Creep resistance evaluation on KAERI cladding tubes for nuclear fuel
AbstractAbstract
[en] At present, Zircaloy-4 is widely used as a cladding material for PWRs. However, the demanding operating conditions such as high burnup, extended fuel cycle, high temperature and high pH coolant condition make it unacceptable of the use of Zircaloy-4. In this regard, KAERI have developed 6 advanced cladding tubes and the performance tests on the new tubes are underway. Creep resistance is one of the life-limiting factors of a cladding material. In this paper, the tube creep results are described, which was performed at 350 .deg. C and 400 .deg. C temperatures, and applied hoop stress range of 100-150MPa. The creep resistance was strongly influenced by final annealing temperature in such way that recrystallized tube showed low creep strain than stress-relieved one by a factor of 3, while the effect of intermediate annealing on creep strength was very little. The alloying content of Sn and Nb dominated the creep resistance. The KAERI claddings showed superior or comparable creep resistance to Zircaloy-4 tube
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Source
Korean Nuclear Society, Taejon (Korea, Republic of); [CD-ROM]; Oct 2002; [9 p.]; 2002 autumn meeting of the KNS; Yongpyoung (Korea, Republic of); 24-25 Oct 2002; Available from KNS, Taejon (KR); 8 refs, 8 figs, 2 tabs
Record Type
Miscellaneous
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Conference
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Descriptors (DEI)
Descriptors (DEC)
ALLOYS, ALLOY-ZR98SN-4, CHROMIUM ADDITIONS, CHROMIUM ALLOYS, CORROSION RESISTANT ALLOYS, DEPOSITION, ENERGY SOURCES, FUELS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HEAT TREATMENTS, IRON ADDITIONS, IRON ALLOYS, KOREAN ORGANIZATIONS, MATERIALS, MECHANICAL PROPERTIES, NATIONAL ORGANIZATIONS, REACTOR MATERIALS, SURFACE COATING, TIN ALLOYS, TRANSITION ELEMENT ALLOYS, ZIRCALOY, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
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