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

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

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

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

APPLICATIONS OF THE SIMMER-III FAST REACTOR SAFETY ANALYSIS CODE TO THERMAL INTERACTIONS OF MELTS WITH SODIUM AND WATER

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

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

None

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

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

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

Critical heat flux of subcooled flow boiling in narrow rectangular channels

Kureta, Masatoshi; Akimoto, Hajime

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 8 Pages, 1999/00

no abstracts in English

Study on tritium/hydrogen permeation in the HTTR hydrogen production system

Takeda, Tetsuaki; Iwatsuki, Jin*; Inagaki, Yoshiyuki; Ogawa, Masuro

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

no abstracts in English