighted. The interagency (NASA/DOE/DOD) NTP Technology Panel worked in 1991 to evaluate nuclear thermal propulsion concepts on a consistent basis. Additionally, the panel worked to continue technology development project planning for a joint project in nuclear propulsion for the Space Exploration Initiative (SEI). Five meetings of the panel were held in 1991 to continue the planning for technology development of nuclear thermal propulsion systems. The state-of-the-art of the NTP technologies was reviewed in some detail. The major technologies identified were as follows: fuels, coatings, and other reactor technologies; materials; instrumentation, controls, health monitoring and management, and associated technologies; nozzles; and feed system technology, including turbopump assemblies.

Computation of Thermodynamic Equilibria Pertinent to Nuclear Materials in Multi-Physics Codes

NASA Astrophysics Data System (ADS)

Piro, Markus Hans Alexander

Nuclear energy plays a vital role in supporting electrical needs and fulfilling commitments to reduce greenhouse gas emissions. Research is a continuing necessity to improve the predictive capabilities of fuel behaviour in order to reduce costs and to meet increasingly stringent safety requirements by the regulator. Moreover, a renewed interest in nuclear energy has given rise to a "nuclear renaissance" and the necessity to design the next generation of reactors. In support of this goal, significant research efforts have been dedicated to the advancement of numerical modelling and computational tools in simulating various physical and chemical phenomena associated with nuclear fuel behaviour. This undertaking in effect is collecting the experience and observations of a past generation of nuclear engineers and scientists in a meaningful way for future design purposes. There is an increasing desire to integrate thermodynamic computations directly into multi-physics nuclear fuel performance and safety codes. A new equilibrium thermodynamic solver is being developed with this matter as a primary objective. This solver is intended to provide thermodynamic material properties and boundary conditions for continuum transport calculations. There are several concerns with the use of existing commercial thermodynamic codes: computational performance; limited capabilities in handling large multi-component systems of interest to the nuclear industry; convenient incorporation into other codes with quality assurance considerations; and, licensing entanglements associated with code distribution. The development of this software in this research is aimed at addressing all of these concerns. The approach taken in this work exploits fundamental principles of equilibrium thermodynamics to simplify the numerical optimization equations. In brief, the chemical potentials of all species and phases in the system are constrained by estimates of the chemical potentials of the system components at each iterative step, and the objective is to minimize the residuals of the mass balance equations. Several numerical advantages are achieved through this simplification. In particular, computational expense is reduced and the rate of convergence is enhanced. Furthermore, the software has demonstrated the ability to solve systems involving as many as 118 component elements. An early version of the code has already been integrated into the Advanced Multi-Physics (AMP) code under development by the Oak Ridge National Laboratory, Los Alamos National Laboratory, Idaho National Laboratory and Argonne National Laboratory. Keywords: Engineering, Nuclear -- 0552, Engineering, Material Science -- 0794, Chemistry, Mathematics -- 0405, Computer Science -- 0984

DOE Office of Scientific and Technical Information (OSTI.GOV)

Dunn, Darrell; Poinssot, Christophe; Begg, Bruce

Management of nuclear waste remains an important international topic that includes reprocessing of commercial nuclear fuel, waste-form design and development, storage and disposal packaging, the process of repository site selection, system design, and performance assessment. Requirements to manage and dispose of materials from the production of nuclear weapons, and the renewed interest in nuclear power, in particular through the Generation IV Forum and the Advanced Fuel Cycle Initiative, can be expected to increase the need for scientific advances in waste management. A broad range of scientific and engineering disciplines is necessary to provide safe and effective solutions and address complexmore » issues. This volume offers an interdisciplinary perspective on materials-related issues associated with nuclear waste management programs. Invited and contributed papers cover a wide range of topics including studies on: spent fuel; performance assessment and models; waste forms for low- and intermediate-level waste; ceramic and glass waste forms for plutonium and high-level waste; radionuclides; containers and engineered barriers; disposal environments and site characteristics; and partitioning and transmutation.« less

Performance study of the neutron-TPC

NASA Astrophysics Data System (ADS)

Huang, Meng; Li, Yulan; Niu, Libo; Deng, Zhi; Cheng, Xiaolei; He, Li; Zhang, Hongyan; Fu, Jianqiang; Yan, Yangyang; Cai, Yiming; Li, Yuanjing

2017-02-01

Fast neutron spectrometers will play an important role in the future of the nuclear industry and nuclear physics experiments, in tasks such as fast neutron reactor monitoring, thermo-nuclear fusion plasma diagnostics, nuclear reaction cross-section measurement, and special nuclear material detection. Recently, a new fast neutron spectrometer based on a GEM (Gas Electron Multiplier amplification)-TPC (Time Projection Chamber), named the neutron-TPC, has been under development at Tsinghua University. It is designed to have a high energy resolution, high detection efficiency, easy access to the medium material, an outstanding n/γ suppression ratio, and a wide range of applications. This paper presents the design, test, and experimental study of the neutron-TPC. Based on the experimental results, the energy resolution (FWHM) of the neutron-TPC can reach 15.7%, 10.3% and 7.0% with detection efficiency higher than 10-5 for 1.2 MeV, 1.81 MeV and 2.5 MeV neutrons respectively. Supported by National Natural Science Foundation of China (11275109)

Study of activation data of metal samples from LDEF-1 and Spacelab-2

NASA Technical Reports Server (NTRS)

Laird, C. E.

1994-01-01

Gamma-ray spectra obtained from samples flown aboard the Long Duration Exposure Facility have been analyzed to obtain the nuclear species produced in this material by the interaction of this material with protons and neutrons in this material by the interaction of this material with protons and neutrons encountered in its 69 month orbital flight as well as to quantify the specific activity (pCi/kg) of these nuclear species. This quantification requires accurate corrections of efficiency, self-attenuation, and background. Plans have been developed for archival of the spectra in a form readily accessible to the scientific, engineering and technical community engaged in space research and application. Work has been initiated in the process of estimating the flux of activating particles encountered by material at various locations of the spacecraft.

Lightweight Radiator for in Space Nuclear Electric Propulsion

NASA Technical Reports Server (NTRS)

Craven, Paul; Tomboulian, Briana; SanSoucie, Michael

2014-01-01

Nuclear electric propulsion (NEP) is a promising option for high-speed in-space travel due to the high energy density of nuclear fission power sources and efficient electric thrusters. Advanced power conversion technologies may require high operating temperatures and would benefit from lightweight radiator materials. Radiator performance dictates power output for nuclear electric propulsion systems. Game-changing propulsion systems are often enabled by novel designs using advanced materials. Pitch-based carbon fiber materials have the potential to offer significant improvements in operating temperature, thermal conductivity, and mass. These properties combine to allow advances in operational efficiency and high temperature feasibility. An effort at the NASA Marshall Space Flight Center to show that woven high thermal conductivity carbon fiber mats can be used to replace standard metal and composite radiator fins to dissipate waste heat from NEP systems is ongoing. The goals of this effort are to demonstrate a proof of concept, to show that a significant improvement of specific power (power/mass) can be achieved, and to develop a thermal model with predictive capabilities making use of constrained input parameter space. A description of this effort is presented.

National cyclotron centre at the Institute for Nuclear Research and Nuclear Energy

NASA Astrophysics Data System (ADS)

Tonev, D.; Goutev, N.; Asova, G.; Artinyan, A.; Demerdjiev, A.; Georgiev, L. S.; Yavahchova, M.; Bashev, V.; Genchev, S. G.; Geleva, E.; Mincheva, M.; Nikolov, A.; Dimitrov, D. T.

2018-05-01

An accelerator laboratory is presently under construction in Sofia at the Institute for Nuclear Research and Nuclear Energy. The laboratory will use a TR24 type of cyclotron, which provides a possibility to accelerate a proton beam with an energy of 15 to 24 MeV and current of up to 0.4 mA. An accelerator with such parameters allows to produce a large variety of radioisotopes for development of radiopharmaceuticals. The most common radioisotopes that can be produced with such a cyclotron are PET isotopes like: 11C, 13N, 15O, 18F, 124I, 64Cu, 68Ge/68Ga, and SPECT isotopes like: 123I, 111In, 67Ga, 57Co, 99mTc. Our aim is to use the cyclotron facility for research in the fields of radiopharmacy, radiochemistry, radiobiology, nuclear physics, materials sciences, applied research, new materials and for education in all these fields including nuclear energy. Presently we perform investigations in the fields of target design for production of radioisotopes, shielding and radioprotection, new ion sources etc.

International Safeguards and the Pacific Northwest National Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

Olsen, Khris B.; Smith, Leon E.; Frazar, Sarah L.

Established in 1965, Pacific Northwest National Laboratory’s (PNNL) strong technical ties and shared heritage with the nearby U.S. Department of Energy Hanford Site were central to the early development of expertise in nuclear fuel cycle signatures, separations chemistry, plutonium chemistry, environmental monitoring, modeling and analysis of reactor systems, and nuclear material safeguards and security. From these Hanford origins, PNNL has grown into a multi-program science and engineering enterprise that utilizes this diversity to strengthen the international safeguards regime. Today, PNNL supports the International Atomic Energy Agency (IAEA) in its mission to provide assurances to the international community that nations domore » not use nuclear materials and equipment outside of peaceful uses. PNNL also serves in the IAEA’s Network of Analytical Laboratories (NWAL) by providing analysis of environmental samples gathered around the world. PNNL is involved in safeguards research and development activities in support of many U.S. Government programs such as the National Nuclear Security Administration’s (NNSA) Office of Research and Development, NNSA Office of Nonproliferation and Arms Control, and the U.S. Support Program to IAEA Safeguards. In addition to these programs, PNNL invests internal resources including safeguards-specific training opportunities for staff, and laboratory-directed research and development funding to further ideas that may grow into new capabilities. This paper and accompanying presentation highlight some of PNNL’s contributions in technology development, implementation concepts and approaches, policy, capacity building, and human capital development, in the field of international safeguards.« less

Leveraging existing information for use in a National Nuclear Forensics Library (NNFL)

DOE Office of Scientific and Technical Information (OSTI.GOV)

Davydov, Jerry; Dion, Heather; LaMont, Stephen

A National Nuclear Forensics Library (NNFL) assists a State to assess whether nuclear material encountered out of regulatory control is of domestic or international origin. And by leveraging nuclear material registries, nuclear enterprise records, and safeguards accountancy information, as well as existing domestic technical capability and subject-matter domain expertise, states can better assess the effort required for setting up an NNFL. For states who are largely recipients of nuclear and radiological materials and have no internal production capabilities may create an NNFL that relies on existing information rather than carry out advanced analyses on domestic materials.

Leveraging existing information for use in a National Nuclear Forensics Library (NNFL)

DOE PAGES

Davydov, Jerry; Dion, Heather; LaMont, Stephen; ...

2015-12-16

A National Nuclear Forensics Library (NNFL) assists a State to assess whether nuclear material encountered out of regulatory control is of domestic or international origin. And by leveraging nuclear material registries, nuclear enterprise records, and safeguards accountancy information, as well as existing domestic technical capability and subject-matter domain expertise, states can better assess the effort required for setting up an NNFL. For states who are largely recipients of nuclear and radiological materials and have no internal production capabilities may create an NNFL that relies on existing information rather than carry out advanced analyses on domestic materials.

Functions of an engineered barrier system for a nuclear waste repository in basalt

NASA Astrophysics Data System (ADS)

Coons, W. E.; Moore, E. L.; Smith, M. J.; Kaser, J. D.

1980-01-01

The functions of components selected for an engineered barrier system for a nuclear waste repository in basalt are defined providing a focal point for barrier material research and development by delineating the purpose and operative lifetime of each component of the engineered system. A five component system (comprised of waste form, canister, buffer, overpack, and tailored backfill) is discussed. Redundancy is provided by subsystems of physical and chemical barriers which act in concert with the geology to provide a formidable barrier to transport of hazardous materials to the biosphere. The barrier system is clarified by examples pertinent to storage in basalt, and a technical approach to barrier design and material selection is proposed.

Determine Important Nuclear Fragmentation Processes for Space Radiation Protection in Human Space Explorations

NASA Technical Reports Server (NTRS)

Lin, Zi-wei

2004-01-01

Space radiation from cosmic ray particles is one of the main challenges for long-term human space explorations such as a permanent moon base or a trip to Mars. Material shielding may provide significant radiation protection to astronauts, and models have been developed in order to evaluate the effectiveness of different shielding materials and to predict radiation environment inside the spacecraft. In this study we determine the nuclear fragmentation cross sections which will most effect the radiation risk behind typical radiation shielding materials. These cross sections thus need more theoretical studies and accurate experimental measurements in order for us to more precisely predict the radiation risk in human space explorations.

Determine Important Nuclear Fragmentation Processes for Space Radiation Protection in Human Space Explorations

NASA Technical Reports Server (NTRS)

Lin, Zi-Wei

2004-01-01

Space radiation from cosmic ray particles is one of the main challenges for long-term human space explorations such as a permanent moon base or a trip to Mars. Material shielding may provide significant radiation protection to astronauts, and models have been developed in order to evaluate the effectiveness of different shielding materials and to predict radiation environment inside the spacecraft. In this study we determine the nuclear fragmentation cross sections which will most affect the radiation risk behind typical radiation shielding materials. These cross sections thus need more theoretical studies and accurate experimental measurements in order for us to more precisely predict the radiation risk in human space exploration.

Determine Important Nuclear Fragmentation Processes for Space Radiation Protection in Human Space Explorations

NASA Technical Reports Server (NTRS)

Lin, Zi-Wei

2004-01-01

Space radiation from cosmic ray particles is one of the main challenges for long-term human space explorations such as a permanent moon base or a trip to Mars. Material shielding may provide significant radiation protection to astronauts, and models have been developed in order to evaluate the effectiveness of different shielding materials and to predict radiation environment inside the spacecraft. In this study we determine the nuclear fragmentation cross sections which will most affect the radiation risk behind typical radiation shielding materials. These cross sections thus need more theoretical studies and accurate experimental measurements in order for us to more precisely predict the radiation risk in human space explorations.

Nuclear radiation problems, unmanned thermionic reactor ion propulsion spacecraft

NASA Technical Reports Server (NTRS)

Mondt, J. F.; Sawyer, C. D.; Nakashima, A.

1972-01-01

A nuclear thermionic reactor as the electric power source for an electric propulsion spacecraft introduces a nuclear radiation environment that affects the spacecraft configuration, the use and location of electrical insulators and the science experiments. The spacecraft is conceptually configured to minimize the nuclear shield weight by: (1) a large length to diameter spacecraft; (2) eliminating piping penetrations through the shield; and (3) using the mercury propellant as gamma shield. Since the alumina material is damaged by the high nuclear radiation environment in the reactor it is desirable to locate the alumina insulator outside the reflector or develop a more radiation resistant insulator.

75 FR 25301 - Nuclear Fuel Services, Inc.; Environmental Assessment and Finding of No Significant Impact for...

Federal Register 2010, 2011, 2012, 2013, 2014

2010-05-07

... procedures for storing and handling radioactive materials. Thus, the impacts under the ``no action... of Special Nuclear Material AGENCY: Nuclear Regulatory Commission. ACTION: Environmental Assessment... Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Mail Stop EBB-2C40M, Rockville, MD...

10 CFR 11.11 - General requirements.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 1 2011-01-01 2011-01-01 false General requirements. 11.11 Section 11.11 Energy NUCLEAR... SPECIAL NUCLEAR MATERIAL Requirements for Special Nuclear Material Access Authorization § 11.11 General..., formula quantities of special nuclear material (as defined in part 73 of this chapter) subject to the...

10 CFR 150.16 - Submission to Commission of nuclear material transaction reports.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Submission to Commission of nuclear material transaction reports. 150.16 Section 150.16 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Authority in Agreement States § 150.16 Submission to Commission of nuclear material transaction reports. (a...

10 CFR 150.16 - Submission to Commission of nuclear material transaction reports.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Submission to Commission of nuclear material transaction reports. 150.16 Section 150.16 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Authority in Agreement States § 150.16 Submission to Commission of nuclear material transaction reports. (a...

10 CFR 150.16 - Submission to Commission of nuclear material transaction reports.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Submission to Commission of nuclear material transaction reports. 150.16 Section 150.16 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Authority in Agreement States § 150.16 Submission to Commission of nuclear material transaction reports. (a...

10 CFR 11.11 - General requirements.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false General requirements. 11.11 Section 11.11 Energy NUCLEAR... SPECIAL NUCLEAR MATERIAL Requirements for Special Nuclear Material Access Authorization § 11.11 General..., formula quantities of special nuclear material (as defined in part 73 of this chapter) subject to the...

10 CFR 11.11 - General requirements.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 1 2012-01-01 2012-01-01 false General requirements. 11.11 Section 11.11 Energy NUCLEAR... SPECIAL NUCLEAR MATERIAL Requirements for Special Nuclear Material Access Authorization § 11.11 General..., formula quantities of special nuclear material (as defined in part 73 of this chapter) subject to the...

10 CFR 150.16 - Submission to Commission of nuclear material transaction reports.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Submission to Commission of nuclear material transaction reports. 150.16 Section 150.16 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Authority in Agreement States § 150.16 Submission to Commission of nuclear material transaction reports. (a...

10 CFR 11.11 - General requirements.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 1 2014-01-01 2014-01-01 false General requirements. 11.11 Section 11.11 Energy NUCLEAR... SPECIAL NUCLEAR MATERIAL Requirements for Special Nuclear Material Access Authorization § 11.11 General..., formula quantities of special nuclear material (as defined in part 73 of this chapter) subject to the...

10 CFR 11.11 - General requirements.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 1 2013-01-01 2013-01-01 false General requirements. 11.11 Section 11.11 Energy NUCLEAR... SPECIAL NUCLEAR MATERIAL Requirements for Special Nuclear Material Access Authorization § 11.11 General..., formula quantities of special nuclear material (as defined in part 73 of this chapter) subject to the...

10 CFR 76.117 - Special nuclear material of low strategic significance-Category III.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Special nuclear material of low strategic significance-Category III. 76.117 Section 76.117 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.117 Special nuclear material of low strategic...

10 CFR 76.115 - Special nuclear material of moderate strategic significance-Category II.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Special nuclear material of moderate strategic significance-Category II. 76.115 Section 76.115 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.115 Special nuclear material of moderate...

10 CFR 150.17 - Submission to Commission of nuclear material status reports.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Submission to Commission of nuclear material status reports. 150.17 Section 150.17 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Authority in Agreement States § 150.17 Submission to Commission of nuclear material status reports. (a...

10 CFR 76.117 - Special nuclear material of low strategic significance-Category III.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Special nuclear material of low strategic significance-Category III. 76.117 Section 76.117 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.117 Special nuclear material of low strategic...

41 CFR 101-42.1102-4 - Nuclear Regulatory Commission-controlled materials.

Code of Federal Regulations, 2014 CFR

2014-07-01

... 41 Public Contracts and Property Management 2 2014-07-01 2012-07-01 true Nuclear Regulatory...-Special Types of Hazardous Materials and Certain Categories of Property § 101-42.1102-4 Nuclear Regulatory Commission-controlled materials. (a) General. The Nuclear Regulatory Commission (NRC) has exclusive control...

41 CFR 101-42.1102-4 - Nuclear Regulatory Commission-controlled materials.

Code of Federal Regulations, 2011 CFR

2011-07-01

... 41 Public Contracts and Property Management 2 2011-07-01 2007-07-01 true Nuclear Regulatory...-Special Types of Hazardous Materials and Certain Categories of Property § 101-42.1102-4 Nuclear Regulatory Commission-controlled materials. (a) General. The Nuclear Regulatory Commission (NRC) has exclusive control...

10 CFR 11.16 - Cancellation of request for special nuclear material access authorization.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 1 2013-01-01 2013-01-01 false Cancellation of request for special nuclear material access authorization. 11.16 Section 11.16 Energy NUCLEAR REGULATORY COMMISSION CRITERIA AND PROCEDURES FOR DETERMINING ELIGIBILITY FOR ACCESS TO OR CONTROL OVER SPECIAL NUCLEAR MATERIAL Requirements for...

10 CFR 76.117 - Special nuclear material of low strategic significance-Category III.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Special nuclear material of low strategic significance-Category III. 76.117 Section 76.117 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.117 Special nuclear material of low strategic...

10 CFR 50.101 - Retaking possession of special nuclear material.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 1 2013-01-01 2013-01-01 false Retaking possession of special nuclear material. 50.101 Section 50.101 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION... Operations by the Commission § 50.101 Retaking possession of special nuclear material. Upon revocation of a...

41 CFR 101-42.1102-4 - Nuclear Regulatory Commission-controlled materials.

Code of Federal Regulations, 2012 CFR

2012-07-01

... 41 Public Contracts and Property Management 2 2012-07-01 2012-07-01 false Nuclear Regulatory...-Special Types of Hazardous Materials and Certain Categories of Property § 101-42.1102-4 Nuclear Regulatory Commission-controlled materials. (a) General. The Nuclear Regulatory Commission (NRC) has exclusive control...

10 CFR 50.101 - Retaking possession of special nuclear material.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 1 2011-01-01 2011-01-01 false Retaking possession of special nuclear material. 50.101 Section 50.101 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION... Operations by the Commission § 50.101 Retaking possession of special nuclear material. Upon revocation of a...

10 CFR 150.17 - Submission to Commission of nuclear material status reports.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Submission to Commission of nuclear material status reports. 150.17 Section 150.17 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Authority in Agreement States § 150.17 Submission to Commission of nuclear material status reports. (a...

10 CFR 50.101 - Retaking possession of special nuclear material.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 1 2014-01-01 2014-01-01 false Retaking possession of special nuclear material. 50.101 Section 50.101 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION... Operations by the Commission § 50.101 Retaking possession of special nuclear material. Upon revocation of a...

41 CFR 101-42.1102-4 - Nuclear Regulatory Commission-controlled materials.

Code of Federal Regulations, 2013 CFR

2013-07-01

... 41 Public Contracts and Property Management 2 2013-07-01 2012-07-01 true Nuclear Regulatory...-Special Types of Hazardous Materials and Certain Categories of Property § 101-42.1102-4 Nuclear Regulatory Commission-controlled materials. (a) General. The Nuclear Regulatory Commission (NRC) has exclusive control...

10 CFR 150.17 - Submission to Commission of nuclear material status reports.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Submission to Commission of nuclear material status reports. 150.17 Section 150.17 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Authority in Agreement States § 150.17 Submission to Commission of nuclear material status reports. (a...

41 CFR 101-42.1102-4 - Nuclear Regulatory Commission-controlled materials.

Code of Federal Regulations, 2010 CFR

2010-07-01

... 41 Public Contracts and Property Management 2 2010-07-01 2010-07-01 true Nuclear Regulatory...-Special Types of Hazardous Materials and Certain Categories of Property § 101-42.1102-4 Nuclear Regulatory Commission-controlled materials. (a) General. The Nuclear Regulatory Commission (NRC) has exclusive control...

10 CFR 76.115 - Special nuclear material of moderate strategic significance-Category II.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Special nuclear material of moderate strategic significance-Category II. 76.115 Section 76.115 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.115 Special nuclear material of moderate...

10 CFR 11.16 - Cancellation of request for special nuclear material access authorization.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 1 2014-01-01 2014-01-01 false Cancellation of request for special nuclear material access authorization. 11.16 Section 11.16 Energy NUCLEAR REGULATORY COMMISSION CRITERIA AND PROCEDURES FOR DETERMINING ELIGIBILITY FOR ACCESS TO OR CONTROL OVER SPECIAL NUCLEAR MATERIAL Requirements for...

10 CFR 150.21 - Transportation of special nuclear material by aircraft.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Transportation of special nuclear material by aircraft. 150.21 Section 150.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Transportation of special nuclear material by aircraft. Except as specifically approved by the Commission no...

10 CFR 76.115 - Special nuclear material of moderate strategic significance-Category II.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Special nuclear material of moderate strategic significance-Category II. 76.115 Section 76.115 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.115 Special nuclear material of moderate...

10 CFR 150.17 - Submission to Commission of nuclear material status reports.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Submission to Commission of nuclear material status reports. 150.17 Section 150.17 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Authority in Agreement States § 150.17 Submission to Commission of nuclear material status reports. (a...

10 CFR 76.115 - Special nuclear material of moderate strategic significance-Category II.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Special nuclear material of moderate strategic significance-Category II. 76.115 Section 76.115 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.115 Special nuclear material of moderate...

10 CFR 50.101 - Retaking possession of special nuclear material.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Retaking possession of special nuclear material. 50.101 Section 50.101 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION... Operations by the Commission § 50.101 Retaking possession of special nuclear material. Upon revocation of a...

10 CFR 11.16 - Cancellation of request for special nuclear material access authorization.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 1 2012-01-01 2012-01-01 false Cancellation of request for special nuclear material access authorization. 11.16 Section 11.16 Energy NUCLEAR REGULATORY COMMISSION CRITERIA AND PROCEDURES FOR DETERMINING ELIGIBILITY FOR ACCESS TO OR CONTROL OVER SPECIAL NUCLEAR MATERIAL Requirements for...

10 CFR 150.21 - Transportation of special nuclear material by aircraft.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Transportation of special nuclear material by aircraft. 150.21 Section 150.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Transportation of special nuclear material by aircraft. Except as specifically approved by the Commission no...

10 CFR 76.117 - Special nuclear material of low strategic significance-Category III.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 2 2012-01-01 2012-01-01 false Special nuclear material of low strategic significance-Category III. 76.117 Section 76.117 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.117 Special nuclear material of low strategic...

10 CFR 76.115 - Special nuclear material of moderate strategic significance-Category II.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Special nuclear material of moderate strategic significance-Category II. 76.115 Section 76.115 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.115 Special nuclear material of moderate...

10 CFR 150.21 - Transportation of special nuclear material by aircraft.

Code of Federal Regulations, 2013 CFR

2013-01-01

... 10 Energy 2 2013-01-01 2013-01-01 false Transportation of special nuclear material by aircraft. 150.21 Section 150.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Transportation of special nuclear material by aircraft. Except as specifically approved by the Commission no...

10 CFR 150.21 - Transportation of special nuclear material by aircraft.

Code of Federal Regulations, 2011 CFR

2011-01-01

... 10 Energy 2 2011-01-01 2011-01-01 false Transportation of special nuclear material by aircraft. 150.21 Section 150.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Transportation of special nuclear material by aircraft. Except as specifically approved by the Commission no...

10 CFR 150.21 - Transportation of special nuclear material by aircraft.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Transportation of special nuclear material by aircraft. 150.21 Section 150.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Transportation of special nuclear material by aircraft. Except as specifically approved by the Commission no...

10 CFR 50.101 - Retaking possession of special nuclear material.

Code of Federal Regulations, 2012 CFR

2012-01-01

... 10 Energy 1 2012-01-01 2012-01-01 false Retaking possession of special nuclear material. 50.101 Section 50.101 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION... Operations by the Commission § 50.101 Retaking possession of special nuclear material. Upon revocation of a...

10 CFR 76.117 - Special nuclear material of low strategic significance-Category III.

Code of Federal Regulations, 2010 CFR

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Special nuclear material of low strategic significance-Category III. 76.117 Section 76.117 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) CERTIFICATION OF GASEOUS DIFFUSION PLANTS Safeguards and Security § 76.117 Special nuclear material of low strategic...

10 CFR 150.17 - Submission to Commission of nuclear material status reports.

Code of Federal Regulations, 2014 CFR

2014-01-01

... 10 Energy 2 2014-01-01 2014-01-01 false Submission to Commission of nuclear material status reports. 150.17 Section 150.17 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXEMPTIONS AND CONTINUED... Authority in Agreement States § 150.17 Submission to Commission of nuclear material status reports. (a...

10 CFR 74.31 - Nuclear material control and accounting for special nuclear material of low strategic significance.

Code of Federal Regulations, 2010 CFR

2010-01-01

... and maintain a measurement system which assures that all quantities in the material accounting records...) In each inventory period, control total material control and accounting measurement uncertainty so... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for special...

Peculiarities of organizing the construction of nuclear medicine facilities and the transportation of radionuclide

NASA Astrophysics Data System (ADS)

Telichenko, Valeriy; Malykha, Galina; Dorogan, Igor

2017-10-01

The article is devoted to the organization of construction of nuclear medicine facilities in Russia. The article describes the main methods of nuclear medical diagnostics, as well as the peculiarities of nuclear medicine facilities that determine the need for application of specific methods for organizing and managing the construction, methods of requirements management in the organization of construction of nuclear medicine facilities. Sustainable development of the transport of radioactive isotopes from the place of production to places of consumption is very important for the safety of the population. The requirements management system is an important and necessary component in organizing the construction of complex facilities, such as nuclear medicine facilities. The author developed and proposed a requirements management system for the design, construction and operation of a nuclear medicine facility, which provides for a cyclic sequence of actions. This system allows reducing the consumption of resources including material and energy during construction and operation of complex objects.

Radiological Characterization Technical Report on Californium-252 Sealed Source Transuranic Debris Waste for the Off-Site Source Recovery Project at Los Alamos National Laboratory

DOE Office of Scientific and Technical Information (OSTI.GOV)

Feldman, Alexander

2014-04-24

This document describes the development and approach for the radiological characterization of Cf-252 sealed sources for shipment to the Waste Isolation Pilot Plant. The report combines information on the nuclear material content of each individual source (mass or activity and date of manufacture) with information and data on the radionuclide distributions within the originating nuclear material. This approach allows for complete and accurate characterization of the waste container without the need to take additional measurements. The radionuclide uncertainties, developed from acceptable knowledge (AK) information regarding the source material, are applied to the summed activities in the drum. The AK informationmore » used in the characterization of Cf-252 sealed sources has been qualified by the peer review process, which has been reviewed and accepted by the Environmental Protection Agency.« less

An Investigation for Ground State Features of Some Structural Fusion Materials

NASA Astrophysics Data System (ADS)

Aytekin, H.; Tel, E.; Baldik, R.; Aydin, A.

2011-02-01

Environmental concerns associated with fossil fuels are creating increased interest in alternative non-fossil energy sources. Nuclear fusion can be one of the most attractive sources of energy from the viewpoint of safety and minimal environmental impact. When considered in all energy systems, the requirements for performance of structural materials in a fusion reactor first wall, blanket or diverter, are arguably more demanding or difficult than for other energy system. The development of fusion materials for the safety of fusion power systems and understanding nuclear properties is important. In this paper, ground state properties for some structural fusion materials as 27Al, 51V, 52Cr, 55Mn, and 56Fe are investigated using Skyrme-Hartree-Fock method. The obtained results have been discussed and compared with the available experimental data.

Asymptotic Expansion Homogenization for Multiscale Nuclear Fuel Analysis

DOE Office of Scientific and Technical Information (OSTI.GOV)

Hales, J. D.; Tonks, M. R.; Chockalingam, K.

2015-03-01

Engineering scale nuclear fuel performance simulations can benefit by utilizing high-fidelity models running at a lower length scale. Lower length-scale models provide a detailed view of the material behavior that is used to determine the average material response at the macroscale. These lower length-scale calculations may provide insight into material behavior where experimental data is sparse or nonexistent. This multiscale approach is especially useful in the nuclear field, since irradiation experiments are difficult and expensive to conduct. The lower length-scale models complement the experiments by influencing the types of experiments required and by reducing the total number of experiments needed.more » This multiscale modeling approach is a central motivation in the development of the BISON-MARMOT fuel performance codes at Idaho National Laboratory. These codes seek to provide more accurate and predictive solutions for nuclear fuel behavior. One critical aspect of multiscale modeling is the ability to extract the relevant information from the lower length-scale sim- ulations. One approach, the asymptotic expansion homogenization (AEH) technique, has proven to be an effective method for determining homogenized material parameters. The AEH technique prescribes a system of equations to solve at the microscale that are used to compute homogenized material constants for use at the engineering scale. In this work, we employ AEH to explore the effect of evolving microstructural thermal conductivity and elastic constants on nuclear fuel performance. We show that the AEH approach fits cleanly into the BISON and MARMOT codes and provides a natural, multidimensional homogenization capability.« less

Recapturing Graphite-Based Fuel Element Technology for Nuclear Thermal Propulsion

DOE Office of Scientific and Technical Information (OSTI.GOV)

Trammell, Michael P; Jolly, Brian C; Miller, James Henry

ORNL is currently recapturing graphite based fuel forms for Nuclear Thermal Propulsion (NTP). This effort involves research and development on materials selection, extrusion, and coating processes to produce fuel elements representative of historical ROVER and NERVA fuel. Initially, lab scale specimens were fabricated using surrogate oxides to develop processing parameters that could be applied to full length NTP fuel elements. Progress toward understanding the effect of these processing parameters on surrogate fuel microstructure is presented.

High reliability - low noise radionuclide signature identification algorithms for border security applications

NASA Astrophysics Data System (ADS)

Lee, Sangkyu

Illicit trafficking and smuggling of radioactive materials and special nuclear materials (SNM) are considered as one of the most important recent global nuclear threats. Monitoring the transport and safety of radioisotopes and SNM are challenging due to their weak signals and easy shielding. Great efforts worldwide are focused at developing and improving the detection technologies and algorithms, for accurate and reliable detection of radioisotopes of interest in thus better securing the borders against nuclear threats. In general, radiation portal monitors enable detection of gamma and neutron emitting radioisotopes. Passive or active interrogation techniques, present and/or under the development, are all aimed at increasing accuracy, reliability, and in shortening the time of interrogation as well as the cost of the equipment. Equally important efforts are aimed at advancing algorithms to process the imaging data in an efficient manner providing reliable "readings" of the interiors of the examined volumes of various sizes, ranging from cargos to suitcases. The main objective of this thesis is to develop two synergistic algorithms with the goal to provide highly reliable - low noise identification of radioisotope signatures. These algorithms combine analysis of passive radioactive detection technique with active interrogation imaging techniques such as gamma radiography or muon tomography. One algorithm consists of gamma spectroscopy and cosmic muon tomography, and the other algorithm is based on gamma spectroscopy and gamma radiography. The purpose of fusing two detection methodologies per algorithm is to find both heavy-Z radioisotopes and shielding materials, since radionuclides can be identified with gamma spectroscopy, and shielding materials can be detected using muon tomography or gamma radiography. These combined algorithms are created and analyzed based on numerically generated images of various cargo sizes and materials. In summary, the three detection methodologies are fused into two algorithms with mathematical functions providing: reliable identification of radioisotopes in gamma spectroscopy; noise reduction and precision enhancement in muon tomography; and the atomic number and density estimation in gamma radiography. It is expected that these new algorithms maybe implemented at portal scanning systems with the goal to enhance the accuracy and reliability in detecting nuclear materials inside the cargo containers.

Addressing the psychosocial and communication challenges posed by radiological/nuclear terrorism: key developments since NCRP Report No. 138.

PubMed

Becker, Steven M

2005-11-01

One of the most innovative aspects of NCRP Report No. 138 (Management of Terrorist Incidents Involving Radioactive Material) was the high priority it accorded to psychosocial and communication issues. While previous discussions of radiological and nuclear terrorism had occasionally referred to these topics, NCRP Report No. 138 was the first report of its kind to recognize the profound challenges posed by these issues and to place them at the heart of preparedness and response efforts. In the years since the report's release, a host of important developments have taken place in relation to psychosocial and communication issues. This paper reviews key changes and advances in five broad areas: (1) training exercises, (2) policy and guidance development, (3) findings on hospital and clinician needs, (4) survey research on public perceptions of radiological terrorism, and (5) risk communication for radiological and nuclear terrorism situations. The article concludes with a discussion of continuing psychosocial and communication challenges, including critical areas needing further attention as the nation moves to meet the threat of terrorism involving radioactive materials.

Cladding and duct materials for advanced nuclear recycle reactors

NASA Astrophysics Data System (ADS)

Allen, T. R.; Busby, J. T.; Klueh, R. L.; Maloy, S. A.; Toloczko, M. B.

2008-01-01

The expanded use of nuclear energy without risk of nuclear weapons proliferation and with safe nuclear waste disposal is a primary goal of the Global Nuclear Energy Partnership (GNEP). To achieve that goal the GNEP is exploring advanced technologies for recycling spent nuclear fuel that do not separate pure plutonium, and advanced reactors that consume transuranic elements from recycled spent fuel. The GNEP’s objectives will place high demands on reactor clad and structural materials. This article discusses the materials requirements of the GNEP’s advanced nuclear recycle reactors program.

One perspective on stakeholder involvement at Hanford.

PubMed

Martin, Todd

2011-11-01

The Hanford nuclear site in Washington State had a major role in the production of nuclear weapons materials during the Manhattan Project in World War II and during the Cold War that followed. The production of weapons-grade radionuclides produced a large amount of radioactive byproducts that have been stored since the mid-1900s at the Hanford Site. These by-product radionuclides have leaked from containment facilities into the groundwater, contaminated buildings used for radionuclide processing, and also contaminated the nuclear reactors used to produce weapons-grade uranium and plutonium. This issue has been a major concern to Hanford stakeholders for several decades, and the U.S. Department of Energy, the U.S. Environmental Protection Agency, and the Washington State Department of Ecology established a Tri-Party Agreement in 1989, at which time Hanford ceased production of nuclear weapons materials and began a major effort to clean up and remediate the Hanford Site's contaminated groundwater, soil, and facilities. This paper describes the concerns of stakeholders in the production of nuclear weapons, the secrecy of Hanford operations, and the potential impacts to public health and the environment from the unintended releases of weapons-grade materials and by-products associated with their production at the Hanford Site. It also describes the involvement of public stakeholders in the development and oversight by the Hanford Advisory Board of the steps that have been taken in cleanup activities at the Hanford Site that began as a major effort about two decades ago. The importance of involvement of the general public and public interest organizations in developing and implementing the Hanford cleanup strategy are described in detail.

Developing a structural health monitoring system for nuclear dry cask storage canister

NASA Astrophysics Data System (ADS)

Sun, Xiaoyi; Lin, Bin; Bao, Jingjing; Giurgiutiu, Victor; Knight, Travis; Lam, Poh-Sang; Yu, Lingyu

2015-03-01

Interim storage of spent nuclear fuel from reactor sites has gained additional importance and urgency for resolving waste-management-related technical issues. In total, there are over 1482 dry cask storage system (DCSS) in use at US plants, storing 57,807 fuel assemblies. Nondestructive material condition monitoring is in urgent need and must be integrated into the fuel cycle to quantify the "state of health", and more importantly, to guarantee the safe operation of radioactive waste storage systems (RWSS) during their extended usage period. A state-of-the-art nuclear structural health monitoring (N-SHM) system based on in-situ sensing technologies that monitor material degradation and aging for nuclear spent fuel DCSS and similar structures is being developed. The N-SHM technology uses permanently installed low-profile piezoelectric wafer sensors to perform long-term health monitoring by strategically using a combined impedance (EMIS), acoustic emission (AE), and guided ultrasonic wave (GUW) approach, called "multimode sensing", which is conducted by the same network of installed sensors activated in a variety of ways. The system will detect AE events resulting from crack (case for study in this project) and evaluate the damage evolution; when significant AE is detected, the sensor network will switch to the GUW mode to perform damage localization, and quantification as well as probe "hot spots" that are prone to damage for material degradation evaluation using EMIS approach. The N-SHM is expected to eventually provide a systematic methodology for assessing and monitoring nuclear waste storage systems without incurring human radiation exposure.

DOE Office of Scientific and Technical Information (OSTI.GOV)

Braase, Lori

Develop advanced nuclear fuel cycle separation and waste management technologies that improve current fuel cycle performance and enable a sustainable fuel cycle, with minimal processing, waste generation, and potential for material diversion.