Abstract
Nuclear Energy Safety Organization (JNES) has been carrying out a program of developing methodology of Level 3 PSA [1][2]. In the program, the MACCS2 code has been extensively applied to analyze radiological consequences for typical BWR and PWR plants in Japan. In addition, effects of accident management (AM), which have been implemented by industries, on radiological consequence for a typical BWR with a Mark-II containment have been discussing at JNES used with a developing methodology of Level 2 PSA [3].
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References
Ins/Nupec, Development of Methodology for Radiological Consequence in BWR, (in Japanese) INS/M02-36, 2003
Ins/Nupec, Level 2&3 PSA Study of BWR plants in Japan, (in Japanese), INS/M03-22, vol. 2, 2003
Ins/Nupec, Level 2 PSA Study of BWR plants in Japan, (in Japanese), INS/M02-11, 2003
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© 2004 Springer-Verlag London
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Funayama, K., Sumida, S., Kajimoto, M. (2004). Analysis of Radiological Consequences and its Characteristics in a typical BWR with a MARK-II Containment. In: Spitzer, C., Schmocker, U., Dang, V.N. (eds) Probabilistic Safety Assessment and Management. Springer, London. https://doi.org/10.1007/978-0-85729-410-4_518
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DOI: https://doi.org/10.1007/978-0-85729-410-4_518
Publisher Name: Springer, London
Print ISBN: 978-1-4471-1057-6
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