Comprehensive Safety Analysis Code System for Nuclear Fusion Reactors III: Ex-Vessel LOCA Analyses Considering Passive Safety-Reference-Cited by-同舟云学术

Comprehensive Safety Analysis Code System for Nuclear Fusion Reactors III: Ex-Vessel LOCA Analyses Considering Passive Safety

Published:1996-01 Issue:1 Volume:29 Page:116-125
ISSN:0748-1896
Container-title:Fusion Technology
language:en
Short-container-title:Fusion Technology

Author:

Honda T.¹,Okazaki T.¹,Maki K.¹,Uda T.¹,Seki Y.²,Aoki I.²,Kunugi T.³

Affiliation:

1. Hitachi Ltd., Energy Research Laboratory, 2-1, Omika-cho 7-chome Hitachi-shi, Ibaraki-ken, 319-12 Japan

2. Japan Atomic Energy Research Institute Naka Fusion Research Establishment, Naka-machi, Naka-gun Ibaraki-ken 311-01, Japan

3. Japan Atomic Energy Research Institute Tokai Research Establishment, Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan

Publisher

Informa UK Limited

Subject

General Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/FST96-A30661

Reference19 articles.

1. “ITER Conceptual Design Report,” ITER Documentation Series, No. 18, International Atomic Energy Agency (1991).

2. G. W. Pacher et al. “ITER, Operations and Research Program,” ITER Documentation Series, No. 23, International Atomic Energy Agency (1991).

3. J. Raeder et al. “ITER, Safety,” ITER Documentation Series, No. 36, International Atomic Energy Agency (1991).

4. Y. Seki et al. “Conceptual Design of Fusion Experimental Reactor–Safety Analysis and Evaluation,” JAERI-M, 91-126, Japan Atomic Energy Research Institute (1991) (in Japanese).

5. Analysis of loss-of-coolant and loss-of-flow accidents in the divertor cooling system of NET/ITER

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3. Safety Analyses for Transient Behavior of Plasma and In-vessel Components during Plasma Abnormal Events in Fusion Reactor;Journal of Nuclear Science and Technology;1997-07

4. Analyses of passive plasma shutdown during ex-vessel loss of coolant accident in the first wall/shield blanket of fusion reactor;J NUCL SCI TECHNOL;1997

5. Analyses of Passive Plasma Shutdown during Ex-vessel Loss of Coolant Accident in the First Wall/Shield Blanket of Fusion Reactor;Journal of Nuclear Science and Technology;1997-06