Probabilistic fracture mechanics applied for DHC assessment in the cool-down transients for CANDU pressure tubes-Reference-Cited by-同舟云学术

Probabilistic fracture mechanics applied for DHC assessment in the cool-down transients for CANDU pressure tubes

Published:2012-12 Issue: Volume:253 Page:211-218
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Radu Vasile,Roth Maria

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

Reference12 articles.

1. ASME Boiler & Pressure Vessel Code XI, Rules for In-service Inspection of Nuclear Power Plant Components;ASME,2004

2. CAN/CSA N285.8, Technical requirements for in-service evaluation of zirconium alloy pressure tubes in CANDU reactors, 2005.

3. Hydrogen uptake and corrosion behavior of Zr–2.5%Nb pressure tubes in Wolsong Unit 1;Choo;J. Nucl. Mater.,2001

4. Structural Reliability Methods, Monograph;Ditlevsen,2007

5. Quest Reliability;FEACrack Version 2.7,2012

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