Evaluating the safety of aging nuclear reactor pressure vessels

被引：0

作者：

Pennell, WE ^{[1
]}

机构：

[1] OAK RIDGE NATL LAB,DIV ENGN TECHNOL,OAK RIDGE,TN

来源：

PROCEEDINGS OF THE AMERICAN POWER CONFERENCE, VOL 58, PTS I AND II | 1996年 / 58卷

关键词：

D O I：

暂无

中图分类号：

TE [石油、天然气工业]; TK [能源与动力工程];

学科分类号：

0807 ; 0820 ;

摘要：

引用

页码：141 / 146

页数：6

共 50 条

[21] TRENDS IN DESIGN OF PRESSURE VESSELS FOR NUCLEAR POWER STATIONS - SAFETY CONCEPT FOR A BOILING WATER REACTOR WITH PRESTRESSED CONCRETE PRESSURE VESSEL
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SCHAFSTA.HG
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[22] Effects of thermal aging on microstructure and hardness of stainless steel weld-overlay claddings of nuclear reactor pressure vessels
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[28] SUMMARY AND CONCLUSIONS OF THE WORKSHOP ON THE SAFETY ASSESSMENT OF REACTOR PRESSURE-VESSELS
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