Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors
Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors

Author: National Academies of Sciences, Engineering, and Medicine

Publisher: National Academies Press

Published: 2016-02-12

Total Pages: 205

ISBN-13: 0309379210

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The continued presence of highly enriched uranium (HEU) in civilian installations such as research reactors poses a threat to national and international security. Minimization, and ultimately elimination, of HEU in civilian research reactors worldwide has been a goal of U.S. policy and programs since 1978. Today, 74 civilian research reactors around the world, including 8 in the United States, use or are planning to use HEU fuel. Since the last National Academies of Sciences, Engineering, and Medicine report on this topic in 2009, 28 reactors have been either shut down or converted from HEU to low enriched uranium fuel. Despite this progress, the large number of remaining HEU-fueled reactors demonstrates that an HEU minimization program continues to be needed on a worldwide scale. Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors assesses the status of and progress toward eliminating the worldwide use of HEU fuel in civilian research and test reactors.

Material Properties of Unirradiated Uranium-Molybdenum (U-Mo) Fuel for Research Reactors
Material Properties of Unirradiated Uranium-Molybdenum (U-Mo) Fuel for Research Reactors

Author: International Atomic Energy Agency

Publisher:

Published: 2020-10-12

Total Pages: 144

ISBN-13: 9789201157201

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This publication presents the material properties of all unirradiated Uranium-Molybdenum (U-Mo) fuel constituents that are essential for fuel designers and reactor operators to evaluate the fuel's performance and safety for research reactors. Many significant advances in the understanding and development of low enriched uranium U-Mo fuels have been made since 2004, stimulated by the need to understand irradiation behavior and early fuel failures during testing. The publication presents a comprehensive overview of mechanical and physical property data from U-Mo fuel research

Nuclear Energy Basic Principles
Nuclear Energy Basic Principles

Author: International Atomic Energy Agency

Publisher:

Published: 2008

Total Pages: 0

ISBN-13: 9789201126085

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Describes the rationale and vision for the peaceful use of nuclear energy. The publication identifies the basic principles that nuclear energy systems must satisfy to fulfil their promise of meeting growing global energy demands.

Nuclear Material Performance
Nuclear Material Performance

Author: Rehab Abdel Rahman

Publisher: BoD – Books on Demand

Published: 2016-06-29

Total Pages: 174

ISBN-13: 9535124471

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Assessing and improving nuclear material performance is a crucial subject for the sustainability of the nuclear energy and radioactive isotope supplies. This book aims to present research efforts used to identify nuclear materials performances in different areas. The contributions of esteemed international experts have covered important research aspects in fission and fusion technologies and naturally occurring radioactive materials management. The authors introduced current and anticipated trends toward better performances and mitigating challenges for commercial application of innovative technologies, biological remediation of mine effluents, nuclear fuel performance in power and research fission reactors, gamma ray spectrometer calibration, and recent advances in understanding the performance of tungsten composite in fusion reactor environment.

Post-irradiation Examination Techniques for Research Reactor Fuels
Post-irradiation Examination Techniques for Research Reactor Fuels

Author: IAEA

Publisher: International Atomic Energy Agency

Published: 2023-04-18

Total Pages: 149

ISBN-13: 920102021X

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Post-irradiation examination (PIE) is an indispensable step in the selection of new or improved research reactor fuel, and in the characterization and understanding of its in-core behaviour. This publication provides an introduction to PIE techniques. It describes a typical PIE process from intercycle inspections in the reactor pool or channel, to hot cell PIE, which is subdivided into non-destructive and destructive testing techniques with their typical output, advantages and drawbacks, and their applicability to understanding fuel irradiation behaviour. Much of the work presented in this publication originated from the research and development of new low enriched uranium research reactor fuels. Intended readers include research reactor operators, regulators and their technical support organizations, fuel developers and manufacturers, laboratory staff, and policy makers.

Comprehensive Nuclear Materials
Comprehensive Nuclear Materials

Author: Todd R Allen

Publisher: Elsevier

Published: 2011-05-12

Total Pages: 3552

ISBN-13: 0080560334

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Comprehensive Nuclear Materials, Five Volume Set discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials. The work addresses the full panorama of contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds' leading scientists and engineers. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environment Fully integrated with F-elements.net, a proprietary database containing useful cross-referenced property data on the lanthanides and actinides Details contemporary developments in numerical simulation, modelling, experimentation, and computational analysis, for effective implementation in labs and plants