Abstract
Characteristics of fuel relocation and its effect on safety margin in a loss-of-coolant accident (LOCA) safety analysis have been analyzed. Packing fraction model developed by Quantum Technology was validated and slight modification was conducted based on the formation of high burnup structure model. FAMILY computer code that is an integrated code with FRAPTRAN and MARS-KS is used for the evaluation. The peak cladding temperature (PCT) and peak local oxidation (PLO) of the APR1400 nuclear power plant with the PLUS7 fuel during LOCA were evaluated by a best-estimate plus uncertainty analysis methodology up to 60 MWd/kgU. Fuel relocation resulted in an increase in 95 %/95 % probability/confidence level of the reflood PCT (95/95 reflood PCT) and the PLO (95/95 PLO) until the fuel burnup of ∼ 50 MWd/kgU. Maximum increase of 95/95 reflood PCT was about 130 K at 30 MWd/kgU burnup. This results in the minimum safety margin of the reflood PCT at that burnup with respect to the U.S. NRC proposed 10CFR50.46c PCT limit. Maximum increase of 95/95 PLO was 3.9 percent point at 30 MWd/kgU. However, minimum safety margin was observed at different burnups such as 40 MWd/kgU and 60 MWD/kgU. Regarding the cladding burst characteristics, fuel relocation may lead to an increase in the burst temperature and burst strain of the cladding, and it also induces an earlier failure of cladding.
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