Accident Progression for a Loss-of-Heat-Sink with Scram in a Liquid-Metal Fast Breeder Reactor-Reference-Cited by-同舟云学术

Accident Progression for a Loss-of-Heat-Sink with Scram in a Liquid-Metal Fast Breeder Reactor

Published:1979-08 Issue:3 Volume:44 Page:357-380
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Bari R. A.¹,Ludewig H.¹,Pratt W. T.¹,Sun Y. H.¹

Affiliation:

1. Brookhaven National Laboratory Department of Nuclear Energy Upton, New York 11973

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/NT79-A32272

Reference32 articles.

1. “Final Environmental Statement Related to the Construction and Operation of the Clinch River Breeder Reactor Plant,” NURKG-0139, U.S. Nuclear Regulatory Commission (Feb. 1977).

2. J. F. MEYER, L. LOIS, J. L. CARTER, and T. P. SPEIS, “An Analysis and Evaluation of the Clinch River Breeder Reactor Core Disruptive Accident Energetics,” NUREG-0122, U.S. Nuclear Regulatory Commission (Mar. 1977).

3. “Reliability of the CRBRP Shutdown Heat Removal System,” NEDM-14082, General Electric Corporation (Jan. 1976).

4. A. J. BUSLIK, I. A. PAPAZOGLOU, and R. A. BARI, “Reliability of the Shutdown Heat Removal System of the CRBR,” BNL-NUREG-21962, Brookhaven National Laboratory (Oct. 1976).

5. IAEA Specialists’ Mtg. Reliability of Decay Heat Removal Systems for Fast Reactors, Harwell, England (Summary Report) (Apr. 1975).

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