2011

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  • 2011:04 Evaluation of the Technical Basis for New Proposals of Fatigue Design of Nuclear Components

    During the recent years fatigue analysis procedures for nuclear components have been investigated. The most common method so far has been the American code ASME III. The basis for the current design procedures in ASME III is quite old and has now been evaluated against modern data leading to the proposal of modified design curves. Also the effect of the environment has been the subject of...

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