Effect of material hardening model for canister on finite element cask drop simulation for strain-based acceptance evaluation-Reference-Cited by-同舟云学术

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Effect of material hardening model for canister on finite element cask drop simulation for strain-based acceptance evaluation

Published:2021-09 Issue: Volume: Page:
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Kim Hune-Tae^ORCID,Seo Jun-Min^ORCID,Seo Ki-Wan^ORCID,Yoon Seong-Ho,Kim Yun-Jae,Oh Chang-Young

Funder

Ministry of Science and ICT, South Korea

National Research Foundation of Korea

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference27 articles.

1. Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities,2020

2. Load Combinations for the Structural Analysis of Shipping Casks for Radioactive Material,1989

3. ASME B&PV Code, Sec. III, Appendices, Nonmandatory Appendix F, Rules for Evaluation of Service Loadings with Level D Service Limits,2019

4. ASME B&PV Code, Sec. III, Appendices, Nonmandatory Appendix FF, Strain-Based Acceptance Criteria for Energy-Limited Events,2019

5. Strain-based acceptance criteria for energy-limited events;Snow,2009

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Fracture mechanics analysis of multipurpose canister for spent nuclear fuels under horizontal/oblique drop accidents;Nuclear Engineering and Technology;2023-12

2. Effect of material properties of impact limiter steel on drop accident of spent nuclear fuel transport cask;Journal of Mechanical Science and Technology;2022-10-26

3. Sensitivity of SNF transport cask response to uncertainty in properties of wood inside the impact limiter under drop accident conditions;Nuclear Engineering and Technology;2022-10

4. Effect of strain rate and stress triaxiality on fracture strain of 304 stainless steels for canister impact simulation;Nuclear Engineering and Technology;2022-07

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