Analysis of an Advanced Test Reactor Small-Break Loss-of-Coolant Accident with an Engineered Safety Feature to Automatically Trip the Primary Coolant Pumps-Reference-Cited by-同舟云学术

Analysis of an Advanced Test Reactor Small-Break Loss-of-Coolant Accident with an Engineered Safety Feature to Automatically Trip the Primary Coolant Pumps

Published:2000-10 Issue:1 Volume:132 Page:167-178
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Polkinghorne Steven T.¹,Davis Cliff B.¹,McCracken Richard T.¹

Affiliation:

1. Idaho National Engineering and Environmental Laboratory Bechtel BWXT Idaho, LLC, P.O. Box 1625, Idaho Falls, Idaho 83415

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/NT00-A3136

Reference9 articles.

1. “Advanced Test Reactor Upgraded Final Safety Analysis Report,” Rev. 1999, AU, Bechtel BWXT Idaho (July 1999).

2. “SCDAP/RELAP5/MOD2 Code Manual, Vols. 1, 2, and 3,” NUREG/CR-5273, EGG-2555, C. M. ALLISON and E. C. JOHNSON, Eds. EG&G Idaho (Sep. 1989).

3. J. D. GASKI, “SINDA 1987/ANSI Computer Code,” Network Analysis Associates (Oct. 1987).

4. Pump Cavitation in Savannah River Reactors During Loss-of-Coolant Accidents

5. V. H. RANSOM, R. J. WAGNER, and G. W. JOHNSEN, “RELAP5/MOD2 Code Manual, Vol. 3: Developmental Assessment Problems,” EGG-TFM-7952, EG&G Idaho (Dec. 1987).

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