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Tanimura, Yoshihiko; Birumachi, Atsushi
no journal, ,
no abstracts in English
Takaya, Shigeru; Nagae, Yuji
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no abstracts in English
Mukai, Yasunobu; Kato, Yoshiyuki; Kimura, Yuichi*; Nemoto, Ryo*
no journal, ,
no abstracts in English
Arai, Yoichi; Takeuchi, Masayuki; Kato, Toshihiro*
no journal, ,
no abstracts in English
Imai, Yoshiyuki
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no abstracts in English
Tochio, Daisuke; Inoi, Hiroyuki
no journal, ,
no abstracts in English
Yamashita, Shinichiro
no journal, ,
no abstracts in English
Hayashi, Takao; Masaki, Kei; Arai, Takashi; Miya, Naoyuki
no journal, ,
no abstracts in English
Kato, Tomoko; Suzuki, Yuji*; Oi, Takao
no journal, ,
no abstracts in English
Tochigi, Yoshikatsu
no journal, ,
no abstracts in English
Kato, Junya; Miyauchi, Atsushi; Yamasaki, Akito*
no journal, ,
no abstracts in English
Nakahara, Masaumi; Sano, Yuichi; Nomura, Kazunori
no journal, ,
Concerning the advance aqueous reprocessing system named NEXT process, the simplified solvent extraction process was conducted for U, Pu and Np co-recovery in JAEA. In this study, the feed solution or scrubbing solution were adjusted to high nitric acid concentration, which the extraction and oxidation behavior of Np were estimated using the dissolver solution of irradiated fast reactor fuel. These experimental results showed the large contribution of nitric acid concentration at the extraction section to Np oxidation and extraction, and the effectiveness of high nitric acid concentration in the feed solution, which might bring the acceleration of the Np oxidation in the feed solution as well as at the extraction section in the centrifugal contactors.
Gunji, Ikuko; Tabata, Rimiko; Otoshi, Sachio*; Kuwagaki, Reiko*; Ishibashi, Yoichiro*
no journal, ,
no abstracts in English
Kitao, Takahiko; Nemoto, Hirokazu*; Yamada, Keiji; Sakai, Toshio
no journal, ,
no abstracts in English