과제정보
연구 과제 주관 기관 : Korea Radiation Safety Foundation, National Research Foundation of Korea (NRF)
참고문헌
- S. Basu, T. Ginsberg, Report of the 2nd Steam Explosion Review Group Workshop (SERG2), NUREG-1524, 1996.
- R. Meignen, D. Magallon, K.-H. Bang, G. Berthoud, S. Basu, M. Burger, M. Buck, M.L. Corradini, H. Jacobs, O. Melikhov, M. Naitoh, K. Moriyama, R. Sairanen, J.-H. Song, N. Suh, T.G. Theofanous, Comparative Review of FCI Computer Models Used in the OECD-serena Program, Proceedings of International Congress on Advances in Nuclear Power Plants (ICAPP'05), Seoul, Korea, Paper 5087, 2005.
- Organization for Economic Co-operation and Development, Nuclear Energy Agency (OECD/NEA), OECD Research Program on Fuel-coolant Interaction: SteamExplosion Resolution for Nuclear Applications-SERENA, Final Report, NEA/CSNI/R(2007) 11, 2007.
- K. Moriyama, Y. Maruyama, H. Nakamura, Steam Explosion Simulation Code JASMINE v.3 User's Guide, JAEA-Data/Code 2008-014, 2008.
- K. Moriyama, H. Nakamura, A Strategy for the Application of Steam Explosion Codes to Reactor Analysis, Proc. Technical Meeting on Severe Accident and Accident Management, Tokyo, Japan, 2006.
- K. Moriyama, Y. Maruyama, H. Nakamura, A simple evaluation method of the molten fuel amount in a premixing region of fuel-coolant interactions, Journal of Nuclear Science and Technology 39 (2002) 53-58. https://doi.org/10.1080/18811248.2002.9715156
- A. Annunziato, C. Addabo, A. Yerkess, R. Silverii, W. Brewka, G. Leva, FARO Test L-14 on Fuel-coolant Interaction and Quenching-Comparison Report, in: Analysis of the Results-OECD/CSNI International Standard Problem 39, Volume I, OECD/NEA/CSNI, NEA/CSNI/R (97) 31/Part I, 1998.
- D. Magallon, Characteristics of corium debris bed generated in large-scale fuel-coolant interaction experiments, Nucl. Eng. Des. 236 (2006) 1998-2009. https://doi.org/10.1016/j.nucengdes.2006.03.038
- Organization for Economic Co-operation and Development, Nuclear Energy Agency (OECD/NEA), OECD/SERENA Project Report, Summary and Conclusions, NEA/CSNI/R 15 (2014), 2015.
- K. Moriyama, Y. Maruyama, T. Usami, H. Nakamura, Coarse Break-up of a Stream of Oxide and Steel Melt in a Water Pool, JAERI-Research 2005-017, Japan Atomic Energy Research Institute, 2005.
피인용 문헌
- Analysis of Steam Explosion under Conditions of Partially Flooded Cavity and Submerged Reactor Vessel vol.2018, pp.None, 2018, https://doi.org/10.1155/2018/3106039