Acknowledgement
본 연구는 원자력안전위원회의 재원으로 한국원자력안전재단의 지원을 받아 수행한 원자력안전연구사업의 연구결과입니다. (No. 1805003)
References
- USNRC, 2018, "Consequential SGTR Analysis for Westinghouse and Combustion Engineering Plants with Thermally Treated Alloy 600 and 690 Steam Generator Tubes," U.S. Nuclear Regulatory Commission, Washington DC, NUREG-2195.
- KHNP, 2020, "Final Safety Assessment Report of Wolsong 3,4 units," Korea Hydro & Nuclear Power Co., Ltd.
- IAEA, 2015, "The Fukushima Daiichi Accident," International Atomic Energy Agency, Vienna, Pub-1710.
- Ahn, K. I., Lee, K. H., Lee, S. W., Choi, G. and Hwang, S. W., 2021 "Estimation of fission product source terms for the SGTR accident of a reference PWR plant using MELCOR and MAAP5," NUCL ENG DES, Vol. 371. https://doi.org/10.1016/j.nucengdes.2020.110967
- Lim, C. K., Han, S. K., Kim, S. K., Jin, D. S., Ko, B. J., Hong, Y. H., Ahn, K. I., Park, S. Y., Hwang, S. W., Paul M. and Paik, C. Y., 2020, "Best-estimate analysis for a MSGTR accident of CANDU-6 plants using the MAAP-ISAAC code," NUCL ENG DES, Vol. 359. https://doi.org/10.1016/j.nucengdes.2019.110452
- Lim, C. K., Jin, D. S., Kim, S. Y., Ahn, K. I., Han, S. K., Kim, S. K., Ko, B. J., Hong, Y. H. and Hwang, S. W., 2021, "Off-site consequence analyses of ISLOCA & MSGTR severe accidents in CANDU-6 plants using the WinMACCS code," NUCL ENG DES, Vol. 372. https://doi.org/10.1016/j.nucengdes.2020.110980
- OECD, 2016, "Five Years after the Fukushima Daiichi Accident: Nuclear Safety Improvements and Lessons Learnt," Nuclear Energy Agency, Paris, No. 7284.
- KINS, 2018, "MARS-KS Code Manual," Korea Institute of Nuclear Safety, Daejeon, KINS/RR-1822.
- Yu, S. O., Cho, M. K., Lee, K. W. and Baek, K. L., 2020, "Code Analysis of Effect of PHTS Pump Sealing leakage during Station Blackout at PHWR Plants," Trans. of the KPVP, Vol. 16, No. 1, pp. 11-21. http://dx.doi.org/10.20466/KPVP.2020.16.1.011