THE EPRI EMBRITTLEMENT MANAGEMENT PROGRAM

被引:0
|
作者
GRIESBACH, TJ [1 ]
SERVER, WL [1 ]
机构
[1] TENERA,BERKELEY,CA
关键词
D O I
10.1016/0029-5493(90)90361-Z
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
One of the main concerns in nuclear power plant operation is protecting the reactor pressure vessel against unstable, brittle fracture. The ASME Boiler and Pressure Vessel Code and the Code of Federal Regulations prescribe plant operating pressure-temperature and radiation embrittlement limits which include safety margins for normal and accident conditions. These limits must be updated periodically using a surveillance testing program to reflect the condition of the steel vessel wall after many years of neutron irradiation. In some older plants, these limits may impose significant operational restrictions. The result of the EPRI Embrittlement Management Program will provide guidelines for safe, continued operation of reactor pressure vessels well into the future.
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页码:153 / 156
页数:4
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