A Safety Analysis of a Steam Generator Module Pipe Break for the SMART-P |
Kim Hee Kyung
(Korea Atomic Energy Research Institute)
Chung Young-Jong (Korea Atomic Energy Research Institute) Yang Soo-Hyung (Korea Atomic Energy Research Institute) Kim Hee-Cheol (Korea Atomic Energy Research Institute) Zee Sung-Quun (Korea Atomic Energy Research Institute) |
1 | H.K. Kim, SMP65-SA-ST520-03, 'An analysis of a Steam Generator Module Pipe Break for the SMART-P', KAERI, 2004 |
2 | H.Y. Yoon, et al., 'Thermal Hydraulic Model Descnp-tion of TASS/SMR', KAERLTR-1835/2001, 2001 |
3 | H.K. Kim, SMP65-SA-ST520-02, 'An analysis of a Steam Generator Tube Rupture for the SMART-P',KAERI, 2004 |
4 | S.H. Kim, et al., 'Design vehfication program of SMART', Proc. of GENES4/ANP2003, Kyoto, Japan, Sep. 15-19, 2003 |
5 | Proposed ANS standard, 'Decay Energy Release RateFollowing Shutdown of Uranium-Fueled Thermal Reactors', Oct. 1971 |
6 | S.K. Sim, et al., 'TASS Code Topical Report', KAERI/TR-845/97, 1996 |
7 | S.Y. Ryu, SMP65-FS-SD310, Rev 00, 'SMART-P NSSS Design', KAERI, 2002 |
8 | Y.J. Chung, SMP65-SA-03008, 'SMART-P SRDBE', 2003 |
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