RISK ANALYSIS ON CONTAINMENT BYPASS ACCIDENTS IN M310 NUCLEAR POWER PLANT

• Jian Yang

  China Nuclear Power Engineering CO.LTD

• Jin Yan Du

  China Nuclear Power Engineering CO.LTD

• Chu Ran Feng

  China Nuclear Power Engineering CO.LTD

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.

収録刊行物

• Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE

  Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE 2019.27 (0), 1604-, 2019

  一般社団法人 日本機械学会

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)

詳細情報

• CRID: 1390283659833012352
• NII論文ID: 130007773611
• DOI: 10.1299/jsmeicone.2019.27.1604
• ISSN: 24242934
• Web Site: https://www.jstage.jst.go.jp/article/jsmeicone/2019.27/0/2019.27_1604/_pdf
• 本文言語コード: en
• データソース種別:
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  • Crossref
  • CiNii Articles
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