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JAEA Reports

Evaluation of decay heat value from high-level liquid waste; Data for safety assessment of partitioning process

Morita, Yasuji; Tsubata, Yasuhiro

JAEA-Data/Code 2019-015, 45 Pages, 2020/01

JAEA-Data-Code-2019-015.pdf:2.09MB

Decay heat from radioactive elements in high-level liquid waste (HLLW) and separated solutions in partitioning process was evaluated as a basic data for safety assessment of partitioning process. In the evaluation of HLLW from spent UO$$_{2}$$ fuel burned-up to 45 GWd/t in light water reactor, decay heat value from fission products decreased as the cooling period become longer but heat from actinides, Am and Cm, was almost constant until 50-year cooling. Decay heat density in solutions of Am, Cm and rare earth elements and of Am and Cm without concentration for volume reduction does not exceed the heat density of HLLW, but the concentration should be required to minimize the scale of the partitioning process. Separated solution of Am and Cm must be concentrated to convert the two elements to a solid state to make fuel for transmutation, and the decay heat density of the concentrated solution of Am and Cm is 10 times higher compared with the Pu solution of same element concentration. Higher burn-up UO$$_{2}$$ fuel and MOX fuel in light water reactor and minor-actinide-recycled MOX fuel in fast reactor were also considered and the evaluated decay heat was compared among the spent fuels.

JAEA Reports

Development of partitioning process; Extraction behavior and third-phase formation of lanthanoid and iron with DIDPA

Watanabe, Masayuki; Morita, Yasuji; Kubota, Masumitsu

JAERI-Research 99-001, 18 Pages, 1999/01

JAERI-Research-99-001.pdf:0.78MB

no abstracts in English

JAEA Reports

Development of partitioning method; Adsorption of cesium with mordenite in acidic media

L.Donnet*; Morita, Yasuji; Yamagishi, Isao; Kubota, Masumitsu

JAERI-Research 98-058, 63 Pages, 1998/10

JAERI-Research-98-058.pdf:2.19MB

no abstracts in English

Journal Articles

Wet partitioning and waste treatment

Morita, Yasuji; Kubota, Masumitsu

Hoshasei Haikibutsu Kenkyu, 2(1-2), p.75 - 83, 1996/02

no abstracts in English

Journal Articles

Diisodecylphosphoric acid, DIDPA, as an extractant for transuranium elements

Morita, Yasuji; ; Shirahashi, Koichi; ; *; Kubota, Masumitsu

Global 1995,Int. Conf. on Evaluation of Emerging Nuclear Fuel Cycle Systems, 2, p.1163 - 1170, 1995/00

no abstracts in English

Oral presentation

Recent progress on R&D of reprocessing and minor actinide separation process with innovative extractants in CHON principle

Matsumura, Tatsuro; Ban, Yasutoshi; Suzuki, Hideya; Tsubata, Yasuhiro; Hotoku, Shinobu; Tsutsui, Nao; Suzuki, Asuka

no journal, , 

The new reprocessing and minor actinide (MA) separation processes using innovative extractants in accord with CHON principle has been developed in Japan Atomic Energy Agency aimed for reduction of radioactive wastes from nuclear fuel cycle. The new nonorganophosphorus extractants which have appropriate extraction behaviors for each separation steps were developed. Continuous counter-current experiment of each solvent extraction process with uranium, plutonium and tracers of minor actinides were carried out. The experimental results showed that the separation performance of the solvent extraction processes were demonstrated successfully.

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