The Use of Fatigue Crack Growth Technology in Fracture Control Plans for Nuclear Components
Auteur : WH. Bamford, DP. Jones
Date de publication : 1981
Éditeur : ASTM International
Nombre de pages : 19
Résumé du livre
The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code now suggests the use of fatigue crack growth analysis in the evaluation of indications found during in-service inspection of nuclear components. In this paper the role of crack growth analysis in the evaluation process is reviewed in some detail, and the background and philosophy of its implementation is discussed.