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Oral presentation

Completion of the Handbook on Process and Chemistry of Nuclear Fuel Reprocessing, 3rd edition

Tsubata, Yasuhiro; Asakura, Toshihide; Tsutsui, Nao; Ban, Yasutoshi; Hotoku, Shinobu; Matsumura, Tatsuro; Morita, Yasuji; Homma, Shunji*

no journal, , 

The fundamental data on spent nuclear fuel reprocessing and related chemistry was collected and summarized as the 3rd edition of The "Handbook on Process and Chemistry of Nuclear Fuel Reprocessing". The purpose of this handbook is contribution to R&D on the spent fuel reprocessing and fuel cycle technology for high burnup uranium fuel and mixed oxide fuel utilization in near future, including minor actinides separation and recovery. Revised contents in this book was discussed and reviewed by specialists of science and technology on fuel reprocessing in Japan. In this poster presentation, the aim of the revised handbook and outline of revised data are introduced.

Oral presentation

Selective separation of platinoid elements using adsorbents bearing zwitterion moiety

Suzuki, Tomoya; Morita, Keisuke; Sasaki, Yuji; Matsumura, Tatsuro

no journal, , 

no abstracts in English

Oral presentation

Development of U and Pu co-processing process in the Tokai Reprocessing Plant

Kudo, Atsunari; Yanagibashi, Futoshi; Hoshi, Takahiro; Tada, Kazuhito; Sato, Takehiko; Fujimoto, Ikuo; Obu, Tomoyuki

no journal, , 

no abstracts in English

Oral presentation

Partitioning behavior of plutonium by acid split method using centrifugal contactors

Nakahara, Masaumi; Koma, Yoshikazu; Nakajima, Yasuo

no journal, , 

Acid split flow sheet without a Pu reductant for U and Pu co-recovery was investigated, and a countercurrent experiment using centrifugal contactors was carried out with a dissolver solution of irradiated fast reactor fuel. Partitioning of Pu has advantage under the conditions of low temperature and low HNO$$_{3}$$ concentration solution, and acid split flow sheet was evaluated by extraction calculation code. In the flow sheet, U scrubbing section was deleted, and Pu was stripped with 0.15 mol/dm$$^{3}$$ HNO$$_{3}$$. Then, the Pu content of the U/Pu product increased to approximately 2.3 times that of the feed solution.

Oral presentation

Elucidation for thermal decomposition behaviour of the high-level radioactive liquid waste; Effect on the thermal decomposition reaction of lanthanoid/alkali metal nitrates caused by ruthenium

Kawai, Kota*; Nakano, Yoshio*; Takeshita, Kenji*; Nagai, Takayuki; Kobayashi, Hidekazu; Amamoto, Ippei; Ayame, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Research and development of minor actinide separation process with novel extractants

Matsumura, Tatsuro; Suzuki, Hideya; Tsubata, Yasuhiro; Shibata, Mitsunobu; Kurosawa, Tatsuya; Kawasaki, Tomohiro; Sagawa, Hiroshi

no journal, , 

no abstracts in English

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