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Journal Articles

Separation technologies on thermochemical water-splitting iodine-sulfur process

Kubo, Shinji; Yoshida, Mitsunori; Sakurai, Makoto*; Tanaka, Kotaro*; Miyashita, Reiko*

Bunri Gijutsu, 35(3), p.148 - 152, 2005/05

no abstracts in English

Journal Articles

Experiments of continuous gas separation for D$$_{2}$$/He mixed gas under room temperature

Tanzawa, Sadamitsu; Hiroki, Seiji; Abe, Tetsuya

Shinku, 46(3), p.154 - 157, 2003/03

no abstracts in English

JAEA Reports

None

; Koyama, Tomozo; Funasaka, Hideyuki

JNC-TN8400 99-021, 34 Pages, 1999/03

JNC-TN8400-99-021.pdf:1.27MB

None

Journal Articles

Convection-aided separation and its material

Saito, Kyoichi*; *; *; Sugo, Takanobu

Kagaku Kogaku, 58(7), p.553 - 558, 1994/00

no abstracts in English

Journal Articles

Development of separation membrane by radiation induced graft polymerization

Sugo, Takanobu

Nippon Kaisui Gakkai-Shi, 47(4), p.235 - 241, 1993/00

no abstracts in English

Journal Articles

Chemical analysis technology and separation technology (2)

Radioisotopes, 21(2), p.145 - 153, 1972/02

no abstracts in English

Oral presentation

Investigation on reduction of volume of HLW of HTGR; Confirmation on reduction of volume of HLW with disposal scenario and separation

Fukaya, Yuji; Ohashi, Hirofumi

no journal, , 

Investigation on the reduction of HLW of HTGR have been performed. First, The number of waste packages and repository footprint of HLW of HTGR, which have an advantage in reduction of waste due to high burn-up and high thermal efficiency, were evaluated and compared with those of LWR. As a result, the number and footprint is reduced by 60% for direct disposal, and by 30% for disposal with reprocessing. Second, the disposal method and scenario are optimized for HLW of HTGR. With horizontal emplacement and extending cooling time of 40 years, the repository footprint is reduced by 50% for direct disposal, and by 80% for disposal with reprocessing. Furthermore, the number of waste packages can be reduced by 60% with partitioning, the repository footprint can be reduced by 90% with horizontal emplacement and extended cooling time about 150 years.

Oral presentation

Separation technology for reprocessing process in future nuclear system and role of partitioning and transmutation technology

Yamaguchi, Akira*; Matsumura, Tatsuro; Ikeda, Takao*

no journal, , 

no abstracts in English

Oral presentation

Development of separation method for actinides and fission products by solvent extraction, 1; Outline explanation

Sasaki, Yuji; Matsumiya, Masahiko*

no journal, , 

In Japan, the decreases of radioactive waste and its toxicity in HLW are noticed. Thus we need to recover Cs and Sr of heat source and Mo and platinum group metals of limiting factor to produce solidified glass, and treat them by proper method. From these ideas, it is important to develop the four-group partitioning process that JAEA conducted energetically. We focus on the recovery of actinides and fission products by solvent extraction method, and explain the outline in this conference.

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