Deterministic and probabilistic analysis of a reactor pressure vessel subjected to pressurized thermal shocks-Reference-Cited by-同舟云学术

Deterministic and probabilistic analysis of a reactor pressure vessel subjected to pressurized thermal shocks

Published:2014-07 Issue: Volume:273 Page:381-395
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Qian Guian,Niffenegger Markus

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

Reference34 articles.

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3. Use of fracture toughness test data to establish reference temperature for pressure retaining materials other than bolting for class 1 vessels, section III, division 1;ASME,1999

4. ASME Boiler and Pressure Vessel Code, Section III, Nuclear Power Plant Components;ASME,1995

5. Stress intensity factor solution for continuous surface flaws in reactor pressure vessels. Mechanics of crack growth;Buchalet;ASTM Spec. Tech. Publ.,1976

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