A multibarrier safety concept for the reactor pressure vessel of the Stade Nuclear Power Plant
| Autor: | G. Nagel, W. Schmitt, J.G Blauel |
|---|---|
| Rok vydání: | 1993 |
| Předmět: |
Nuclear and High Energy Physics
Leak Core cooling Materials science business.industry Mechanical Engineering Nuclear engineering Welding Structural engineering law.invention Nuclear Energy and Engineering law Nuclear power plant Crack size General Materials Science Safety Risk Reliability and Quality Wall thickness business Waste Management and Disposal Reactor pressure vessel Brittle fracture |
| Zdroj: | Nuclear Engineering and Design. 144:45-52 |
| ISSN: | 0029-5493 |
| DOI: | 10.1016/0029-5493(93)90007-v |
| Popis: | Two specific problems within the safety case of Stade RPV have been analysed: brittle fracture initiation and arrest under strip type emergency core cooling conditions and safety margins against ductile failure from deep cracks as postulated by ASME- and German KTA-rules. For EOL material conditions exclusion of initiation is shown for cracks of more than twice the size which is safely detectable by NDE; for arbitrarily postulated large cracks it is demonstrated that they are arrested well within the allowed depth of 34 of the wall thickness; therefore no critical crack size exists for Stade RPV under strip cooling. Growth in depth of an assumed 34 t circumferential flaw in the girth weld embrittled at EOL could occur only at upper shelf temperatures and by loads higher than about twice the service pressure; leak before break was demonstrated in a constraint-modified J − R-curve crack-growth analysis. But neither a transient nor the plant itself would be able to provide the necessary high loads. The LEFM and EPFM proofs are summarized in a multibarrier safety scheme. |
| Databáze: | OpenAIRE |
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