Discussion of fracture surface using beach marks on fatigue test data with large scale piping

Author:

Bodai Masaru,Nomura Yuichiro,Takagoshi Daiki,Asada Seiji,Hayashi Kentaro

Publisher

Elsevier BV

Subject

General Engineering,Energy Engineering and Power Technology

Reference32 articles.

1. JSME S NC1-2016, Codes for Nuclear Power Generation Facilities, Rules on Design and Construction for Nuclear Power Plants, The First Part I:

2. Light Water Reactor Structural Design Standard, The Japan Society of Mechanical Engineers, December 2016. (in Japanese).

3. NUREG/CR-6909, Effect of LWR Coolant Environments on Fatigue Life of Reactor Materials (Final Report), ANL-06/08, U.S. Nuclear Regulatory Commission, February 2006.

4. ASME Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Power Plant Components, American Society of Mechanical Engineers.

5. Asada, S., Zhang, S., Takanashi, M., Nomura, Y., 2019, Study on Incorporation of a New Design Fatigue Curve into the JSME Environmental

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