Monitoring of mechanical properties of vessel materials of water-moderated water-cooled reactors of nuclear power plants for assurance of their safe service

被引：0

作者：

Amaev, AD ^{[1
]}

Korolev, YN ^{[1
]}

Krasikov, EA ^{[1
]}

Shtrombakh, YI ^{[1
]}

机构：

[1] Kurchatov Inst, Russian Sci Ctr, Moscow, Russia

来源：

INDUSTRIAL LABORATORY | 2000年 / 66卷 / 07期

关键词：

D O I：

10.1023/A:1004162530861

中图分类号：

TH7 [仪器、仪表];

学科分类号：

0804 ; 080401 ; 081102 ;

摘要：

Methods to monitor the mechanical properties of the material of reactor vessels with a view to ensuring their safe service are presented. Data on the hydrogen and radiation resistance of vessels unclad with stainless steel for protection are discussed. A method using small-size substandard impact-test specimens for determination of the critical brittle point for in-service reactor vessels is substantiated. A scheme for predicting the radiation life of reactor vessels treated by recovery annealing technology to enhance their safe service is proposed.

引用

页码：462 / 470

页数：9

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