Objectif
The proposal addresses the ageing of primary pressure boundary components of nuclear power plants by environmentally assisted cracking. In particular, it deals with the crack growth behaviour of low alloy steels for reactor pressure vessels (eastern and western type) in light water reactor environment under static and cyclic load. Besides different crack geometries and specimen sizes transient conditions as postulated for plant operation will be considered during the test by varying water chemistry and mechanical load. The initiation of environmentally assisted cracking in pre-fatigued specimens will be forced by cyclic loading in the test environment. The results will lead to recommendations for service operation and for Code implementations. They will broaden the database for the lifetime assessment of nuclear power plants.
Champ scientifique
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CSC - Cost-sharing contractsCoordinateur
70569 STUTTGART
Allemagne