SIBAMOTO Yasuteru | Japan Atomic Energy Agency
スポンサーリンク
概要
関連著者
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SIBAMOTO Yasuteru
Japan Atomic Energy Agency
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NAKAMURA Hideo
Japan Atomic Energy Agency
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YONOMOTO Taisuke
Japan Atomic Energy Agency
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MARUYAMA Yu
Japan Atomic Energy Agency
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KUKITA Yutaka
Department of Energy Engineering and Science, Nagoya University
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Kukita Yutaka
Department Of Energy Engineering And Science Nagoya University
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Kukita Y
Department Of Energy Engineering And Science Nagoya University
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SIBAMOTO Yasuteru
Nuclear Safety Research Center, Japan Atomic Energy Agency
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NAKAMURA Hideo
Nuclear Safety Research Center, Japan Atomic Energy Agency
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IGUCHI Tadashi
Japan Atomic Energy Research Institute, Department of Reactor Safety Research
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Iguchi Tadashi
Japan Atomic Energy Research Institute Department Of Reactor Safety Research
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Yonomoto T
Nuclear Safety Research Center Japan Atomic Energy Agency
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Nakamura Hideo
Nuclear Safety Research Center Japan Atomic Energy Agency
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IGUCHI Tadashi
Japan Atomic Energy Research Institute
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KUKITA Yutaka
Department of Energy Engineering & Science, Nagoya University
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Kukita Yutaka
Nagoya University
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YONOMOTO Taisuke
Nuclear Safety Research Center, Japan Atomic Energy Agency
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Asaka Hideo
JAPAN Atomic Energy Research Institute
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Nakamura H
Nuclear Engineering Laboratory Toshiba Corporation
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Nakamura Hideo
Department Of Nuclear Safety Research Japan Atomic Energy Research Institute
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MORIMAYA Kiyofumi
Japan Atomic Energy Agency
著作論文
- Core Heat Transfer Coefficients Immediately Downstream of the Rewetting Front during Anticipated Operational Occurrences for BWRs
- ICONE11-36298 SYSTEM PRESSURE EFFECT ON DENSITTY-WAVE INSTABILITY : SIMPLIFIED MODEL ANALYSIS AND EXPERIMENTS
- Small-scale Experiment on Subcooled Water Jet Injection into Molten Alloy by Using Fluid Temperature-Phase Coupled Measurement and Visualization
- In-pile Experiment in JMTR on the Radiation Induced Surface Activation (RISA) Effect on Flow-boiling Heat Transfer
- ICONE11-36452 EXPERIMENTAL STUDY ON COOLING LIMIT UNDER FLOW INSTABILITY IN BOILING FLOW CHANNEL
- Core Heat Transfer Coefficients Immediately Downstream of the Rewetting Front during Anticipated Operational Occurrences for BWRs
- A simple mass and heat balance model for estimating plant conditions during the Fukushima Dai-ichi NPP accident