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Search Results: Records 1-20 displayed on this page of 32

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Journal Articles

Development of cold source moderator structure

Aso, Tomokazu; Ishikura, Shuichi*; Terada, Atsuhiko*; Teshigawara, Makoto; Watanabe, Noboru; Hino, Ryutaro

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/04

no abstracts in English

Journal Articles

Flow study on the ESS target water model

Haga, Katsuhiro; Takeda, Yasushi*; Bauer, G.*; Guttek, B.*

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/04

no abstracts in English

Journal Articles

Real-time neutron monitoring method using an imaging plate

Sakasai, Kaoru; Katagiri, Masaki; Kishimoto, Maki; Fujii, Yoshio

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 6 Pages, 1999/04

no abstracts in English

Journal Articles

Flow-induced vibration test of thermowell in the secondary cooling system of the proyotype FBR

*

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7), 0 Pages, 1999/00

None

Journal Articles

On-line support of the FUGEN plant using MARS

Iguchi, Yukihiro; Sotsu, Masutake; Mizuno, Koichi

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7), 0 Pages, 1999/00

None

Journal Articles

Development of A Low Reynolds Number Turbulence Stress and Heat FluxEquation Models - A New Type Wall Boundary Condition for Dissipation Rate of Turbulent Kinetic Energy Aided by DNS Data Base -

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7), 0 Pages, 1999/00

None

Journal Articles

Pesponse of Water Filled Calandria Vessel to Pressure Tube Rupture

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7), 0 Pages, 1999/00

None

Journal Articles

Response of a Water Filled Calandria Vessel to Explosion

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7), 0 Pages, 1999/00

None

Journal Articles

Measurement and Analysis of Decay Heat of Fast Reactor Spent Fuel

Aoyama, Takafumi; Torimaru, Tadahiko; Nose, Shoichi; ;

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7), 0 Pages, 1999/00

None

Journal Articles

Direct Numerical Simulation of Liquid Sodium Droplet Combustion in Forced Convection Air Flow

Okano, Yasushi; Yamaguchi, Akira

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7), 0 Pages, 1999/00

None

Journal Articles

Three Dimensional Particle Method Code for Sodium Leakage Analysis in Liquid Metal Reactor

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7), 402 Pages, 1999/00

None

Journal Articles

Applications of the SIMMER-III fast reactor safety analysis code to thermal interactions of melts with sodium and water

; ; Flad, M.*; Arnecke, G.*; P.Coste*

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7), 0 Pages, 1999/00

None

Journal Articles

Current status and validation of the SIMMER-III LMFR safety analysis code

; ; Kamiyama, Kenji; Yamano, Hidemasa; Fujita, Satoshi

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7), 0 Pages, 1999/00

None

Journal Articles

Evaluation of CDA energetics in the prototype LMFBR with lastest knowledge and tools

; ; ;

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7), 0 Pages, 1999/00

None

Journal Articles

MOX fuel behavior under reactivity accident conditions

Sasajima, Hideo; Fuketa, Toyoshi; Ishijima, Kiyomi; Kikuchi, Keiichi*; Abe, Tomoyuki*

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00

no abstracts in English

Journal Articles

Mechanical energy generation during high burnup fuel failure under reactivity initiated accident conditions

; Fuketa, Toyoshi; Ishijima, Kiyomi

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00

no abstracts in English

Journal Articles

Empirical modeling of pressure rise and power characteristics of helium circulators for the High Temperature engineering Test Reactor

Takeda, Takeshi; Nakagawa, Shigeaki; Kunitomi, Kazuhiko

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00

no abstracts in English

Journal Articles

Sensitivity analysis of failure probability on PTS benchmark problems of pressure vessel using a probabilistic fracture mechanics analysis code

Y.Li*; Kato, Daisuke*; Shibata, Katsuyuki

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00

no abstracts in English

Journal Articles

A Feasibility study on core cooling of pressurized heavy water moderated reactor with tight lattice core

Onuki, Akira; Okubo, Tsutomu; Akimoto, Hajime

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00

no abstracts in English

Journal Articles

Creep analysis of piping with elevated internal pressure and temperature

Maeda, Akio; Maruyama, Yu; Hashimoto, Kazuichiro; Harada, Yuhei; Shibazaki, Hiroaki*; Kudo, Tamotsu; Hidaka, Akihide; Sugimoto, Jun; Nakamura, Naohiko*

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00

no abstracts in English

32 (Records 1-20 displayed on this page)