Analysis of severe accident progression and Cs behavior for SBO event during mid-loop operation of OPR1000 using MELCOR |
Park, Yerim
(Department of Nuclear Engineering, Hanyang University)
Shin, Hoyoung (Department of Nuclear Engineering, Hanyang University) Kim, Seungwoo (Department of Nuclear Engineering, Hanyang University) Jin, Youngho (Department of Nuclear Engineering, Hanyang University) Kim, Dong Ha (Department of Nuclear Engineering, Hanyang University) Jae, Moosung (Department of Nuclear Engineering, Hanyang University) |
1 | L.N. Kmetyk, T.D. Brown, Part 2, Evaluation of Potential Severe Accidents during Low Power and Shutdown Operations at Grand Gulf, Unit 1: Evaluation of Severe Accident Risks for Plant Operational State 5 during a Refueling Outage, vol. 6, 1995. NUREG/CR-6143, SAND93-2440. |
2 | Korea Hydro, Nuclear Power Co, LPSD Internal Events Level 2 PSA Report for Shin-Kori Units 1&2, , Ltd, 2015. |
3 | S.M. Bowman, I.C. Gauld, OrigenArp Primer, How to Perform Isotopic Depletion and Decay Calculations with SCALE/ORIGEN, 2010. ORNL/TM-2010/43. |
4 | S. Nishioka, K. Nakajima, E. Suzuki, M. Osaka, An experimental investigation of influencing chemical factors on Cs-chemisorption behavior onto stainless steel, J. Nucl. Sci. Technol. 56 (11) (2019) 995-998. |
5 | Korea Hydro, Nuclear Power Co., Ltd, LPSD Internal Events Level 1 PSA Report for Shin-Kori Units 1&2, 2015. |
6 | S. Kim, S. Park, Y. Seo, M. Jae, An Evaluation of Core Inventory for Reactor Types by Using ORIGEN, 2019. NSTAR-19NS12-82. |
7 | International Atomic Energy Agency, Nuclear Power Reactors in the World 2019 Edition, Vienna, 2019. |
8 | L.L. Humphries, B.A. Beeny, C. Faucett, F. Gelbard, T. Haskin, D.L. Louie, J. Philips, MELCOR Computer Code Manuals Vol. 2: Reference Manual, Sandia National Laboratories, 2019, pp. SAND2019-12537O. |
9 | K. Nakajima, S. Nishioka, E. Suzuki, M. Osaka, Study on chemisorption model of cesium hydroxide onto stainless steel type 304, Mechanical Engineering Journal 7 (2020). Issue 3 19-00564. |
10 | Y. Son, et al., Detailed Thermal-Hydraulic Analysis for Korea Standard Nuclear Power Plant during Low Power/Shutdown Operation, 2004. KAERI/TR-2680/2004. |
11 | Korea hydro & nuclear power Co., ltd, At-Power Level 2 PSA Report for Shin-Kori Units 1&2 (2015). |
12 | L.L. Humphries, B.A. Beeny, F. Gelbard, D.L. Louie, J. Philips, MELCOR Computer Code Manuals Vol. 1: Primer and Users' Guide, Sandia National Laboratories, 2019, pp. SAND2019-12536O. |
13 | U.S. Nuclear Regulatory Commission, Loss of Residual Heat Removal System: Diablo Canyon, Unit 2, April 10, 1987, NUREG-1269. |
14 | V. Mubayi, J. Jo, C. C. Lin, L. Neymotion, W. T. Pratt, Evaluation of severe accident risk during mid-loop operation at Surry unit-1, fourth international conference on nuclear engineering (ICONE-4), new orleans, LA, March 10-14, 1996, BNL-NUREG-62012. |
15 | Y. Jin, et al., Validation of Accident Analysis Capability of MARS Code during Shutdown Operation, 2003. KAERI/TR-2442-2003. |
16 | Korea Hydro, Nuclear Power Co, Ltd, Probabilistic Safety Assessment Report for Shin-Kori Unit 1&2 Part 1, Internal Events, 2011. |
17 | Korea Hydro, Nuclear Power Co, Ltd, Final Safety Analysis Report for Shin-Kori Units 1&2 (2016). |
18 | U.S. Nuclear Regulatory Commission, Loss of Vital AC Power and the Residual Heat Removal System during Mid-loop Operations at Vogtle Unit 1 on March 20, 1990, NUREG-1410. |
![]() |