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Nagase, Fumihisa; Furuta, Teruo; Seino, Shun; Komatsu, Kazushi.
Japan Atomic Energy Research Inst., Tokyo (Japan)1995
Japan Atomic Energy Research Inst., Tokyo (Japan)1995
AbstractAbstract
[en] As the burnup of the LWR fuel is extended, waterside corrosion and hydrogen pickup increase in the Zircaloy cladding. Hydrogen embrittlement of Zircaloy is one of the main factors which may limit the life of the fuel rod. This report presents a review on the hydrogen embrittlement of zirconium and its alloys including the irradiated materials. Research tasks for the reduction of ductility in the high burnup fuel cladding are also discussed. Many fundamental investigations have been performed on the hydrogen embrittlement of zirconium alloys. However, the embrittlement mechanism of the high burnup fuel cladding is complicated. Especially, a coupled effect of hydrides and radiation defects are expected to be pronounced with neutron dose increase. In order to evaluate the reduction of ductility of the higher burnup fuel cladding properly, it is necessary to investigate the coupled effect of these two factors by systematic examinations. (author) 64 refs
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Aug 1995; 127 p
Record Type
Report
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ALLOYS, BEAMS, CRYSTAL STRUCTURE, EMBRITTLEMENT, ENRICHED URANIUM REACTORS, HYDRIDES, HYDROGEN COMPOUNDS, MATERIALS, NUCLEON BEAMS, PARTICLE BEAMS, POWER REACTORS, RADIATION EFFECTS, REACTORS, THERMAL REACTORS, TRANSITION ELEMENT ALLOYS, TRANSITION ELEMENT COMPOUNDS, WATER COOLED REACTORS, WATER MODERATED REACTORS, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS, ZIRCONIUM COMPOUNDS
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