Structural integrity assessment of the reactor pressure vessel under the pressurized thermal shock loading-Reference-Cited by-同舟云学术

Structural integrity assessment of the reactor pressure vessel under the pressurized thermal shock loading

Published:2014-06 Issue: Volume:272 Page:84-91
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Chen Mingya,Lu Feng,Wang Rongshan,Ren Ai

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

Reference20 articles.

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3. ASME Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Facility Components, New York;ASME,2010

4. Validation of the large interface method of NEPTUNE CFD 1.0.8 for pressurized thermal shock (PTS) applications;Coste;Nucl. Eng. Des.,2012

5. Validation of a linear-elastic fracture methodology for postulated flaws embedded in the wall of a nuclear reactor pressure vessel;Dickson,2000

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