JOPSS - Search Results

Search Results: Records 1-8 displayed on this page of 8

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Journal Articles

Simulation of rising bubbles and mesurement of interfacial area

Watanabe, Tadashi; Ebihara, Kenichi

Proceedings of 2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), p.422 - 429, 2000/00

no abstracts in English

Journal Articles

Feasibility study of BWR-type reduced-moderation water reactor core design in thermal-hydraulic view point

Araya, Fumimasa; Kureta, Masatoshi; Akimoto, Hajime

Proceedings of 2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), p.309 - 314, 2000/00

no abstracts in English

Journal Articles

Calculation of thermal-hydraulic behavior of horizontal heat exchanger with parallel tubes

Kondo, Masaya; Otani, Etsuo*; Nakamura, Hideo; Asaka, Hideaki*; Anoda, Yoshinari

Proceedings of 2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), p.344 - 350, 2000/00

no abstracts in English

Journal Articles

Single U-tube Testing and RELAP5 code analysis of PCCS with horizontal heat exchanger

Nakamura, Hideo; Kondo, Masaya; Asaka, Hideaki; Anoda, Yoshinari; Tabata, Hiroaki*; Obata, Hiroyuki*

Proceedings of 2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), p.336 - 343, 2000/00

no abstracts in English

Journal Articles

Behaior of a lighter fluid intrusion into a flowing heavier fluid in simulating reactor horizontal leg

Shibamoto, Yasuteru; Kukita, Yutaka*; Yonomoto, Taisuke; Anoda, Yoshinari

Proceedings of 2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), p.374 - 380, 2000/00

no abstracts in English

Journal Articles

Numerical investigation of multi-dimensional characteristics in sodium combustion

Takata, Takashi; Yamaguchi, Akira

Proceedings of 2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), p.89 - 95, 2000/00

None

Journal Articles

A Computer code SPHINCS for sodium fire safety evaluation

Yamaguchi, Akira

Proceedings of 2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), p.81 - 88, 2000/00

None

Journal Articles

SIMMER-3 Analysis of gas-liquid flows with large liquid densities

Suzuki, Toru; ; ; Yamano, Hidemasa

Proceedings of 2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), p.73 - 80, 2000/00

None