Author:
Poulain T.,Mendez J.,Hénaff G.,de Baglion L.
Subject
Mechanical Engineering,Mechanics of Materials,General Materials Science
Reference19 articles.
1. Chopra OK, Shack WJ. Effect of LWR coolant environments on the fatigue life of reactor materials. In: NUREG/CR-6909, ANL-06/08, U.S. NRC. Washington: Office of Nuclear Regulatory Research; 2007.
2. Low cycle fatigue behavior of a type 304L austenitic stainless steel in air or in vacuum, at 20 degrees C or at 300 degrees C: relative effect of strain rate and environment;De Baglion;Procedia Eng,2010
3. De Baglion L, Mendez J, Le Duff J-A, Lefrançois A. Influence of PWR primary water on LCF behavior of type 304L austenitic stainless steel at 300°C – comparison with results obtained in vacuum or in air. In: Proceedings of ASME 2012 pressure vessels and piping conference; 2012.
4. Low cycle fatigue behavior in vacuum of a 316L type austenitic stainless steel between 20 and 600 C Part I: Fatigue resistance and cyclic behavior;Alain;Mater Sci Eng A,1997
5. Huin N, Tsutsumi K, Legras L, Couvant T, Loisnard D, Mendez J, et al. Fatigue crack initiation of 304L stainless steel in simulated PWR primary environment: relative effect of strain rate. In: Proceedings of ASME 2012 pressure vessels and piping conference; 2012.
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