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Nagaoka, Shinichi; Ishida, Michihiko; Kanamori, Sadamu; Hayashi, Shinichiro
Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 5 Pages, 2011/12
The feasibility of applying PSA to nuclear fuel cycle facilities such as reprocessing plants has been also studied. We conducted a simplified risk assessment of each of the selected individual accident events and compared the assessment results for four accident categories (fire, explosion, criticality, and other accident events in which large amounts of radioactive materials are released).
Nagaoka, Shinichi; Morimoto, Kazuyuki; Sato, Takehiko; Kanamori, Sadamu; Omori, Eiichi
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no abstracts in English
Morimoto, Kazuyuki; Kanamori, Sadamu; Omori, Eiichi
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no abstracts in English
Obu, Tomoyuki; Morimoto, Kazuyuki; Yoshinari, Toshimi; Kanamori, Sadamu; Omori, Eiichi
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no abstracts in English
Kurabayashi, Kazuaki; Kawaguchi, Yoshihito; Takaya, Akikazu; Morimoto, Kazuyuki; Kanamori, Sadamu; Omori, Eiichi
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Plutonium product recovered from Fugen MOX type B spent fuel is measured temperature at Tokai Reprocessing Plant. And we studied difference between estimated by ORIGEN and analytical value of relative promotion on Pu, moreover, we studied calculation model because of the difference between initial evaluation and temperature of Pu product.
Hoshi, Takahiro; Kawaguchi, Yoshihito; Kitao, Takahiko; Oyama, Koichi; Morimoto, Kazuyuki; Kanamori, Sadamu; Omori, Eiichi
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For reprocessing nuclear spent fuel, in future, used for plutonium-thermal and fast-breeding reactor, density of DBP in extraction solvent on reprocessing Fugen MOX Type B fuel was measured. And we formulated an equation for increased density of DBP to estimate density of DBP in extraction cycle.
Kawakami, Yoshiyuki; Nagaoka, Shinichi; Kitao, Takahiko; Morimoto, Kazuyuki; Obu, Tomoyuki; Kanamori, Sadamu; Omori, Eiichi
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We are trying to research how acidity and temperature influences Np behavior at extraction process in Tokai Reprocessing Plant. So we varied acidity and warmed up solution within the limit of operating parameter for second extraction cycle, and measured Np extracted.
Nagaoka, Shinichi; Morimoto, Kazuyuki; Kitao, Takahiko; Obu, Tomoyuki; Kanamori, Sadamu; Omori, Eiichi
no journal, ,
40
50% of neptunium (Np) was distributed to product stream in Tokai Reprocessing Plant (TRP) at present. We tried to increase acidity of second extraction cycle within available operating parameter, and by measuring neptunium concentration at outlet stage in second extraction cycle, we verified that 6070% of neptunium was distributed to product stream. Also we warmed up solutions in contactors of second extraction cycle within available operating parameter to make sure oxidation of neptunium on actual process, and we verified that 70% of neptunium was distributed to product stream. We confirmed that increasing acidity and warming up solutions was effective for Pu-U-Np co-extraction on the engineering scale reprocessing facility.
Nagaoka, Shinichi; Taguchi, Katsuya; Ishida, Michihiko; Kanamori, Sadamu
no journal, ,
no abstracts in English