The EPRI embrittlement management program
Autor: | T.J. Griesbach, W.L. Server |
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Rok vydání: | 1990 |
Předmět: |
Nuclear and High Energy Physics
Engineering business.industry Mechanical Engineering Nuclear engineering Boiler (power generation) Pressure vessel law.invention Nuclear Energy and Engineering law Code of Federal Regulations Nuclear power plant Forensic engineering General Materials Science Safety Risk Reliability and Quality Neutron irradiation business Waste Management and Disposal Reactor pressure vessel Embrittlement Brittle fracture |
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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