Post Irradiation Examination Techniques For Research Reactor Fuels

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.

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.

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

This publication represents a summary and proceedings of two technical meetings on the subjects of 1) hot cell post-irradiation examination (PIE) techniques and poolside inspection of water reactor fuel assemblies, and 2) fuel rod instrumentation and in-pile measurement techniques. It provides an overview of the status of in-pile and post-irradiation techniques of water reactor fuel examination with an emphasis on experimental methods applied to high burnup fuel. Further important items addressed at these meetings were the information on progress achieved in non-destructive and destructive PIE techniques used for investigation of water reactor fuels, advanced PIE techniques such as 3-D tomography, as well as advanced in-pile measurement techniques for a better understanding of mechanisms of fuel behavior under irradiation.

This guidebook gives a complete survey of destructive techniques available to perform microstructural examinations, elemental and isotopic analyses and measurement of physical, chemical and mechanical properties of irradiated fuel and structural materials, and describes asociated refabrication and instrumentation techniques. Non-destructive examination (NDE) data are verified by destructive examination (DE) data. The data were submitted to the IAEA by hot laboratories from 12 countries and one international organization (CEC/ITU) during the period 1992-1995. Together with IAEA Technical Reports Series No.322 (1991), Guidebook on non-destructive examination of water reactor fuel, it presents the most comprehensive summary of post-irradiation examination techniques to date.