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Oral presentation

Evaluation of residual uranium enrichment in burnt BWR fuel assembly

Sekiya, Yukou*; Takaki, Naoyuki*; Tonoike, Kotaro

no journal, , 

Fuel pellets may be scattered, in the accident of Fukushima Daiichi Nuclear Power Station, without melting in the containment vessels. Precise information of composition of the burnt BWR fuel assemblies is necessary to study the criticality control method for the scattered fuel pellets. In this study, distribution of residual $$^{235}$$U enrichment was evaluated, for each of the reactors, using a model of a fuel-rod array in a fuel assembly.

Oral presentation

Criticality safety evaluation of fuel debris using residual U enrichment by detailed burnup analysis

Sekiya, Yukou*; Takaki, Naoyuki*; Tonoike, Kotaro

no journal, , 

no abstracts in English

Oral presentation

Study on reflection of operating experience of Prototype Fast Breeder Reactor Monju fuel handling system to the next generation FBR

Rekimoto, Masafumi; Ando, Masato; Chikazawa, Yoshitaka; Kato, Atsushi; Hamano, Tomoharu; Shiohama, Yasutaka; Miyagawa, Takayuki*; Uzawa, Masayuki*; Hara, Hiroyuki*; Yamauchi, Kanau*; et al.

no journal, , 

no abstracts in English

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