Failure behavior of SA508 Gr.1a LAS and SA312 TP316 SS pipes with a circumferential through-wall crack under large amplitude cyclic loads

Author:

Kim Jin WeonORCID,Kweon Hyeong Do,Kim Yun Jae

Funder

Ministry of Trade, Industry and Energy

Korea Institute of Energy Technology Evaluation and Planning

Korea Hydro and Nuclear Power

Publisher

Elsevier BV

Subject

Mechanical Engineering,Building and Construction,Civil and Structural Engineering

Reference46 articles.

1. Regulatory Guide for Reviewing Seismic Design of Nuclear Power Reactor Facilities,2006

2. Summary of the historical development of seismic design of nuclear power plants in Japan and the U.S;Stevenson;Nucl. Eng. Des.,2014

3. Seismic Design Standards and Calculational Methods in the United States and Japan,2017

4. Rules for Construction of Nuclear Facility Components,2007

5. USNRC, 2013, SRP 3.7.3 Seismic Subsystem Analysis Review Responsibility,” NUREG–0800, Rev.4.

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