EPRI activities to address reactor pressure vessel integrity issues

被引：0
|
作者：
Rosinski, ST [1 ]
Carter, RG [1 ]
机构：
[1] Elect Power Res Inst, Charlotte, NC 28262 USA
来源：
NUCLEAR ENGINEERING AND DESIGN | 1999年 / 194卷 / 2-3期
关键词：
D O I：
10.1016/S0029-5493(99)00205-8
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
The demonstration of reactor pressure vessel (RPV) structural integrity is an essential element in ensuring the continued safe and reliable operation of US nuclear power plants. The Electric Power Research Institute (EPRI), through its domestic and. international member utilities, continues to pursue an aggressive research program to develop technologies and capabilities that will address issues associated with reactor pressure vessel integrity. Ongoing research in the EPRI Nuclear Power Group Materials Performance Program covers a broad range of technical areas associated with RPVs. The program is structured under the following product groups; (1) Management and Mitigation; (2) Material Performance Databases; (3) Material Condition Assessment; and (4) Operability Assessment. Specific activities under each of theses product groups are described in this paper. (C) 1999 Elsevier Science S.A. All rights reserved.
引用
收藏
页码：199 / 204
页数：6
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