ASAKA Hideaki | Japan Atomic Energy Research Institute
スポンサーリンク
概要
関連著者
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ASAKA Hideaki
Japan Atomic Energy Research Institute
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Kukita Yutaka
Japan Atomic Energy Research Institute
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Asaka H
Japan Atomic Energy Research Institute
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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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ANODA Yoshinari
Japan Atomic Energy Research Institute
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Kukita Yutaka
Nagoya University
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YONOMOTO Taisuke
Japan Atomic Energy Agency
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KUMAMARU Hiroshige
Japan Atomic Energy Research Institute
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Ohtsu Iwao
Japan Atomic Energy Research Institute
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NAKAMURA Hideo
Japan Atomic Energy Agency
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Kukita Yutaka
Department Of Nuclear Safety Research Japan Atomic Energy Research Institute
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Kumamaru H
Graduate School Of Engineering University Of Hyogo
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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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Schultz Richard
Idaho National Engineering & Environmental Laboratory
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Schultz Richard
Idaho National Engineering Laboratory
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Kukita Y
Nagoya University
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Kumamaru H
Univ. Hyogo Hyogo
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Boucher Timothy
Idaho National Engineering Laboratory
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ORTIZ Marcos
Idaho National Engineering Laboratory
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SHAW Roy
Idaho National Engineering Laboratory
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YONOMOTO Taisuke
Nuclear Safety Research Center, Japan Atomic Energy Agency
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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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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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TASAKA Kanji
Japan Atomic Energy Research Institute
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KOIZUMI Yasuo
Japan Atomic Energy Research Institute
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OSAKABE Masahiro
Japan Atomic Energy Research Institute
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MIMURA Yuichi
I. S. L. Inc.
著作論文
- ROSA/AP600 Testing : Facility Modifications and Initial Test Results
- Secondary-Side Depressurization during PWR Cold-Leg Small Break LOCAs Based on ROSA-V/LSTF Experiments and Analyses
- Core Liquid Level Responses Due to Secondary-Side Depressurization during PWR Small Break LOCA
- Intentional Depressurization of Steam Generator Secondary Side during a PWR Small-Break Loss-Coolant Accident
- Sub- to Supercritical Flow Transition in a Horizontally-Stratified Two-Phase Flow in PWR Hot Legs
- Analysis of System Thermal Hydraulic Responses for Passive Safety Injection Experiment at ROSA-IV/Large Scale Test Facility. Using JAERI Modified Version of RELAP5/MOD2 Code.:Using JAERI Modified Version of RELAP5/MOD2 Code
- Investigation of break orientation effect during cold leg small-break LOCA at ROSA-IV LSTF.