An Assessment of the Core Degradation Frequency in a Typical Large LMFBR Design for Internal Accident Initiators—A Comparison with PWR Predictions-Reference-Cited by-同舟云学术

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An Assessment of the Core Degradation Frequency in a Typical Large LMFBR Design for Internal Accident Initiators—A Comparison with PWR Predictions

Published:1983-12 Issue:3 Volume:63 Page:369-396
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Tzanos Constantine P.¹,Hanan Nelson A.¹,Adamantiades Achilles G.²

Affiliation:

1. Science Applications, Inc., 1211 West 22nd Street, Oak Brook, Illinois 60521

2. Electric Power Research Institute3412 Hillview Avenue, P.O. Box 10412, Palo Alto, California 94303

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/NT83-A33266

Reference48 articles.

1. L. CAVE, “Definition of Safety Criteria for the Clinch River Breeder Reactor,” UCLA-ENG-7692, University of California, Los Angeles, School of Engineering (1976).

2. “Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants,” WASH-1400 (NUREG-75/104), U.S. Nuclear Regulatory Commission (1975).

3. “CRBRP Safety Study: An Assessment of Accident Risks in the CRBRP,” Clinch River Breeder Reactor Plant (1977).

4. “LMFBR Conceptual Design Study, Design Safety Review Report,” CDS 400-7, Westinghouse Electric Corporation Advanced Reactor Division (1981).

5. “Safety Goals for Nuclear Power Plants: A Discussion Paper,” NUREG-0880, U.S. Nuclear Regulatory Commission (1982).

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