TAMAI Hidesada | Japan Atomic Energy Research Institute
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概要
関連著者
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TAMAI Hidesada
Japan Atomic Energy Research Institute
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Tamai Hidesada
Japan Atomic Energy Agency
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Akimoto Hajime
Japan Atomic Energy Agency
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Akimoto H
Japan Atomic Energy Res. Inst. Ibaraki
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Akimoto Hajime
Frontier Research System For Global Change
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KURETA Masatoshi
Japan Atomic Energy Agency
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Ohnuki A
Japan Atomic Energy Agency
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Ohnuki Akira
Japan Atomic Energy Research Institute
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Ohnuki Akira
Japan Atomic Energy Agency
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Liu W
Japan Atomic Energy Agency
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Liu Wei
サウサンプトン大
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Liu Wei
Japan Atomic Energy Agency
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SATO Takashi
Japan Meteorological Agency
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Liu W
九大 大学院工学府
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Sato Takashi
Japan Atomic Energy Agency
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YOSHIDA Hiroyuki
Japan Tobacco Inc. Applied Plant Research Center
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Yoshida Hiroyuki
Japan Atomic Energy Agency Nuclear Science And Engineering Directorate
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Yoshida Hiroyuki
Japan Atomic Energy Research Institute
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Yoshida Hiroyuki
Japan Atomic Energy Agency
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NAKATSUKA Toru
Japan Atomic Energy Agency
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TAKASE Kazuyuki
Japan Atomic Energy Research Institute
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Ose Yasuo
Yamato System Engineer Co. Ltd.
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Takase Kazuyuki
Japan Atomic Energy Agency Nuclear Science And Engineering Directorate
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吉田 啓之
日本原子力研究所
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吉田 啓之
原子力機構
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秋本 肇
原研
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玉井 秀定
日本原子力研究開発機構
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高瀬 和之
原研
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吉田 啓之
原研
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永吉 拓至
原研
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秋本 肇
日本原子力研究開発機構
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永吉 拓至
(株)日立製作所
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吉田 啓之
JAEA
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Shirai Hiroshi
Tepco Systems Corporation
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Ose Yasuo
Yamato System Engineer
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Hotta Akitoshi
TEPCO Systems Corporation
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Yamamoto Kazuhiko
Japan Atomic Power Company
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Okada Hiroyuki
Tokyo Electric Power Company
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玉井 秀定
(独)日本原子力開発機構 東海研究開発センター
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高瀬 和之
(独)日本原子力開発機構 東海研究開発センター
著作論文
- 界面追跡法による単管内気泡流の解析(原子炉伝熱流動解析の革新(1),原子炉伝熱流動解析の革新)
- Effect of Rod Bowing on Critical Power Based on Tight-Lattice 37-Rod Bundle Experiments
- Gap Width Effect on Critical Power based on Tight-Lattice 37-Rod Bundle Experiments
- Pressure Drop Experiments using Tight-Lattice 37-Rod Bundles
- Critical Power Experiment with a Tight-Lattice 37-Rod Bundle
- Critical Power Characteristics in 37-rod Tight Lattice Bundles under Transient Conditions
- Numerical Analysis of a Water-Vapor Two-Phase Film Flow in a Narrow Coolant Channel with a Three-Dimensional Rectangular Rib(International Conferences on Power and Energy System)
- Pressure Drop Characteristics in Tight-Lattice Bundles for Reduced-Moderation Water Reactors(International Conferences on Power and Energy System)
- ICONE11-36232 NUMERICAL ANALYSIS OF A WATER-VAPOR TWO-PHASE FILM FLOW IN A NARROW COOLANT CHANNEL WITH A THREE-DIMENSIONAL RECTANGULAR RIB
- ICONE11-36172 EVALUATION OF CRITICAL HEAT FLUX OF TIGHT LATTICE CORE WITH SUBCHANNEL ANALYSIS CODE NASCA
- ICONE11-36098 PRESSURE DROP CHARACTERISTICS IN TIGHT-LATTICE ROD BUNDLES FOR REDUCED-MODERATION WATER REACTERS