A review of the ASME low upper shelf toughness evaluation procedures for nuclear reactor pressure vessels
Autor: | E. Smith, T.J. Griesbach |
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Rok vydání: | 1991 |
Předmět: |
Nuclear and High Energy Physics
Engineering Toughness business.industry Mechanical Engineering Nuclear engineering Pressurized water reactor Fracture mechanics Context (language use) Structural engineering Nuclear reactor Pressure vessel law.invention Fracture toughness Nuclear Energy and Engineering law General Materials Science Safety Risk Reliability and Quality business Waste Management and Disposal Reactor pressure vessel |
Zdroj: | Nuclear Engineering and Design. 130:259-266 |
ISSN: | 0029-5493 |
DOI: | 10.1016/0029-5493(91)90218-7 |
Popis: | The ASME Section X1 Working Group on Flaw Evaluation has proposed criteria for the evaluation of reactor pressure vessel beltline materials which have an upper shelf energy less than 50 ft-lbs (69 J). These criteria have been assessed and applied to Linde 80 weld materials in recent investigations; this assessment and evaluation are described in the paper. A key element in the evaluation procedure is the JR curve for the relevant material. Recent experimental studies have demonstrated that the JR curve is size dependent for some materials, in the sense that the JR curve slope decreases with increasing specimen thickness. This paper assesses this experimental work and discusses it in the context of the integrity of nuclear reactor pressure vessels. |
Databáze: | OpenAIRE |
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