The SCC testing of nuclear steam generator tubing materials

被引：1

作者：

Doherty, PE ^{[1
]}

Sarver, JM ^{[1
]}

Miglin, BP ^{[1
]}

机构：

[1] BABCOCK & WILCOX RES & DEV DIV,CORROS SECT,ALLIANCE,OH 44601

来源：

JOM-JOURNAL OF THE MINERALS METALS & MATERIALS SOCIETY | 1996年 / 48卷 / 05期

关键词：

D O I：

10.1007/BF03222941

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The integrity of heat-exchanger tubes in a nuclear reaction system is crucial for the safe operation of a power plant. In order to study the corrosion behavior of certain alloys, constant extension rate (CERT) tests were performed on alloy 690 and alloy 800 nuclear steam generator tubing specimens. In this article, the CERT test results (such as maximum stress achieved and crack morphology) are correlated to tubing microstructure, chemistry, and manufacturing processes.

引用

页码：39 / 41

页数：3

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