Severity, causes and frequencies of pressure vessel thermal shock at U.S. pressurized water reactors (1963

Severity, causes and frequencies of pressure vessel thermal shock at U.S. pressurized water reactors (1963–1981)

Published:1983-06 Issue:3 Volume:75 Page:375-388
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Phung Doan L.,Cottrell William B.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference8 articles.

1. Pressure Vessel Thermal Shock at U.S. Pressurized Water Reactors: Events and Precursors, 1963–1981;Phung,1983

2. Oconee Nuclear Reactor Vessel Pressurized Thermal Shock Evaluation;Duke Power Company;DPC-RS-1001,1982

3. Summary of evaluation related to reactor vessel integrity performed for the Westinghouse Owners Group;Westinghouse Electric Corporation, Nuclear Technology Division;Report 20 72Q:1,1982

4. NRC Internal Memorandum by F.B. Litton,1982

5. Review of Licensee Event Reports (1976–1977);USNRC Advisory Committee on Reactor Safeguards;NUREG-0572,1979

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1. Thermal shock fracture experiments on large size plates of A533-B steel;International Journal of Pressure Vessels and Piping;1991-01

2. Trends in the evaluation of the structural integrity of RPVs;Nuclear Engineering and Design;1989-09

3. Results of probabilistic fracture mechanics analyses for pressurized thermal shock transients in the reactor pressure vessel of BIBLIS-B;Nuclear Engineering and Design;1986-10

4. Prediction of pressure vessel failure: A critical review of the probabilistic approach;Theoretical and Applied Fracture Mechanics;1986-02