Assessment of primary water stress corrosion cracking of PWR steam generator tubes-Reference-Cited by-同舟云学术

Assessment of primary water stress corrosion cracking of PWR steam generator tubes

Published:1992-05 Issue:2-3 Volume:134 Page:199-215
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Shah V.N.,Lowenstein D.B.,Turner A.P.L.,Ward S.R.,Gorman J.A.,MacDonald P.E.,Weidenhamer G.H.

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

Reference36 articles.

1. Residual Life Assessment of Major LWR Components Overview,1987

2. PWR Steam Generator Tubes (Draft);Lowenstein;Nureg/Cr-5314, EGG-2562,1992

3. Steam generator tube performance: Experience with water-cooled nuclear power reactors during 1982;Tatone;Nuclear Safety,1985

4. Status and Suggested Course of Action for Nondenting-Related Primary-Side IGSCC of Westinghouse-Type Steam Generators;Hunt;Epri Np-4594-LD,1986

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