RISK ANALYSIS ON CONTAINMENT BYPASS ACCIDENTS IN M310 NUCLEAR POWER PLANT

Yang Jian; Du Jin Yan; Feng Chu Ran

doi:10.1299/jsmeicone.2019.27.1604

2019.27

セッションID: 1604

DOI https://doi.org/10.1299/jsmeicone.2019.27.1604

会議情報

主催: The Japan Society of Mechanical Engineers

会議名: 第27回原子力工学国際会議（ICONE27）

開催日: 2019/05/19 - 2019/05/24

RISK ANALYSIS ON CONTAINMENT BYPASS ACCIDENTS IN M310 NUCLEAR POWER PLANT

*Yang Jian, Du Jin Yan, Feng Chu Ran

著者情報

キーワード: Probability Safety Analysis(PSA), Containment bypass, Steam generator tube rupture(SGTR), Interfacing systems loss of coolant accident(ISLOCA), Large early release frequency(LERF)

会議録・要旨集認証あり

詳細

抄録

In this paper, Level 1 and 2 PSA model of Fuqing 1 unit was built to quantify the risk of containment bypass accidents. For these containment bypass accidents, the large early release frequency(LERF) is 5.35E-7/r.y. Typical containment bypass accidents, including interfacing-systems LOCA,SGTR initiating event, pressure induced SGTR and temperature induced SGTR were analyzed in this paper. Containment bypass accidents are the main contributor for the LERF of M310 Nuclear Power Plant, and SGTR initiating event accounts for 76 percent in the LERF. Finally, some targeted design improvements were discussed from the point of view of reducing risk in this paper.

責任著者(Corresponding author)

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