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Journal Articles

Development of plutonium recovery process by molten salt electrorefining with liquid cadmium cathode

Iizuka, Masatoshi*; Uozumi, Koichi*; Inoue, Tadashi*; Iwai, Takashi; Shirai, Osamu; Arai, Yasuo

Proceedings of 6th International Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), p.327 - 341, 2000/00

no abstracts in English

Journal Articles

Research on nitride fuel and pyrochemical process for MA transmutation

Arai, Yasuo; Ogawa, Toru

Proceedings of 6th OECD/NEA International Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, p.445 - 457, 2000/00

no abstracts in English

Oral presentation

Adsorption/elution performance of TEHDGA/SiO$$_{2}$$-P for Am/Cm Recovery from genuine HLLW

Sato, Daisuke; Watanabe, So; Arai, Yoichi; Nakamura, Masahiro; Arai, Tsuyoshi*; Sano, Yuichi; Shibata, Atsuhiro; Takeuchi, Masayuki

no journal, , 

Oral presentation

Management of MOX spent fuel from LWR, 1; Thermal design of direct disposal

Abe, Takumi; Nishihara, Kenji

no journal, , 

In the case of the direct disposal of MOX spent fuel, the temperature of the buffer material surrounding the waste seems to exceed the limitation due to the decay heat higher than that of UO2 spent fuel. To satisfy the limitation, we investigated the impacts of changing some design parameters, and several direct disposal concepts for MOX spent fuel were obtained.

Oral presentation

Current status of R&D on MA separation process using solvent extraction technique for partitioning and transmutation technology

Matsumura, Tatsuro

no journal, , 

The management of high-level radioactive waste is one of the most important issues for the sustainable use of fission energy. Partitioning and transmutation (P&T) technologies for high level waste (HLW) are expected to reduce the burden of disposal by reducing radiotoxicity and heat generation. Minor actinides (MA) have high priority for separation due to their long lifetime and high radio-toxicity. The new MA separation process using innovative extractants in accord with CHON principle has been developed in Japan Atomic Energy Agency (JAEA) for the P&T technology. The new nonorganophosphorus extractants which have appropriate extraction behaviors were developed. Continuous counter-current experiments of each solvent extraction process with genuine HLW were carried out using mixer-settler type extractors. This paper presents the current status of research and development of MA separation processes using solvent extraction methods at JAEA.

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