Code Analysis of Effect of PHTS Pump Sealing Leakage during Station Blackout at PHWR Plants |
YU, Seon Oh
(Korea Institute of Nuclear Safety)
CHO, Min Ki (Korea Institute of Nuclear Safety) LEE, Kyung Won (Korea Institute of Nuclear Safety) BAEK, Kyung Lok (Korea Institute of Nuclear Safety) |
1 | IAEA, 2015, "The Fukushima Daiichi Accident," International Atomic Energy Agency, Vienna, Pub-1710. |
2 | Harwood, C. and Baschuk, J., 2015, "Assessment of thermal hydraulic phenomena for external water make-up," 35th Annual Conference of CNS, Saint John, Canada, May 31-June 3, pp.1-12. |
3 | Ingham, P. J., Luxat, J. C., Melnyk, A. J., and Sanderson, T.V., 2000, "Natural circulation in an integral CANDU test facility," IAEA-TECDOC-1149, pp.201-212. |
4 | KINS, 2018, "MARS-KS Code Manual," Korea Institute of Nuclear Safety, Daejeon, KINS/RR-1822. |
5 | KHNP, 2018, "Final Safety Assessment Report of Wolsong 3,4 units," Korea Hydro & Nuclear Power Co., Ltd. |
6 | KHNP, 2018, "Technical Specification of Wolsong 3,4 units," Korea Hydro & Nuclear Power Co., Ltd. |
7 | Zhou, F. and Novog, D.R., 2017, "RELAP5 simulation of CANDU Station Blackout accidents with/without water make-up to the steam generators," NUCL ENG DES, Vol. 318, pp.35-53. doi:http://dx.doi.org/10.1016/j.nucengdes.2017.04.014 DOI |
8 | USNRC, 2000, "Improvements of RELAP5/MOD3. 2.2 Models for the CANDU Plant Analysis," U.S. Nuclear Regulatory Commission, Washington DC, NUREG/IA-0189. |
9 | KINS, 2018, "Status of experimental and computational analysis on moderator flow of PHWR," Korea Foundation of Nuclear Safety, Seongnam, NSTAR-18NS21-67. |
10 | KINS, 2019, "Analysis of PHWR system behaviors during SBO accident using MARS-KS code," Korea Foundation of Nuclear Safety, Seongnam, NSTAR-19NS13-131. |
11 | OECD, 2016, "Five Years after the Fukushima Daiichi Accident: Nuclear Safety Improvements and Lessons Learnt," Nuclear Energy Agency, Paris, No. 7284. |