Development of Time Dependent Safety Analysis Code for Plasma Anomaly Events in Fusion Reactors
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概要
- 論文の詳細を見る
- Atomic Energy Society of Japanの論文
- 1997-03-25
著者
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Bartels H-w
Iter Joint Central Team San Diego
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Okazaki Takashi
Power & Industrial Systems R&d Division Hitachi Ltd.
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SEKI Yasushi
Naka Fusion Research Establishment, Japan Atomic Energy Research Institute
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HONDA Takuro
Hitachi Research Laboratory, Hitachi Ltd.
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UCKAN N.
Oak Ridge National Laboratory
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OKAZAKI Takashi
Hitachi Research Laboratory, Hitachi Ltd.
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Seki Yasushi
Nuclear Technology And Education Center Tokai Research Establishment Japan Atomic Energy Research In
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Honda Takuro
Power & Industrial Systems R&d Division Hitachi Ltd.
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Uckan N.A.
Oak Ridge National Laboratory
関連論文
- Transient Behaviors of Plasma and In-vessel Components when Considering Divertor Plasma State Transition in a Fusion Reactor
- Safety Analyses for Transient Behavior of Plasma and In-vessel Components during Plasma Abnormal Events in Fusion Reactor
- Analyses of Passive Plasma Shutdown during Ex-vessel Loss of Coolant Accident in the First Wall/Shield Blanket of Fusion Reactor
- Development of Time Dependent Safety Analysis Code for Plasma Anomaly Events in Fusion Reactors
- Analyses for Passive Safety of Fusion Reactor during Ex-Vessel Loss of Coolant Accident
- Numerical Analysis on Ingress of Coolant Event in Vacuum Vessel of Fusion Reactor Using Modified TRAC-BF1
- Development of Dust Removal System Using static Electricity for Fusion Experimental Reactors