Natural Circulation Cooling in a Pressurized Water Reactor Geometry under Accident-Induced Conditions-Reference-Cited by-同舟云学术

Natural Circulation Cooling in a Pressurized Water Reactor Geometry under Accident-Induced Conditions

Published:1984-11 Issue:3 Volume:88 Page:311-320
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Shimeck D. J.¹,Johnsen G. W.¹

Affiliation:

1. EG&G Idaho, Inc., Water Reactor Research Test Facility P.O. Box 1625, Idaho Falls, Idaho 83415

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE84-A18585

Reference8 articles.

1. G. G. LOOMIS, K. SODA, and C. P. FINEMAN, “Quick Look Report for Semiscale Mod-2A Test S-NC-2,” EGG-SEMI-5448, EG&G Idaho, Inc. (July 1981).

2. G. G. LOOMIS and K. SODA, “Quick Look Report for Semiscale Mod-2A Test S-NC-3,” EGG-SEMI-5522, EG&G Idaho, Inc. (Aug. 1981).

3. K. SODA and G. G. LOOMIS, “Quick Look Report for Semiscale Mod-2A Tests S-NC-5 and S-NC-6,” EGG-SEMI-5591, EG&G Idaho, Inc. (Sep. 1981).

4. K. SODA and D. J. SHIMECK, “Quick Look Report for Semiscale Mod-2A Test S-NC-4,” EGG-SEMI-5549, EG&G Idaho, Inc. (Aug. 1981).

5. D. J. SHIMECK, G. G. LOOMIS, and C. M. KULLBERG, “Quick Look Report for Semiscale Mod-2A Test S-NC-7,” EGG-SEMI-5639, EG&G Idaho, Inc. (Oct. 1981).

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