Stress-based vs. Strain-based safety evaluations of spent nuclear fuel transport casks in energy-limited events

Author:

Kim Seung-Pil,Kim Jeongho,Sohn Dongseong,Kwon Hyukjoo,Shin Myoungsu

Funder

Korea Institute of Energy Technology Evaluation and Planning

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference25 articles.

1. ASME BPVC Section III – Rules for Construction of Nuclear Facility Components – Division 1. In Subsection NB: Class 1 Components;American Society of Mechanical Engineers,2010

2. ASME BPVC Section III – Rules for Construction of Nuclear Facility Components – Appendices;American Society of Mechanical Engineers,2015

3. RG 1.59. In Regulatory Guide 1.59, Revision 2, Design Basis Floods for Nuclear Power Plants;US Nuclear Regulatory Commission,1977

4. NUREG-1536 In Standard review plan for dry cask storage systems;US Nuclear Regulatory Commission,1997

5. Analyzing public preference and willingness to pay for spent nuclear fuel facilities in South Korea: A latent class approach;Woo;Prog. Nucl. Energy,2017

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