Analyses of Passive Plasma Shutdown during Ex-vessel Loss of Coolant Accident in the First Wall/Shield Blanket of Fusion Reactor

• Published in: Journal of nuclear science and technology Vol. 34; no. 6; pp. 538 - 543
• Main Authors: HONDA, Takuro, BARTELS, H-W, UCKAN, N. A., OKAZAKI, Takashi, SEKI, Yasushi
• Format: Journal Article
• Language: English
• Published: Tokyo Taylor & Francis 01.06.1997; Atomic Energy Society of Japan; Taylor & Francis Ltd
• Subjects: Applied sciences; density limit; disruption; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; heat transfer; impurities; Installations for energy generation and conversion: thermal and electrical energy; ITER; loss of coolant; passive plasma shutdown; plasma dynamics; safety analysis; thermal analysis; Nuclear safety; Tokamak; Fusion reactors; Loss of coolant accidents; Passive system; Heat transfer; Plasma dynamics

An ex-vessel loss of coolant accident (LOCA) in the first wall/shield blanket of a fusion reactor has been analyzed by a hybrid code consisting of plasma dynamics and heat transfer analysis of in-vessel components. We investigated possibility of passive plasma shutdown scenario during the accident i...