Comprehensive Safety Analysis Code System for Nuclear Fusion Reactors II: Thermal Analyses During Plasma Disruptions for International Thermonuclear Experimental Reactor-Reference-Cited by-同舟云学术

Comprehensive Safety Analysis Code System for Nuclear Fusion Reactors II: Thermal Analyses During Plasma Disruptions for International Thermonuclear Experimental Reactor

Published:1994-12 Issue:4 Volume:26 Page:1288-1295
ISSN:0748-1896
Container-title:Fusion Technology
language:en
Short-container-title:Fusion Technology

Author:

Honda T.¹,Maki K.¹,Okazaki T.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/FST94-A30313

Reference13 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 Programme,” 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. D. E. POST et al. “ITER Physics,” ITER Documentation Series, No. 21, International Atomic Energy Agency (1991).

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1. Safety analyses for transient behavior of plasma and in-vessel components during plasma abnormal events in fusion reactor;J NUCL SCI TECHNOL;1997

2. 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

3. Development of time dependent safety analysis code for plasma anomaly events in fusion reactors;J NUCL SCI TECHNOL;1997

4. Development of Time Dependent Safety Analysis Code for Plasma Anomaly Events in Fusion Reactors;Journal of Nuclear Science and Technology;1997-03

5. Development of safety assessment method for plasma anomaly events in fusion reactors;Journal of Fusion Energy;1997