Study on severe accident mitigation measures for the development of PWR SAMG

MISCELLANEOUS

Study on severe accident mitigation measures for the development of PWR SAMG

ZHANG Kun，

CAO Xue-Wu，

CHE Ji-Yao

Nuclear Science and Techniques

Vol.17, No.4

pp.245-251

Published in print 20 Aug 2006

DOI：10.1016/S1001-8042(06)60046-8

CLC：TL364+.4

38800

In the development of the Severe Accident Management Guidelines (SAMG), it is very important to choose the main severe accident sequences and verify their mitigation measures. In this article, Loss-of-Coolant Accident (LOCA), Steam Generator Tube Rupture (SGTR), Station Blackout (SBO), and Anticipated Transients without Scram (ATWS) in PWR with 300 MWe are selected as the main severe accident sequences. The core damage progressions induced by the above-mentioned sequences are analyzed using SCDAP/RELAP5. To arrest the core damage progression and mitigate the consequences of severe accidents, the measures for the severe accident management (SAM) such as feed and bleed, and depressurizations are verified using the calculation. The results suggest that implementing feed and bleed and depressurization could be an effective way to arrest the severe accident sequences in PWR.

SAMGSevere accidentMitigation measures

References

[1]

Sandia National Laboratory. Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants. USNRC NUREG-1150. 1990.

[2]

Southern California Edison.

Individual Plant Examination Report for San Onofre Nuclear Generating Station Units 2 and 3

. 1993.

Baidu Scholar

Google Scholar

[3]

Omaha Public Power District Fort Calhoun Station Individual Plant Examination Submittal. 1993, Volume 1.

[4]

XU Yiquan, CHE Jiyao, SU Yun, et al. Nuclear Power Engineering (in Chinese), 2004, (6): 546-549.

[5]

Report of the RAMP Mission to the Krško Nuclear Power Plant. Review of accident management programmes mission. IAEA-TCR-00959. 2001

Baidu Scholar

Google Scholar

[6]

CHE Jiyao, CAO Xuewu. Nuclear Power Engineering (in Chinese), 2005, (3): 209-213.

[7]

LI Jigen, YU Erjun, DAI Chuanzeng. Nuclear Science and Engineering (in Chinese), 1996, (3):193-199.

[8]

XU Yiquan, SU Yun, CAO Xuewu. Nuclear Power Engineering (in Chinese), 2004, (3): 279-283.