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Committee for the Joint Research Project between JAERI and Universities; Committee for the Universities' JAERI Collaborative Research
JAERI-Conf 2003-015, 103 Pages, 2003/11
The present report describes the Proceedings of the Symposium on the Joint Research Project between JAERI and Universities - Results of the 4th Phase Joint Research Project and the Future Plan -, held at the University of Tokyo on February 18, 2003. The joint research project composed of the backend chemistry project and the advanced radiation application project was to be concluded in the end of March 2003. Hence the symposium was held in order to review the results obtained in the 4th phase project and to exchange ideas on the effective measures for the future joint collaboration in view of the past activities.
Committee for the Joint Research Project on Backend Chemistry; Committee for the Collaborative Research on the Advanced Radiation Technology
JAERI-Review 2003-001, 97 Pages, 2003/02
no abstracts in English
Ogawa, Toru; Minato, Kazuo
Pure and Applied Chemistry, 73(5), p.799 - 806, 2001/05
Times Cited Count:15 Percentile:54.05(Chemistry, Multidisciplinary)no abstracts in English
Hirata, Masaru
JAERI-Research 96-033, 16 Pages, 1996/06
no abstracts in English
Nihon Genshiryoku Gakkai-Shi, 32(10), p.970 - 974, 1990/10
Times Cited Count:6 Percentile:57.31(Nuclear Science & Technology)no abstracts in English
Toigawa, Tomohiro; Tsubata, Yasuhiro; Matsumura, Tatsuro
no journal, ,
Radiation energy transfer to extraction solvent in minor actinide separation process were simulated by using a Particle and Heavy Ion Transport code System (PHITS). PHITS enabled to calculate the absorbed dose to extraction solvent in situations of intricately shaped apparatus or oil-water mixed state because the code were based on Monte-Carlo algorithm. It was found that the absorbed dose value from -ray depended on the size of the apparatus, while that from alpha-ray was depended on the droplet size in oil-water mixed state. It was demonstrated the degradation yields of the extractant could be evaluated by reference to the experimentally obtained G-values.
Toigawa, Tomohiro; Tsubata, Yasuhiro; Kai, Takeshi; Furuta, Takuya; Kumagai, Yuta; Matsumura, Tatsuro
no journal, ,
Radiation energy transfer to the extraction solvent in minor actinide separation process was simulated by using a Particle and Heavy Ion Transport code System (PHITS). PHITS enabled to calculate the absorbed dose to extraction solvent in situations of intricately shaped apparatus or oil-water mixed state because the code was based on the Monte-Carlo algorithm. Our results suggest that low LET radiation will be the dominant influence on absorbed dose. It was demonstrated the degradation yields of the extractants and the generation yields of the degradation products could be evaluated by reference to the experimentally obtained G-values.