International Round-Robin on Stress Corrosion Crack Initiation of Alloy 600 Material in Pressurized Water Reactor Primary Water

被引:3
作者
Meadows, P. J. [1 ]
Andresen, P. L. [2 ]
Toloczko, M. B. [3 ]
Kuang, W-J [4 ]
Ritter, S. [5 ]
Bjurman, M. [6 ]
Zhang, L. [7 ]
Ernestova, M. [8 ]
Toivonen, A. [9 ]
Perosanz-Lopez, F. [10 ]
Stairmand, J. W. [1 ]
Mottershead, K. J. [1 ]
机构
[1] Jacobs, Walton House,Faraday St,Birchwood Pk, Warrington WA3 6GA, Cheshire, England
[2] Gen Elect Global Res Ctr, Schenectady, NY 12309 USA
[3] Pacific Northwest Natl Lab, Richland, WA 99354 USA
[4] Univ Michigan, Ann Arbor, MI 48109 USA
[5] Paul Scherrer Inst, CH-5232 Villigen, Switzerland
[6] Studsvik Nucl AB, S-61060 Nykoping, Sweden
[7] Shanghai Jiao Tong Univ, Shanghai 200240, Peoples R China
[8] UJV Rez As, Rez 25068, Czech Republic
[9] VTT Tech Res Ctr Finland Ltd, Espoo 02044, Finland
[10] CIEMAT, Madrid 28040, Spain
基金
中国国家自然科学基金;
关键词
alloy; nickel; stress corrosion;
D O I
10.5006/3532
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The International Cooperative Group on Environmentally Assisted Cracking of Water Reactor Materials coordinated an international "Round-Robin" collaboration of 10 laboratories on stress corrosion crack (SCC) initiation in three heats of cold-worked Alloy 600 in high-temperature water. The various laboratories were able to produce good quality experimental crack initiation data, and the Round-Robin exercise highlighted the benefits in generating a significant body of data when assessing the susceptibility of a material to SCC. The compilation of data from multiple laboratories using common test techniques greatly assists the understanding of the material variability and gives confidence in the reliability of the results.
引用
收藏
页码:719 / 733
页数:15
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