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Book Nuclide Importance to Criticality Safety  Decay Heating  and Source Terms Related to Transport and Interim Storage of High Burnup LWR Fuel

Download or read book Nuclide Importance to Criticality Safety Decay Heating and Source Terms Related to Transport and Interim Storage of High Burnup LWR Fuel written by and published by . This book was released on 2000 with total page 104 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report investigates trends in the radiological decay properties and changes in relative nuclide importance associated with increasing enrichments and burnup for spent LWR fuel as they affect the areas of criticality safety, thermal analysis (decay heat), and shielding analysis of spent fuel transport and storage casks. To facilitate identifying the changes in the spent fuel compositions that most directly impact these application areas, the dominant nuclides in each area have been identified and ranked by importance. The importance is investigated as a function of increasing burnup to assist in identifying the key changes in spent fuel characteristics between conventional- and extended-burnup regimes. Studies involving both pressurized water-reactor (PWR) fuel assemblies and boiling-water-reactor (BWR) assemblies are included. This study is seen to be a necessary first step in identifying the high-burnup spent fuel characteristics that may adversely affect the accuracy of current computational methods and data, assess the potential impact on previous guidance on isotopic source terms and decay-heat values, and thus help identify areas for methods and data improvement. Finally, several recommendations on the direction of possible future code validation efforts for high-burnup spent fuel predictions are presented.

Book NUCLIDE IMPORTANCE TO CRITICALITY SAFETY  DECAY HEATING  AND SOURCE TERMS RELATED TO TRANSPORT AND INTERIM STORAGE OF     NUREG

Download or read book NUCLIDE IMPORTANCE TO CRITICALITY SAFETY DECAY HEATING AND SOURCE TERMS RELATED TO TRANSPORT AND INTERIM STORAGE OF NUREG written by U.S. Nuclear Regulatory Commission and published by . This book was released on 2001* with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Criticality Safety

Download or read book Nuclear Criticality Safety written by Ronald Allen Knief and published by American Nuclear Society. This book was released on 1985 with total page 256 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear criticality safety is the prevention of nuclear chain reactions in fissile materials outside of reactors. This book presents the underlying principles of nuclear criticality safety theory along with descriptions of the principal methods currently used and their in-plant applications. Exercises are provided at the end of each chapter to increase understanding of the text.

Book Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long Term Storage of LWR Spent Fuel

Download or read book Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long Term Storage of LWR Spent Fuel written by and published by . This book was released on 1995 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The radionuclide characteristics of light-water-reactor (LWR) spent fuel play key roles in the design and licensing activities for radioactive waste transportation systems, interim storage facilities, and the final repository site. Several areas of analysis require detailed information concerning the time-dependent behavior of radioactive nuclides including (1) neutron/gamma-ray sources for shielding studies, (2) fissile/absorber concentrations for criticality safety determinations, (3) residual decay heat predictions for thermal considerations, and (4) curie and/or radiological toxicity levels for materials assumed to be released into the ground/environment after long periods of time. The crucial nature of the radionuclide predictions over both short and long periods of time has resulted in an increased emphasis on thorough validation for radionuclide generation/depletion codes. Current radionuclide generation/depletion codes have the capability to follow the evolution of some 1600 isotopes during both irradiation and decay time periods. Of these, typically only 10 to 20 nuclides dominate contributions to each analysis area. Thus a quantitative ranking of nuclides over various time periods is desired for each of the analysis areas of shielding, criticality, heat transfer, and environmental dose (radiological toxicity). These rankings should allow for validation and data improvement efforts to be focused only on the most important nuclides. This study investigates the relative importances of the various actinide, fission-product, and light-element isotopes associated with LWR spent fuel with respect to five analysis areas: criticality safety (absorption fractions), shielding (dose rate fractions), curies (fractional curies levels), decay heat (fraction of total watts), and radiological toxicity (fraction of potential committed effective dose equivalent). These rankings are presented for up to six different burnup/enrichment scenarios and at decay times from 2 to 100,000 years. Ranking plots for each of these analysis areas are given in an Appendix for completeness, as well as summary tables in the main body of the report. Summary rankings are presented in terms of high (greater than 10% contribution to the total), medium (between 1% and 10% contribution), and low (less than 1% contribution) for both short- and long-term cooling. When compared with the expected measurement accuracies, these rankings show that most of the important isotopes can be characterized sufficiently for the purpose of radionuclide generation/depletion code validation in each of the analysis areas. Because the main focus of this work is on the relative importances of isotopes associated with LWR spent fuel, some conclusions may not be applicable to similar areas such as high-level waste (HLW) and nonfuel-bearing components (NFBC).

Book Criticality Safety in the Handling of Fissile Material

Download or read book Criticality Safety in the Handling of Fissile Material written by IAEA and published by International Atomic Energy Agency. This book was released on 2022-09-09 with total page 104 pages. Available in PDF, EPUB and Kindle. Book excerpt: The objectives of nuclear criticality safety are to prevent a self-sustained nuclear chain reaction. This Safety Guide provides guidance and recommendations on how to meet the relevant requirements for ensuring subcriticality when dealing with fissile material and for planning the response to criticality accidents. The recommendations address how to ensure subcriticality in systems involving fissile materials during normal operation and during credible abnormal conditions, from initial design through commissioning, operation and decommissioning. This publication also provides recommendations on identification of credible abnormal conditions; performance of criticality safety assessments; verification, benchmarking and validation of calculation methods; safety measures to ensure subcriticality; and management of criticality safety. The guidance and recommendations are applicable to both regulatory bodies and operating organizations.

Book Nuclear Criticality Safety

Download or read book Nuclear Criticality Safety written by and published by . This book was released on 1989 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Physical Theory of Neutron Chain Reactors

Download or read book The Physical Theory of Neutron Chain Reactors written by Alvin Martin Weinberg and published by . This book was released on 1958 with total page 862 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The proposals for national policy statements on energy

Download or read book The proposals for national policy statements on energy written by Great Britain: Parliament: House of Commons: Energy and Climate Change Committee and published by The Stationery Office. This book was released on 2010-03-23 with total page 604 pages. Available in PDF, EPUB and Kindle. Book excerpt: proposals for national policy statements on Energy : Third report of session 2009-10, Vol. 2: Oral and written Evidence

Book Investigations and Recommendations on the Use of Existing Experiments in Criticality Safety Analysis of Nuclear Fuel Cycle Facilities for Weapons Grade Plutonium

Download or read book Investigations and Recommendations on the Use of Existing Experiments in Criticality Safety Analysis of Nuclear Fuel Cycle Facilities for Weapons Grade Plutonium written by and published by . This book was released on 2002 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Sensitivity and Uncertainty (S/U) methods, recently developed at Oak Ridge National Laboratory (ORNL) have been demonstrated to determine the applicability of critical benchmark experiments to the criticality code validation of design systems. These methods, although still under development, have been recently published in several sources. Development of the techniques used in this report was conducted through joint support from the United States Department of Energy (U.S. DOE) and the Nuclear Regulatory Commission (NRC) to provide a physics-based approach for the establishment of the area of applicability of critical experiments per the requirements of ANSI/ANS-8.1. Use of these methods may allow users to interpolate and extrapolate the traditional area of applicability (AOA) of a given set of critical experiments to include new application areas that may not have been anticipated during the experiment design. The new S/U analytical tools include the SEN1 and SEN3 sensitivity analysis sequences, which will be available with the next release of the Standardized Computer Analyses for Licensing Evaluation (SCALE) code system. These analysis sequences compute the relative change in the system neutron multiplication factor, k{sub eff}, which would be observed for perturbations in the group-wise neutron cross-section data for each reaction of each nuclide in the system. The CANDE code uses sensitivity data determined separately for the design system applications and the individual experiments, along with the cross-section-covariance data, to calculate integral parameters which give a measure of the similarity between a particular design system and an experimental benchmark. A high-valued integral parameter for an experiment application pair indicates that the experiment demonstrates similar properties to the application. Thus, the experiment is applicable for the criticality code validation of the design system. A theoretical basis for the S/U techniques applied in this report is given in Sect. 2. This report pertains to two of the five AOAs identified by the licensee [Duke, Cogema, Stone and Webster (DCS)] for the validation of criticality codes in the design of the Mixed-Oxide Fuel Fabrication Facility (MFFF). The five AOAs are as follows: (1) Pu-nitrate aqueous solutions (homogeneous systems), (2) Mixed-oxide (MOX) pellets, fuel rods and fuel assemblies (heterogeneous systems), (3) PuO2 powders, (4) MOX powders, and (5) Aqueous solutions of Pu compounds (Pu-oxalate solutions). This report addresses a S/U analysis pertaining to AOA 3, PuO2 powders, and AOA 4, MOX powders. AOA 3 and AOA 4 are the subject of this report since the other AOAs (solutions and heterogeneous systems) appear to be well represented in the documented benchmark experiments used in the criticality safety community. Prior to this work, DCS used traditional criticality validation techniques to identify numerous experimental benchmarks that are applicable to AOAs 3 and 4. Traditional techniques for selection of applicable benchmark experiments essentially consist of evaluating the area of applicability for important design parameters (e.g., Pu content or average neutron energy) and ensuring experiments have similar characteristics that bound or nearly bound the range of conditions requiring design analysis. DCS provided ORNL with compositions and dimensions for critical systems used to establish preliminary mass limits for facility powder and fuel pellet handling areas corresponding to AOAs 3 and 4. ORNL has reviewed existing critical experiments to identify those, which, in addition to those provided by DCS, may be applicable to the criticality code validation for AOAs 3 and 4. A S/U analysis was then performed to calculate the integral parameters used to determine the similarity of each critical experiment to each design system provided by DCS. This report contains a review of the S/U theory, a description of the design systems, a brief description of the critical experiments evaluated for applicability, and the results of the S/U analysis determining the applicability of each experiment to each application.

Book Nuclear Criticality Safety Handbook  Version 2

Download or read book Nuclear Criticality Safety Handbook Version 2 written by Nihon Genshiryoku Kenkyūjo. Working Group on Nuclear Criticality Safety Data and published by . This book was released on 2001 with total page 217 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Criticality Safety

Download or read book Nuclear Criticality Safety written by Berry F. Estes and published by . This book was released on 1980 with total page 448 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material

Download or read book Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material written by IAEA and published by International Atomic Energy Agency. This book was released on 2022-06-13 with total page 364 pages. Available in PDF, EPUB and Kindle. Book excerpt: This Safety Guide provides recommendations and guidance on achieving and demonstrating compliance with IAEA Safety Standards Series No. SSR-6 (Rev. 1), Regulations for the Safe Transport of Radioactive Material (2018 Edition), which establishes the requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material, including the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit, shipment after storage and receipt at the final destination of packages. The Advisory Material is not a stand-alone text. It is to be used concurrently as a companion to the IAEA Safety Standards Series No. SSR-6 (Rev. 1) and each paragraph of this guide is numbered correspondingly to the paragraph of the Regulations to which it most directly relates.

Book Nuclear Waste Management

Download or read book Nuclear Waste Management written by Man-Sung Yim and published by Springer Nature. This book was released on 2021-12-09 with total page 850 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book lays a comprehensive foundation for addressing the issue of safety in the lifecycle of nuclear waste. With the focus on the fundamental principles, the book covers key technical approaches to safety in the management of spent nuclear fuel, reprocessed high-level waste, low-level waste, and decommissioning wastes. Behaviors of nuclear waste in natural and engineered systems in relation to safety assessment are also described through the explanation of fundamental processes. For any country involved with the use of nuclear power, nuclear waste management is a topic of grave importance. Although many countries have heavily invested in nuclear waste management, having a successful national program still remains a major challenge. This book offers substantial guidance for those seeking solutions to these problems. As the problem of nuclear waste management is heavily influenced by social factors, the connection between technical and social issues in nuclear waste management is also discussed. The book is a core text for advanced students in nuclear and environmental engineering, and a valuable reference for those working in nuclear engineering and related areas.

Book Journal of Nuclear Science and Technology

Download or read book Journal of Nuclear Science and Technology written by and published by . This book was released on 2008 with total page 364 pages. Available in PDF, EPUB and Kindle. Book excerpt: Includes English language abstracts from Japanese articles in Nihon Genshiryoku Gakkai Shi (Journal of the Atomic Energy Society of Japan)

Book Strategy and Methodology for Radioactive Waste Characterization

Download or read book Strategy and Methodology for Radioactive Waste Characterization written by International Atomic Energy Agency and published by IAEA. This book was released on 2007 with total page 188 pages. Available in PDF, EPUB and Kindle. Book excerpt: Over the past decade significant progress has been achieved in the development of waste characterization and control procedures and equipment as a direct response to ever-increasing requirements for quality and reliability of information on waste characteristics. Failure in control procedures at any step can have important, adverse consequences and may result in producing waste packages which are not compliant with the waste acceptance criteria for disposal, thereby adversely impacting the repository. The information and guidance included in this publication corresponds to recent achievements and reflects the optimum approaches, thereby reducing the potential for error and enhancing the quality of the end product. -- Publisher's description.

Book IAEA Safety Glossary

Download or read book IAEA Safety Glossary written by International Atomic Energy Agency and published by International Atomic Energy Agency. This book was released on 2019-09-17 with total page 261 pages. Available in PDF, EPUB and Kindle. Book excerpt: The IAEA Safety Glossary defines and explains technical terms used in the IAEA Safety Standards and other safety related IAEA publications, and provides information on their usage. The 2018 Edition of the IAEA Safety Glossary is a new edition of the IAEA Safety Glossary, originally issued in 2007. It has been revised and updated to take into account new terminology and usage in safety standards issued between 2007 and 2018. The revisions and updates reflect developments in the technical areas of application of the safety standards and changes in regulatory approaches in Member States.