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Languages : en
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This third report in the series reviews possible safeguards approaches for new fast reactors in general, and the ABR in particular. Fast-neutron spectrum reactors have been used since the early 1960s on an experimental and developmental level, generally with fertile blanket fuels to?breed? nuclear fuel such as plutonium. Whether the reactor is designed to breed plutonium, or transmute and?burn? actinides depends mainly on the design of the reactor neutron reflector and the whether the blanket fuel is?fertile? or suitable for transmutation. However, the safeguards issues are very similar, since they pertain mainly to the receipt, shipment and storage of fresh and spent plutonium and actinide-bearing?TRU?-fuel. For these reasons, the design of existing fast reactors and details concerning how they have been safeguarded were studied in developing advanced safeguards approaches for the new fast reactors. In this regard, the design of the Experimental Breeder Reactor-II?EBR-II? at the Idaho National Laboratory (INL) was of interest, because it was designed as a collocated fast reactor with a pyrometallurgical reprocessing and fuel fabrication line - a design option being considered for the ABR. Similarly, the design of the Fast Flux Facility (FFTF) on the Hanford Site was studied, because it was a successful prototype fast reactor that ran for two decades to evaluate fuels and the design for commercial-scale fast reactors.
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Category :
Languages : en
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Book Description
This third report in the series reviews possible safeguards approaches for new fast reactors in general, and the ABR in particular. Fast-neutron spectrum reactors have been used since the early 1960s on an experimental and developmental level, generally with fertile blanket fuels to?breed? nuclear fuel such as plutonium. Whether the reactor is designed to breed plutonium, or transmute and?burn? actinides depends mainly on the design of the reactor neutron reflector and the whether the blanket fuel is?fertile? or suitable for transmutation. However, the safeguards issues are very similar, since they pertain mainly to the receipt, shipment and storage of fresh and spent plutonium and actinide-bearing?TRU?-fuel. For these reasons, the design of existing fast reactors and details concerning how they have been safeguarded were studied in developing advanced safeguards approaches for the new fast reactors. In this regard, the design of the Experimental Breeder Reactor-II?EBR-II? at the Idaho National Laboratory (INL) was of interest, because it was designed as a collocated fast reactor with a pyrometallurgical reprocessing and fuel fabrication line - a design option being considered for the ABR. Similarly, the design of the Fast Flux Facility (FFTF) on the Hanford Site was studied, because it was a successful prototype fast reactor that ran for two decades to evaluate fuels and the design for commercial-scale fast reactors.
Author: Bahman Zohuri
Publisher: Springer
ISBN: 303023682X
Category : Technology & Engineering
Languages : en
Pages : 220
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Book Description
This book discusses advanced Small Modular Reactors (SMRs) as a way to provide safe, clean, and affordable nuclear power options. The advanced SMRs currently under development in the U.S. represent a variety of sizes, technology options and deployment scenarios. These advanced reactors, envisioned to vary in size from a couple megawatts up to hundreds of megawatts can be used for power generation, process heat, desalination, or other industrial uses. In-depth chapters describe how advanced SMRs offer multiple advantages, such as relatively small size, reduced capital investment, location flexibility, and provisions for incremental power additions. SMRs also offer distinct safeguards, security and nonproliferation advantages. The authors present a thorough examination of the technology and defend methods by which the new generation of nuclear power plants known as GEN-IV can safely be used as an efficient source of renewable energy. Provides a unique and innovative approach to the implementation of Small Modular Reactor as part of GEN-IV technology; Discusses how Small Modular Reactors (SMRs) can deliver a viable alternative to Nuclear Power Plants (NPPs); Presents an argument defending the need for nuclear power plant as a source of energy, its efficiency and cost effectiveness, as well as safety related issues.
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Languages : en
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Book Description
The proliferation resistance and physical protection (PR and PP) working group produced a case study on the Example Sodium Fast Reactor (ESFR). The ESFR is a hypothetical nuclear energy system consisting of four sodium-cooled fast reactors of medium size collocated with an on-site dry fuel storage facility and a spent fuel reprocessing facility using pyroprocessing technology. This study revealed how safeguards would be applied at such site consisting of integrated multiple fuel cycle facilities and the implications of what safeguards technology and safeguards concepts would need to be adapted and developed to safeguard successfully this Generation IV nuclear energy system concept. The major safeguards concepts driving our safeguards analysis are timeliness goals and material quantity goals. Because the fresh transuranic (TRU) fuel to be produced in the ESFR fuel fabrication facility contains plutonium, the ESFR will be reprocessing, using in the reactor, and storing material on site that will have IAEA defined 'direct-use material' in it with stringent timeliness goals and material quantity goals that drive the safeguards implementation. Specifically, the TRU fresh fuel, pyroprocessing in process material, LWR spent fuel sent to the ESFR, and TRU spent fuel will contain plutonium. This material will need to be verified at interim intervals four times per year because the irradiated direct-use material, as defined previously, has three-month timeliness goals and 8 kg material quantity goals for plutonium. The TRU in-process material is, of course, irradiated direct-use material as defined by the IAEA. Keeping the plutonium and uranium together with TRu products should provide a radiation barrier. this radiation barrier slows down the ability to reprocess the fuel. Furthermore, the reprocessing technique, if it has some intrinsic proliferation resistance, will need major modifications to be able to separate plutonium from the uranium and TRU mixture. The ESFR design should have such features in it if it is seen to have intrinsic proliferation resistance. The technical difficulty in diverting material from the ESFR is at least as strongly impacted by the adversaries overall technical capabilities as it is by the effort required to overcome those barriers intrinsic to the nuclear fuel cycle. The intrinsic proliferation resistance of the ESFR will affect how extrinsic measures in the safeguards approach for the ESFR will provide overall proliferation resistance.
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201065148
Category : Science
Languages : en
Pages : 0
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Book Description
This publication is the second in the IAEA Nuclear Energy Series to provide guidance on the inclusion of safeguards in nuclear facility design and construction. It is principally intended for designers and operators of nuclear reactor facilities; however, vendors, national authorities and financial backers can also benefit from the information provided. It is introductory rather than comprehensive in nature, complementing the Guidance for States Implementing Comprehensive Safeguards Agreements and Additional Protocols, IAEA Services Series No. 21, and other publications in that series. The publication complements the general considerations addressed in International Safeguards in Nuclear Facility Design and Construction, IAEA Nuclear Energy Series No. NP-T-2.8.
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201189103
Category : Environmental sampling
Languages : en
Pages : 146
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Book Description
The 1990s saw significant developments in the global non-proliferation landscape, resulting in a new period of safeguards development. The current publication, which is the second revision and update of IAEA/NVS/1, is intended to give a full and balanced description of the safeguards techniques and equipment used for nuclear material accountancy, containment and surveillance measures, environmental sampling, and data security. New features include a section on new and novel technologies. As new verification measures continue to be developed, the material in this book will be reviewed periodically and updated versions issued.
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Languages : en
Pages :
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Advanced fuel-cycle developments around the world currently under development are exploring the possibility of disposing of 241Am from spent fuel recycle processes by burning this material in fast reactors. For safeguards practitioners, this approach could potentially complicate both fresh- and spent-fuel safeguards measurements. The increased ([alpha], n) production in oxide fuels from the 241Am increases the uncertainty in coincidence assay of Pu in MOX assemblies and will require additional information to make use of totals-based neutron assay of these assemblies. We have studied the behavior of 241Am-bearing MOX fuel in the fast reactor system and the effect on neutron and gamma-ray source-terms for safeguards measurements. In this paper, we will present the results of simulations of the behavior of 241Am in a fast breeder reactor system. Because of the increased use of MOX fuel in thermal reactors and advances in fuel-cycle designs aimed at americium disposal in fast reactors, we have undertaken a brief study of the behavior of americium in these systems to better understand the safeguards impacts of these new approaches. In this paper we will examine the behavior of 241Am in a variety of nuclear systems to provide insight into the safeguards implications of proposed Am disposition schemes.
Author: Charles R. Russell
Publisher: Elsevier
ISBN: 1483138860
Category : Science
Languages : en
Pages : 405
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Book Description
Reactor Safeguards focuses on the measures and approaches in the safeguard of reactors. The book first discusses the development of nuclear reactors, including the emergence of radiation hazards, construction of nuclear reactors in Chicago, and containment of reactors. The text also focuses on radioactive materials; reactor kinetics; and control and safety systems of reactors. The text discusses the containment of nuclear reactors. Topics include nuclear excursions; combustion of reactor materials; melting of reactor fuels; design of containment structures; and size of breaks or leaks in cooling systems. The text also describes the dispersion of radioactive materials, including problems in operations, diffusion theory, and nomograms for graphical solutions. The book also highlights the possible damages that a nuclear reactor accident can produce. Considerations include the permissible dose of radiation, exposure to nuclear radiations, and evacuation from a contaminated area. The text is a valuable source of data for readers, engineers, and physicists who are responsible in hazard analysis and site selection.
Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 110
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Book Description
This report presents guidelines to the designers of water cooled power reactors which will minimize the impact of IAEA safeguards on plant operations and ensure efficient and effective acquisition of safeguards data to the mutual benefit of the Member State, the plant operator and the IAEA. These guidelines incorporate the IAEA's experience in establishing and carrying out safeguards at currently operating nuclear power plants, the ongoing development of safeguards techniques and the feedback of experience from plant operators and designers on the impact of IAEA safeguards on plant operation.
Author: National Research Council
Publisher: National Academies Press
ISBN: 0309043956
Category : Science
Languages : en
Pages : 234
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Book Description
The construction of nuclear power plants in the United States is stopping, as regulators, reactor manufacturers, and operators sort out a host of technical and institutional problems. This volume summarizes the status of nuclear power, analyzes the obstacles to resumption of construction of nuclear plants, and describes and evaluates the technological alternatives for safer, more economical reactors. Topics covered include: Institutional issues-including regulatory practices at the federal and state levels, the growing trends toward greater competition in the generation of electricity, and nuclear and nonnuclear generation options. Critical evaluation of advanced reactors-covering attributes such as cost, construction time, safety, development status, and fuel cycles. Finally, three alternative federal research and development programs are presented.
Author: Victor Nian
Publisher: Academic Press
ISBN: 0128182571
Category : Technology & Engineering
Languages : en
Pages : 270
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Book Description
Advanced Security and Safeguarding in the Nuclear Power Industry: State of the art and future challenges presents an overview of a wide ranging scientific, engineering, policy, regulatory, and legal issues facing the nuclear power industry. Editor Victor Nian and his team of contributors deliver a much needed review of the latest developments in safety, security and safeguards ("Three S's) as well as other related and important subject matters within and beyond the nuclear power industry. This book is particularly insightful to countries with an interest in developing a nuclear power industry as well as countries where education to improve society's opinion on nuclear energy is crucial to its future success. Advanced Security and Safeguarding in the Nuclear Power Industry covers the foundations of nuclear power production as well as the benefits and impacts of radiation to human society, international conventions, treaties, and standards on the "Three S's, emergency preparedness and response, and civil liability in the event of a nuclear accident. - The socio-technical and economic risks of civilian and military applications of atomic energy - Putting into perspective the hazards of radioactive sources and health impacts of exposure to radiation - Prevention and protection against severe nuclear accidents with a much needed update on lessons learnt from "Fukushima - International conventions, treaties, legal frameworks, standards and best practices on "Three S's, emergency preparedness and response, and civil liability - Evolving technological and institutional challenges facing the nuclear power industry in the future
