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          Safety and Performance Aspects in the Development and Qualification of High Burnup Nuclear Fuels for Water Cooled Reactors

          Proceedings of a Technical Meeting

          IAEA-TECDOC-2053

          English IAEA-TECDOC-2053 | 978-92-0-118524-2

          156 pages | 2 figures | € 30.00 | Date published: 2024

          https://doi.org/10.61092/iaea.hknc-9tzt

          Download PDF (3.69 MB)

          Description

          This TECDOC aims at illustrating the status in addressing safety and technological challenges encountered in the development, qualification and licensing of HBU nuclear fuels for Water Cooled Reactors (WCRs), summarizing the discussions held at a Technical Meeting organized by the IAEA in November 2022. This publication will provide useful insights for a future revision of IAEA Safety Standards Series No. SSG-52, Design of the Reactor Core for Nuclear Power Plants, as industry trends strongly signal a need to broaden the scope of this safety guide to include high burnup nuclear fuels. This publication is intended for Technical and Scientific Support Organizations (TSOs), regulatory organizations, operators, and research organizations.

          More Information on reusing IAEA copyright material.

          Keywords

          Safety and Performance Aspects, Development, Qualification of High Burnup, HBU, Nuclear Fuels, Water Cooled Reactors, WCRs, Fuel Burnup, Nuclear Engineering, Safety Measures, Safety and Technological Challenges, Licensing, Design of the Reactor Core, Nuclear Power Plants, Industry Trends, Technical and Scientific Support Organizations, TSOs, Regulatory Organizations, Operators, Nuclear Utilities, Feasibility Studies, Operational Limits, Member States, State of Art, Physical Phenomena, Multiphysics and Multiscale Modelling, Simulation Capabilities, Experimental Testing, In-Pile, Out of Pile, Numerical Models, Design Basis Accident, DBA, Loss of Coolant Accident, LOCA, Reactivity Insertion Accident, RIA, Lead Test Assembly, LTA, Lead Test Rod, LTR, Thermomechanical Codes, Validation, Advanced Fuel, Cladding Designs, Irradiation of Test Fuel Rods, Pool-Site Inspections, Post-Irradiation Examination, PIE, Design Codes, Methods for HBU Rates, Safety Reviews, Future Activities, Phenomenological Knowledge and Insights, TRANSURANUS Code Application, Fuel Fragmentation Dispersal, SCIANTIX Grain-Scale Code, Future International Cooperation, Review

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