References
- J. M, W.H. Tong, Analysis of Core Damage Frequency: Surry Power Station, Unit 1, Internal Events, NUREG/CR-4550, vol 3, United States Nuclear Regulatory Commission, 1990 rev.1.
- R.C. Bertucio, S.R. Brown, Analysis of Core Damage Frequency: Sequoyah, Unit 1, Internal Events. NUREG/CR-4550, vol 5, United States Nuclear Regulatory Commission, 1990 rev.1.
- M.B. Sattison, K.W. Hall, Analysis of Core Damage Frequency: Zion, Unit 1, Internal Events, NUREG/CR-4550, vol 7, United States Nuclear Regulatory Commission, 1990 rev.1.
- P. Clement, T. Chataing, R. Deruaz, OECD/NEA/CSNI International Standard Problem No.27 - BETHSY Experiment 9.1B 2" Cold Leg Break without HPSI and with Delayed Ultimate Procedure Comparison Report, NEA/CSNI/R(R92)20), vols 1 and 2, OECD Nuclear Energy Agency, 1992.
- H. Asaka, Y. Anoda, Y. Kukita, I. Ohtsu, Secondary-side depressurization during PWR cold-leg small break LOCAs based on ROSA-V/LSTF experiments and analyses, J. Nucl. Sci. Technol. 35 (1998) 905-915. https://doi.org/10.1080/18811248.1998.9733963
- T.-J. Liu, Y.-K. Chan, Y.-M. Ferng, C.-Y. Chang, Experimental investigation of early initiation of primary cooldown by secondary-side depressurization in a PWR inadequate core-cooling accident, Nucl. Technol. 129 (2000) 187-200. https://doi.org/10.13182/NT00-A3056
- P.A. Roth, C.J. Choi, R.R. Schultz, Analysis of Two Small Break Loss-Of-Coolant Experiments in the BETHSY Facility Using RELAP5/MOD3, EGG-NE-10353, Idaho National Engineering Laboratory and EG&G Idaho, Inc, 1992.
- H. Kumamaru, Y. Kukita, H. Asaka, RELAP5/MOD3 code analyses of LSTF experiments on intentional primary-side depressurization following SBLOCAs with totally failed HPI, Nucl. Technol. 126 (1999) 331-339. https://doi.org/10.13182/NT99-A2978
- S.H. Han, S.Y. Park, W. Jung, A Separate Report for Ulchin 3&4 Level 1 PSA, Korea Atomic Energy Research Institute, 1998.
- H.G. Lim, J.-H. Park, S.-C. Jang, The effect of an aggressive cool-down following a refueling outage accident in which a pressurizer safety valve is stuck open, J. Kor. Nucl. Soc. 36 (2004) 497-511.
- S.J. Han, H.G. Lim, J.-E. Yang, An estimation of an operator's action time by using the MARS code in a small break LOCA without a HPSI for a PWR, Nucl. Eng. Des. 237 (2007) 749-760. https://doi.org/10.1016/j.nucengdes.2006.10.016
- J. Cho, J.H. Park, D.-S. Kim, H.-G. Lim, Quantification of LOCA core damage frequency based on thermal-hydraulics analysis, Nucl. Eng. Des. 315 (2017) 77-92. https://doi.org/10.1016/j.nucengdes.2017.02.023
- D.A. Fynan, J. Cho, K.-I. Ahn, Cooldown procedure success criteria map for the full break size spectrum of SBLOCA, Nucl. Eng. Des. 326 (2018) 114-132. https://doi.org/10.1016/j.nucengdes.2017.09.022
- S.-J. Han, J.-E. Yang, Thermal Hydraulic Analysis of a Steam Generator Tube Rupture Accident with Total Loss of High Pressure Safety Injection, KAERI/TR-2731/2004, Korea Atomic Energy Research Institute, 2004.
- J.S. Kim, E.J. Jeong, M.C. Kim, Simulation analysis on steam generator tube rupture with total failure of high pressure safety injection, in: 2018 Korean Nuclear Society Spring Meeting, Jeju, Korea, 2018. May 17-18.
- I.B. Wall, D.W. Worledge, Some perspectives on importance measures, in:Probabilistic Safety Assessment (PSA), Utah, USA, 1996.
- C.L. Smith, Calculating conditional core damage probabilities for nuclear power plant operations, Reliab. Eng. Syst. Saf. 59 (1998) 299-307. https://doi.org/10.1016/S0951-8320(97)00152-X
- M. van der Borst, H. Schoonakker, An overview of PSA importance measures, Reliab. Eng. Syst. Saf. 72 (2001) 241-245. https://doi.org/10.1016/S0951-8320(01)00007-2
- J.B. Fussel, How to hand-calculate system reliability and safety characteristics, IEEE T. Reliab. R-24 (1975) 169-174. https://doi.org/10.1109/TR.1975.5215142
- W.E. Vesely, T.C. Davis, R.S. Denning, N. Saltos, Measures of Risk Importance and Their Applications, NUREG/CR-3385, United States Nuclear Regulatory Commission, 1983.
- PRiME 2.1 HUN 3&4 Model. Daejeon, Korea: Korea Atomic Energy Research Institute.
- S.H. Han, S.W. Lee, S.-C. Jang, H.-G. Lim, J.-E. Yang, Improved features in a PSA software AIMS-PSA, in: 2010 Korean Nuclear Society Spring Meeting, Pyeongchang, Korea, 2010.
- W.S. Jung, S.H. Han, J. Ha, A fast BDD algorithm for large coherent fault tree analysis, Reliab. Eng. Syst. Saf. 83 (2004) 369-374. https://doi.org/10.1016/j.ress.2003.10.009
- Palo Verde Individual Plant Examination, 1992. April 28.
- J.-J. Jeong, K.S. Ha, B.D. Chung, W.J. Lee, Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1, Ann. Nucl. Energy 26 (1999), 1161-1642.
- B.-D. Chung, K.-D. Kim, S.-W. Bae, J.-J. Jeong, S.W. Lee, M.-K. Hwang, C. Yoon, MARS Code Manual Volume I: Code Structure, System Models and Solution Methods, KAERI/TR-2812/2014, Korea Atomic Energy Research Institute, 2010.
- J.-J. Jeong, K.D. Kim, S.W. Lee, Y.J. Lee, W.J. Lee, B.D. Chung, M. Hwang, Development of the MARS Input Model for Ulchin 3/4 Transient Analyzer, KAERI/TR-2620/2003, Korea Atomic Energy Research Institute, 2003.
- H.-G. Lim, J.-H. Park, S.-C. Jang, The effect of an aggressive cool-down following a refueling outage accident in which a pressurizer safety valve is stuck open, J. Kor. Nucl. Soc. 36 (2004) 497-511.
- S.-J. Han, H.-G. Lim, J.-E. Yang, An estimation of an operator's action time by using the MARS code in a small break LOCA without a HPSI for a PWR, Nucl. Eng. Des. 237 (2007) 749-760. https://doi.org/10.1016/j.nucengdes.2006.10.016