Phenomena Identification and Ranking Table for the APR-1400 Main Steam Line Break |
Song, J.H.
(Korea Atomic Energy Research Institute)
Chung, B.D. (Korea Atomic Energy Research Institute) Jeong, J.J. (Korea Atomic Energy Research Institute) Baek, W.P. (Korea Atomic Energy Research Institute) Lee, S.Y. (Korea Power Engineering Company) Choi, C.J. (Korea Power Engineering Company) Lee, C.S. (Korea Power Engineering Company) Lee, S.J. (Korea Nuclear Fuel Company) Um, K.S. (Korea Nuclear Fuel Company) Kim, H.G. (Korea Hydro and Nuclear Power) Bang, Y.S. (Korea Institute of Nuclear Safety) |
1 | H. Song, K. H. Bae, 2000, Evaluation of Analytically Scaled Model of a Pressurized Water Reactor Using the RELAP5/MOD3 Computer Code, Nucl. Eng. Des., 199, pp.215-225 DOI ScienceOn |
2 | W. P. Baek, C. H. Song, B. J. Yun, T. S. Kwon, S. K. Moon, S. J. Lee, KAERI Integral Effect Test Program and the ATLAS Design, F00201, The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Seoul, Korea, October 5-9, (2003) |
3 | ABB-CE, 1987, CESEC user^i manual, CEECES-78 Rev. O-P |
4 | C.S. Lee, 1996, Analysis methodology for the post-trip return to power steam line break event, KAERI/TR-698/96, KAERI |
5 | W.J. Lee et. al., 2002, Development of Realistic Thermal Hydraulic System Analysis Code, KAERI/RR-2235/2001, KAERI |
6 | G. E. Wilson, B. E. Boyack, B. D. Cheung, L. E. Hochreiter, J. N. Reyes, J. M. Cozzol, 2001, Phenomena Identification and Ranking Tabulation, KNGR LBLOCA, INEEL, WFO861702 |
7 | B. D. Chung et. al., Phenomena Identification and Ranking Tabulation for APR-1400 Direct Vessel Injection Line Break, C.D. Rom, F00211, The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Seoul, Korea, October 5-9, 2003 |
8 | G. E. Wilson, C. D. Fletcher, C. B. Davis, J. D. Burtt, T. J. Boucher, 1997, Phenomena Identification and Ranking Tables for Westinghouse AP600 SBLOCA, MSLB, and SGTR Scenarios, NUREG/CR-6451 |
9 | J. N. Reyes Jr., L. Hochreiter, 1998, Scaling analysis for the OSU AP600 test facility (APEX), Nucl. Eng. Des., 186, 53-109 DOI ScienceOn |
10 | B. D. Chung, J. H. Song, S. K. Sim, W. J. Lee, J. J. Jeong., 1997, Development of Preliminary PIRT of Thermal-Hydraulic Phenomena for 330MWt SMART Integral Reactor, KAERI/TR-912/97, KAERI |
11 | KEPCO, 2001, APR-1400 SSAR, Chapter 15 |
12 | G. E. Wilson, B. E. Boyack, 1998, The role of the PIRT process in experiments, code development and code applications associated with reactor safety analysis, Nucl. Eng. Des. 186, 23-37 DOI ScienceOn |
![]() |