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Journal Articles

Spatial Mesh Effects on Three-Dimensional x-y-z Neutron Diffusion Calculations in Fast Breeder Reactors

Kato, Yasuyoshi*

Nuclear Science and Engineering, 104(4), p.402 - 411, 1990/00

 Times Cited Count:2 Percentile:53.48(Nuclear Science & Technology)

None

JAEA Reports

None

*; Ishiguro, Yukio*; *; Inagaki, Tatsutoshi*; *; *; *; Kato, Yasuyoshi*; Shirakata, Keisho;

PNC TN241 84-07, 16 Pages, 1982/10

PNC-TN241-84-07.pdf:0.37MB

None

JAEA Reports

A Preliminary experimental analysis of the BIZET program; Planning and an alysis of control rod experiment

Matsushima, Hidesuke*; Tsutsumi, Kiyoshi*; Kato, Yasuyoshi*; Urushihara, Hiroshi*; Ueda, Yasuyuki*

PNC TJ202 76-01, 151 Pages, 1976/05

PNC-TJ202-76-01.pdf:6.82MB
PNC-TJ202-76-01VOL1.pdf:2.76MB

no abstracts in English

Oral presentation

Supercritical CO$$_{2}$$ gas turbine fast reactor, 4; Capability test results of cycle test loop

Sato, Hiroyuki; Miyake, Osamu; Ishizuka, Takao*; Muto, Yasushi*; Kato, Yasuyoshi*

no journal, , 

no abstracts in English

Oral presentation

Supercritical CO$$_{2}$$ gas turbine fast reactor, 5; Corrosion test of the structural material in supercritical CO$$_{2}$$

Furukawa, Tomohiro; Aoto, Kazumi; Miyake, Osamu; Kato, Yasuyoshi*

no journal, , 

no abstracts in English

Oral presentation

Carbonization of 12Cr-steel in high-temperature Supercritical CO$$_{2}$$

Furukawa, Tomohiro; Aoto, Kazumi; Miyake, Osamu; Kato, Yasuyoshi*

no journal, , 

no abstracts in English

Oral presentation

Compatibility of core and structural materials of FBRs with the coolants; Lead bismuth eutectic and supercritical CO$$_{2}$$

Furukawa, Tomohiro; Aoto, Kazumi; Miyake, Osamu; Inoue, Masaki; Asayama, Tai; Kato, Yasuyoshi*

no journal, , 

A key problem in the development of advanced fast breeder reactors to use lead bismuth eutectic and supercritical carbon dioxide for the coolant is high temperature corrosion of the structural and core materials. Japan Atomic Energy Agency has been studying the compatibility of the materials with the advanced coolants since 2001. This paper summarizes the results of research until the present.

Oral presentation

Integration of knowledge management support system for the decommissioning of nuclear facilities, 8; The Outcomes of knowledge management support system

Taruta, Yasuyoshi; Kato, Yasuaki; Yanagihara, Satoshi*; Iguchi, Yukihiro; Tezuka, Masashi; Kitamura, Koichi; Koda, Yuya; Mizoguchi, Riichiro*

no journal, , 

no abstracts in English

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