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Park, Joo Hwan; Song, Ki Chan; Park, Hee Seoung
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2002
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2002
AbstractAbstract
[en] A DUPIC fuel is re-fabricated by dry-reprocess of a spent PWR fuel under proliferation resistance. Especially, the DUPIC fuel includes a number of fission products as well as UO2 and Pu since the spent PWR fuels turn into the powders by OREOX process and are sintered at several times in the high temperature furnace. Therefore, the material properties of DUPIC pellets are much different those of PWR or CANDU pellets and those make thermal and mechanical behavior of DUPIC pellets be different from others. Recently, the irradiation tests of DUPIC fuel fabricated under OREOX process have been performed in HANARO research reactor at KAERI in order to evaluate the performance of DUPIC fuel. Presently, the 4th irradiation test of DUPIC fuel is carrying out in HANARO. Up-to now, the thermal and mechanical behavior of DUPIC fuel has been evaluated by using the FEMAXI-IV code modified for DUPIC fuel application. In this report, the program characteristics and analysis models of FEMAXI-V which was updated with FEMAXI-IV code and the differences between FEMAXI-IV and FEMAXI-V are described. And the thermal and mechanical behaviors of DUPIC fuel were predicted with the power history of HANARO irradiation of the 4th DUPIC fuel by FEMAXI-V code. The results of FEMAXI-V are compared with those of FEMAXI-IV using the same input data of FEMAXI-V code. From the comparisons of the results of FEMAXI-IV and FEMAXI-V, it was shown that the selections of analysis model option and input data of FEMAXI-V as well as the calculation results by FEMAXI-V were appropriate. Finally, the several kinds of analysis models required to the application of DUPIC thermal and mechanical performance to FEMAXI-V were suggested
Primary Subject
Source
Jul 2002; 62 p; 17 refs, 23 figs, 2 tabs
Record Type
Report
Report Number
Country of publication
COMPUTER CODES, ENERGY SOURCES, ENRICHED URANIUM REACTORS, FUELS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, ISOTOPES, MATERIALS, MATERIALS TESTING REACTORS, NUCLEAR FUELS, PELLETS, POOL TYPE REACTORS, POWER REACTORS, RADIOACTIVE MATERIALS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TEST FACILITIES, TEST REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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