Development of Natural Circulation Analytical Model in Super-COPD Code and Evaluation of Core Cooling Capability in Monju During a Station Blackout-Reference-Cited by-同舟云学术

Development of Natural Circulation Analytical Model in Super-COPD Code and Evaluation of Core Cooling Capability in Monju During a Station Blackout

Published:2014-12 Issue:3 Volume:188 Page:292-321
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Yamada Fumiaki¹,Fukano Yoshitaka¹,Nishi Hiroshi¹,Konomura Mamoru¹

Affiliation:

1. Japan Atomic Energy Agency, Plant Safety Evaluation Group Analysis and Evaluation Department, FBR Safety Technology Center, Tsuruga Head Office Shiraki Tsuruga-shi Fukui-ken, 919-1279, Japan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT13-56

Reference18 articles.

1. S. Nakai et al. “Development of Module Integrated Plant Dynamics Analysis Code: Development of Super-COPD Code”, Technical Review 68-3, Power Reactor and Nuclear Fuel Development Corporation (1988) (in Japanese).

2. “Fast Reactor Database 2006 Update”, IAEA-TECDOC-1531, International Atomic Energy Agency (Dec. 2006).

3. “External Evaluation on the Logical Adequacy of the Safety Measures and Coolability of the Reactor Core and Others in Monju Considering Earthquake and Tsunami”, JAEA-Evaluation 2011-004, p. 55, Japan Atomic Energy Agency, FBR Plant Engineering Center (2011) (in Japanese).

4. M. Tanji et al. “Development and Verification of a Thermo-Hydraulic Simulation Code for System Transient in Monju (COPD Code)”, Technical Review Vol. 23, No. 6, Mitsubishi Heavy Industries, Ltd. (1986) (in Japanese).

5. F. Yamada and M. Minami, “Development of the Monju Core Safety Analysis Numerical Models by Super-COPD Code”, JAEA-Data/Code 2010-023, Japan Atomic Energy Agency (Dec. 2010).

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