Influence of strain range on fatigue life reduction of stainless steel in PWR primary water-Reference-Cited by-同舟云学术

Influence of strain range on fatigue life reduction of stainless steel in PWR primary water

Published:2017-06-13 Issue:12 Volume:40 Page:2194-2203
ISSN:8756-758X
Container-title:Fatigue & Fracture of Engineering Materials & Structures
language:en
Short-container-title:Fatigue Fract Engng Mater Struct

Author:

Kamaya Masayuki¹^ORCID

Affiliation:

1. Institute of Nuclear Safety System, Inc.; Fukui 919-1205 Japan

Publisher

Wiley

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Link

http://onlinelibrary.wiley.com/wol1/doi/10.1111/ffe.12650/fullpdf

Reference32 articles.

1. Higuchi M Comparison of environmental fatigue evaluation methods in LWR water 2008

2. Chopra OK Shack WJ Effect of LWR coolant environments on the fatigue life of reactor materials. NUREG/CR-6909, ANL-06/08, USA 2007

3. De Baglion L Mendez J Le Duff JA Lefrancois A Influence of PWR primary water on LCF behavior of type 304L austenitic stainless steel at 300 degrees C: comparison with results obtained in vacuum or in air 2012

4. Japan Society of Mechanical Engineers (JSME) Codes for nuclear power generation facilities: environmental fatigue evaluation method for nuclear power plants 2006

5. ASME Rules for construction of nuclear facility components - ASME Boiler and Pressure Vessel Code Section III, code case N-792: fatigue evaluations including environmental effects 2006

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