원전 중대사고 시 WinMACCS와 RASCAL 전산코드를 이용한 소외 사고결말평가
Off-site Consequence Analysis of Nuclear Power Plant Severe Accident Using WinMACCS and RASCAL Computer Codes
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After the Fukushima nuclear power plant accident in March 2011, the importance ofevaluating the consequence of the accident is increasing. Accordingly, in South Korea, the law onsubmission of accident management plans including severe accidents was revised in June 2016 toassess accident management capability through probabilistic safety assessment. In this study, werecognized the necessity of verifying the results of the level 3 probabilistic safety assessment andcompared the accident consequence through probabilistic and deterministic methods to confirmthe similarity. In this study, the offsite accident consequence was evaluated for the severe accidentscenario of the US Surry nuclear power plant. For each accident scenario, the radiation source termand the meteorological data of the site of Surry nuclear power plant were used. For the probabilisticconsequence assessment, the WinMACCS computer code was used. For the deterministicconsequence assessment, the RASCAL computer code was used. As a result of the offsiteconsequence assessment, the ratio of the result of the RASCAL computer code to the WinMACCScomputer code was evaluated. In the case of LTSBO, it was 0.53~4.24 times. In the case of STSBO,it was 0.57~3.73 times. In the case of ISLOCA, it was 0.24~2.39 times. In the case of TISGTR, itwas 0.16~1.08 times. These differences were due to the differences in the radiation source term,meteorological data, and exposure modeling methods. The results of offsite consequence assessmentwere evaluated at the same order. It was 0.16 times in minimum, 4.24 times in maximum. Therefore,it is expected that the validity and reliability of probabilistic safety assessment can be judgedeconomically. The results of this study can be used as a basis for establishing a domestic level 3probabilistic safety assessment system.
Abstract
After the Fukushima nuclear power plant accident in March 2011, the importance ofevaluating the consequence of the accident is increasing. Accordingly, in South Korea, the law onsubmission of accident management plans including severe accidents was revised in June 2016 toassess accident management capability through probabilistic safety assessment. In this study, werecognized the necessity of verifying the results of the level 3 probabilistic safety assessment andcompared the accident consequence through probabilistic and deterministic methods to confirmthe similarity. In this study, the offsite accident consequence was evaluated for the severe accidentscenario of the US Surry nuclear power plant. For each accident scenario, the radiation source termand the meteorological data of the site of Surry nuclear power plant were used. For the probabilisticconsequence assessment, the WinMACCS computer code was used. For the deterministicconsequence assessment, the RASCAL computer code was used. As a result of the offsiteconsequence assessment, the ratio of the result of the RASCAL computer code to the WinMACCScomputer code was evaluated. In the case of LTSBO, it was 0.53~4.24 times. In the case of STSBO,it was 0.57~3.73 times. In the case of ISLOCA, it was 0.24~2.39 times. In the case of TISGTR, itwas 0.16~1.08 times. These differences were due to the differences in the radiation source term,meteorological data, and exposure modeling methods. The results of offsite consequence assessmentwere evaluated at the same order. It was 0.16 times in minimum, 4.24 times in maximum. Therefore,it is expected that the validity and reliability of probabilistic safety assessment can be judgedeconomically. The results of this study can be used as a basis for establishing a domestic level 3probabilistic safety assessment system.
참고문헌 (22)
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