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Journal Articles

Benchmark tests of radiation transport computer codes for reactor core and shield calculations

; *; *; *; *; *; ; *; ; ; et al.

Journal of Nuclear Science and Technology, 15(1), p.56 - 71, 1978/01

 Times Cited Count:7

no abstracts in English

Journal Articles

Application of finite element method to two-dimensional multi-group neutron transport equation in cylindrical geometry

; ; ; ; *

Journal of Nuclear Science and Technology, 14(8), p.541 - 550, 1977/08

 Times Cited Count:3

no abstracts in English

Journal Articles

The current status of nuclear codes development in Japan

; ; Katsuragi, Satoru; *; ; *; *; *; Sanokawa, Konomo; ; et al.

Nihon Genshiryoku Gakkai-Shi, 17(7), p.329 - 348, 1975/07

no abstracts in English

JAEA Reports

Oral presentation

Preliminary study on applicability of the multistage centrifugal contactor for nuclear reprocessing

Onishi, Hiroyuki; Washiya, Tadahiro; Myochin, Munetaka

no journal, , 

no abstracts in English

Oral presentation

Development of efficient dissolution technology for FBR MOX fuel, 9; Endurance test of the bearing for rotary dram type continuous dissolver

Katsurai, Kiyomichi; Washiya, Tadahiro; Onishi, Hiroyuki*; Kuroda, Kazuhiko*; Nishikawa, Hideaki*; Nakatani, Tatsuya*; Yamashita, Kazuhiko*; Yoshimine, Chihiro*

no journal, , 

This report presents the knowledge acquired by the endurance test of the bearing used for the rotary drum type continuation dissolver under development as part of Fast Breeder Reactor Cycle technology Development Project (FaCT project). The bearing used for a dissolver is used on high radiation environment and the severe conditions of high load low swing motion operation. In order to check the endurance of the bearing in such conditions, the endurance test of the small scale of hybrid roll bearing using the lubricant which imitated carbon slide bearing as a-less lubricous type, and imitated radiation and heat degradation as a lubricous type was carried out, and the applicability to dissolver bearing was evaluated.

Oral presentation

FaCT phase-I evaluation on advanced aqueous reprocessing process, 4; Co-recovery of U-Pu-Np by solvent extraction

Koma, Yoshikazu; Shibata, Atsuhiro; Nakahara, Masaumi; Ogino, Hideki; Arai, Yoichi; Onishi, Hiroyuki*; Nakajima, Yasuo; Hirano, Hiroyasu; Washiya, Tadahiro

no journal, , 

Concerning reprocessing technology for spent FBR fuel, the results of development on solvent extraction for co-recovery of U, Pu and Np will be reviewed. Chemical processing simplified by considering the condition that moderate decontamination is allowed and centrifugal contactor that provides better plant operating ratio and less Pu inventory were developed.

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