The EPRI embrittlement management program

Autor: T.J. Griesbach, W.L. Server
Rok vydání: 1990
Předmět:
Zdroj: Nuclear Engineering and Design. 124:153-156
ISSN: 0029-5493
DOI: 10.1016/0029-5493(90)90361-z
Popis: 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 results of the EPRI Embrittlement Management Program will provide guidelines for safe, continued operation of reactor pressure vessels well into the future.
Databáze: OpenAIRE
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