Validation of RCS depressurization strategy and core coolability map for independent scenarios of SBLOCA, SBO, and TLOFW

References

• ElBaradei M. Severe accident management programs for nuclear power plants. Vienna (Austria): International Atomic Energy Agency; 2009.
   Google Scholar
• Organisation for Economic Co-operation and Development/Nuclear Energy Agency. Core exit temperature effectiveness in accident management of nuclear power reactor. NEA/CSI/R(2010)9. Paris (France): Nuclear Energy Agency; 2010.
   Google Scholar
• International Atomic Energy Agency. Approaches and tools for severe accident analysis for nuclear power plants. Vienna (Austria): International Atomic Energy Agency; 2008.
   Google Scholar
• Vierow K, Liao Y, Johnson J, Kenton M, Gauntt R. Severe accident analysis of a PWR station blackout with the MELCOR, MAAP4 and SCDAP/RELAP5 codes. Nucl Eng Des. 2004;234:129–145.
   Web of Science ®Google Scholar
• Wang T-C, Wang S-J, Teng J-T. Comparison of severe accident results among SCDAP/RELAP5, MAAP, and MELCOR codes. Nucl Technol. 2005;150:145–152.
   Web of Science ®Google Scholar
• Park R-J, Hong S-W. Effect of SAMG entry condition on operator action time for severe accident mitigation. Nucl Eng Des. 2011;241:1807–1812.
   Web of Science ®Google Scholar
• Park R-J, Kim S-B, Kim H-D. Evaluation of the RCS depressurization strategy for the high pressure sequence by using SCDAP/RELAP5. Nucl Eng Des. 2008;35:150–157.
   Web of Science ®Google Scholar
• Park R-J, Kim S-B, Hong S-W, Kim H-D. Detailed evaluation of coolant injection into the reactor vessel with RCS depressurization for the high pressure sequences. Nucl Eng Des. 2009;239:2484–2490.
   Web of Science ®Google Scholar
• Huang IM, Ferng YM, Wang SJ. Validation of RCS Bleed-And-Feed strategy for the SAMG of the Kuosheng nuclear power plant. Nucl Technol. 2007;160:294–306.
   Web of Science ®Google Scholar
• Martin-Fuertes F, Martin-Valdepenas JM, Mira J, Sanchez MJ. A MELCOR application to two light water reactor nuclear power plant core melt scenarios with assumed cavity flooding action. Nucl Technol. 2003;144:34–48.
   Web of Science ®Google Scholar
• Song JH, Huh CW, Suh N. Improvement of molten core cooling strategy in a severe accident management guideline. Nucl Technol. 2012;178:258–266.
   Web of Science ®Google Scholar
• Korea Atomic Energy Research Institute. Development of accident management guidance for Korean standard nuclear power plant. Daejeon (Republic of Korea): Korea Atomic Energy Research Institute; 1998.
   Google Scholar
• Boyack BE, Dhir VK, Gieseke JA, Haste TJ, Kenton MA, Khatib-Rahbar M, Leonard MT, Viskanta R. MELCOR peer review. Los Alamos Report, DC92012220. Los Alamos (NM): Los Alamos National Laboratory; 1997.
   Google Scholar
• Gauntt RO, Cash JE, Cole RK, Erickson CM, Humphries LL, Rodriguez SB, Young MF. MELCOR Computer Code Manual. NUREG/CR-6119, Rev.3, SAND 2005-5713. Albuquerque (NM): Sandia National Laboratories; 2005.
   Google Scholar
• Huh C, Suh N, Park G-C. Optimum RCS depressurization strategy for effective severe accident management of station black out accident. Nucl Eng Des. 2009;239:2521–2529.
   Web of Science ®Google Scholar
• Wang TC, Wang S-J, Teng J-T. Simulation of a PWR reactor vessel level indicating system during station blackout with MELCOR 1.8.5. Nucl Technol. 2006;156:133–139.
   Web of Science ®Google Scholar
• Haste TJ, Birchley J, Richner M. Accident management following loss-of-coolant accidents during cooldown in a Westing two-loop PWR. Nucl Eng Des. 2010;240:1599–1605.
   Web of Science ®Google Scholar
• Bonelli A, Mazzantini O, Sonnenkalb M, Caputo M, García JM, Zanocco P, Gimenez M. Station black-out analysis with MELCOR 1.8.6 code for Atucha 2 nuclear power plant. Sci Technol Nucl Install. 2012;620298.
   Web of Science ®Google Scholar
• Bixler N, Gauntt R, Jones J, Leonard M. State-of-the-art reactor consequence analyses Project-Volume 1 & 2. Washington (DC): Nuclear Regulatory Research; 2012.
   Google Scholar
• Birchley J, Haste TJ, Richner M. Accident management following loss of residual heat removal during mid-loop operation in a Westinghouse two-loop PWR. Nucl Eng Des. 2008;238:2173–2181.
   Web of Science ®Google Scholar
• Yong KY, et al. Development of the application scheme for the severe accident diagnosis/assessment code. Daejeon (Republic of Korea): Korea Institute of Nuclear Safety; 2010.
   Google Scholar
• Ahn K-I, Park S-Y. Development of a risk-informed accident diagnosis and prognosis system to support severe accident management. Nucl Eng Des. 2009;239:2119–2133.
   Web of Science ®Google Scholar
• Korea Hydro & Nuclear Power. Shin kori 1&2 final safety analysis report. Seoul (Republic of Korea): Korea Hydro & Nuclear Power; 2008.
   Google Scholar
• Kim HC, Lee SH, Kim TH, Kim DS, Kim SC, Ryu YH. Evaluation of the status of the accident management guidelines in Korea and foreign countries. Daejeon (Republic of Korea): Korea Institute of Nuclear Safety; 2013.
   Google Scholar