Correlation of load drop and crack initiation criteria in fatigue life experiments of metallic materials

Author:

Heckmann Klaus,Sievers Jürgen,Schopf Tim,Lücker Lukas,Schmiedt-Kalenborn Anke,Walther Frank,Starke Peter,Acosta Ruth,Boller Christian

Funder

Bundesministerium fur Wirtschaft und Energie

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference17 articles.

1. Erve M. The role of material science for plant life management for nuclear facilities. In: 23rd MPA Seminar, Stuttgart, Germany (in German); 1997.

2. Hirschberg P, Deardorff AF, Carey J. Operating experience regarding thermal fatigue of unisolable piping connected to PWR reactor coolant systems. In: International Conference on Fatigue of Reactor Components, Napa, USA; 2000.

3. Chopra OK. Mechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments. NUREG/CR-6787, ANL-01/025, Argonne, USA; 2002a.

4. Analysis of events related to cracks and leaks in the reactor coolant pressure boundary;Ballesteros;Nucl Engng Des,2014

5. Nuclear Energy Agency (NEA). Fatigue of Nuclear Reactor Components. In: Proceedings of the 4th International Conference, 28 September - 1 October 2015 Seville, Spain; 2017.

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