Assessment of Post-Irradiation Examination Techniques for Advanced Reactor Fuel and Materials
Assessment of Post-Irradiation Examination Techniques for Advanced Reactor Fuel and Materials

Author: International Atomic Energy Agency

Publisher: International Atomic Energy Agency

Published: 2024-04-08

Total Pages: 0

ISBN-13: 9789201536235

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This publication has been developed based on the results of the Technical Meeting on Advances in Post-Irradiation Examination Techniques for Power-Reactor Irradiated Fuels and Innovative Fuels held in July 2021. It explores the use of existing and new post-irradiation examination (PIE) techniques for the study of next-generation fuel types. Specifically, this publication provides an overall understanding of what important performance parameters are typically studied for each fuel type to properly assess its performance, and what are the relevant PIE techniques required for the analyses. Its intended audience comprises nuclear fuel designers, manufacturers, operators, regulators, academia and policy makers who work with the nuclear fuel community

Analysis of Options and Experimental Examination of Fuels for Water Cooled Reactors with Increased Accident Tolerance (Actof)
Analysis of Options and Experimental Examination of Fuels for Water Cooled Reactors with Increased Accident Tolerance (Actof)

Author: International Atomic Energy Agency

Publisher:

Published: 2020-10-12

Total Pages: 179

ISBN-13: 9789201141200

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There is high interest in new fuel types with increased accident tolerance. These range from using an oxidation resistant coating on zirconium based cladding to alternate fuel and cladding materials. These new fuels/claddings under development must be licensed before being deployed industrially and therefore research is being undertaken to assess their behaviour in various conditions. This publication arises from an IAEA coordinated research project (CRP) dealing with the acquisition of data through experiments on new fuel types and cladding materials and the development of modelling capacity to predict the behaviour of the components and the integral performance of accident tolerant fuel designs under normal and transient conditions. Demonstrations of improvements under severe accident conditions were documented. Several coated cladding materials were produced, tested, characterized and analysed in round robin tests carried out within the CRP. For improvement and validation of fuel performance codes, several benchmarks were organized to compare and analyse predictions of the extended codes. The findings and conclusions of the CRP are summarized in this publication.

Characterization and Testing of Materials for Nuclear Reactors
Characterization and Testing of Materials for Nuclear Reactors

Author: International Atomic Energy Agency

Publisher:

Published: 2007

Total Pages: 158

ISBN-13:

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Industrial growth, energy consumption are seen as measures towards economic developments. With increase in industrial development worldwide, the demand of energy is continually on the rise. Today, the energy industry is facing many challenges. Nuclear fission and nuclear fusion are seen as important future energy sources. Development of innovative reactor designs with large efficiency for fuel burn up is one of the needs of fission reactors. The materials resistant to high dose of radiations in fusion reactors is another major challenge. The production of electricity without global warming is an important pressing demand on the energy sector. The demands on quality control of components for nuclear and heavy industry are very stringent. Development of well characterized, high quality materials is therefore essential for safe, efficient and reliable operation of engineering components. The diagnosis of failure of machinery parts comes from the post operational characterization of materials. Various destructive and non-destructive techniques are used for this purpose. Research reactors have played an important role in non-destructive characterization of materials and have contributed to technology development. This publication focuses on characterization of materials for industries in general and nuclear energy sector in particular. The main focus is on research reactor based techniques with some discussion on other allied methods like positron annihilation.--Publisher's description.

Light Water Reactor Fuel Enrichment Beyond the Five Per Cent Limit: Perspectives and Challenges
Light Water Reactor Fuel Enrichment Beyond the Five Per Cent Limit: Perspectives and Challenges

Author: International Atomic Energy Agency

Publisher:

Published: 2020-10-12

Total Pages: 56

ISBN-13: 9789201109200

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The limitation of 235U enrichment is a current concern among IAEA Member States. In response, work has been undertaken to provide a platform to facilitate a comprehensive review of the current status, prospects and challenges associated with the use of fuels having enrichments higher than 5 % 235U in light water reactors. This publication is the outcome of two technical meetings and compiles the results and conclusions in terms of benefits to be obtained from the use of high assay low enriched uranium (HALEU) fuel, with due consideration of safety issues that arise from its use. It details technological options and corresponding issues regarding fuel and core design, safety analysis and assessments relevant to manufacturing, handling, transportation, storage, irradiation, and performance in normal and accident conditions.

Applications of Research Reactors
Applications of Research Reactors

Author: International Atomic Energy Agency

Publisher: International Atomic Energy Agency

Published: 2014

Total Pages: 108

ISBN-13: 9789201450104

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This publication is a comprehensive study that reviews the current situation in a great number of applications of research reactors. It revises the contents of IAEA TECDOC-1234, The Applications of Research Reactors, giving detailed updates on each field of research reactor uses worldwide. Reactors of all sizes and capabilities can benefit from the sharing of current practices and research enabled via this updated version, which describes the requirements for practicing methods as diverse as neutron activation analysis, education and training, neutron scattering and neutron imaging, silicon doping and radioisotope production, material/fuel irradiation and testing, and some others. Many underutilised research reactors can learn how to diversify their technical capabilities, staff and potential commercial partners and users seeking research reactor services and products. The content of the publication has also been strengthened in terms of current issues facing the vast majority of research reactors by including sections describing user and customer relations as well as strategic planning considerations.

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 Fuel Cycle Simulation System (VISTA)
Nuclear Fuel Cycle Simulation System (VISTA)

Author: International Atomic Energy Agency

Publisher: IAEA

Published: 2007

Total Pages: 112

ISBN-13:

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The Nuclear Fuel Cycle Simulation System (VISTA) is a simulation system which estimates long term nuclear fuel cycle material and service requirements as well as the material arising from the operation of nuclear fuel cycle facilities and nuclear power reactors. It is a scenario based simulation tool which can model several nuclear fuel cycle options including existing nuclear power reactor types and future possible reactor types. The past operations of the power reactors and fuel cycle facilities can be modelled in the system, in order to estimate the current amount of spent fuel stored or total Pu in stored spent fuel. It can also accept future projections for nuclear power and other scenario parameters in order to predict future fuel cycle material requirements.The model has been designed to be an optimum mixture of simplicity, speed and accuracy. It does not require too many input parameters if the purpose is just to compare the requirements for selected scenarios. Furthermore, the accuracy of the system can be improved by introducing more detailed and correct sets of input parameters.

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.