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Report No.

Recent progress in safety assessments of Japanese water-cooled solid breeder test blanket module

Tsuru, Daigo; Enoeda, Mikio; Akiba, Masato

This reports presents summary of safety assessment activities of the Japanese WCSB TBM. Nuclear analyses have been carried out to calculate neutron flux, tritium breeding ratio, nuclear heat, decay heat and induced activity of radioactive waste are calculated. For the purpose of evaluation of occupational radiolysis exposure, RI inventories in each component are estimated. FMEA has been carried out to identify the PIEs, i.e., the representative events that need safety evaluation. The PIEs are summarized into three groups, i.e., release of RI, pressurization and heatup. With respect to PIEs about release of RI, the maximum released RI is evaluated for three RI inventories, i.e., RI in VV (tritium and radio-activated dust), RI in purge gas (tritium) and RI in coolant (tritium and Active Corrosion Products (ACP)). With respect to PIEs about pressurization, the PIEs of pressurization of the compartment nearby the pipes of cooling system are evaluated by numerical analyses.



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Category:Nuclear Science & Technology



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