Performance degradation of candidate accident-tolerant cladding under corrosive environment
Source abstract
Abstract
Abstract Light-water reactor (LWR) fuel cladding shall retain the performance as the barrier for nuclear fuel materials and fission products in high-pressure and high-temperature coolant under irradiation conditions for long periods. The cladding also has to withstand temperature increase and severe loading under accidental conditions. As lessons learned from the accident at the Fukushima Daiichi nuclear power station, advanced cladding materials are being developed to enhance accident tolerance compared to conventional zirconium alloys. The present paper reviews the progress of the development and summarizes the subjects to be solved for enhanced accident-tolerant fuel cladding, focusing on performance degradation under various corrosive environmental conditions that should be considered in designing the LWR fuel.
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Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
Affiliations
Japan Atomic Energy Agency , 2-4 Shirakata, Tokai-mura, Naka-gun , Ibaraki-ken 319-1195 , Japan
Nippon Nuclear Fuel Development, Co., Ltd. , 2163 Narita-cho, Oarai-machi , Ibaraki-ken 311-1313 , Japan
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