A fracture mechanics analysis of the PWR nuclear power plant reactor pressure vessel beltline weld

被引：2
|
作者：
Young, LJ [1 ]
机构：
[1] Chung Hua Univ, Dept Appl Math, Hsinchu 30067, Taiwan
来源：
JOURNAL OF NUCLEAR MATERIALS | 2001年 / 288卷 / 2-3期
关键词：
Fracture mechanics - Nuclear power plants - Pressurized water reactors - Welds;
D O I：
10.1016/S0022-3115(00)00710-8
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
In this paper, a generic pressured water reactor (PWR) power plant reactor vessel is analyzed. The primary purpose of this work is to assure structural integrity of the irradiated reactor pressure vessel (RPV) beltline weld under normal operating conditions at the end-of-life, as specified by the requirements of 10CFR50, App.G. It is found that suitable margins of safety are maintained at the end-of-life (32 effective full power years or 1.25 x 10(23) n/m(2) inner wall fluence). (C) 2001 Elsevier Science B.V. All rights reserved.
引用
收藏
页码：197 / 201
页数：5
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