Rod internal pressure of spent nuclear fuel and its effects on cladding degradation during dry storage-Reference-Cited by-同舟云学术

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Rod internal pressure of spent nuclear fuel and its effects on cladding degradation during dry storage

Published:2017-08 Issue: Volume:492 Page:253-259
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Kim Ju-Seong^ORCID,Hong Jong-Dae,Yang Yong-Sik,Kook Dong-Hak

Funder

Radioactive Waste Management Technology Program of the Korea Institute of Energy Technology Evaluation and Planning (KETEP)

Ministry of Trade, Industry & Energy, Republic of Korea

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference46 articles.

1. Standard Review Plan for Dry Cask Storage Systems, NUREG-1536;U.S. Nuclear Regulatory Commission (NRC),1997

2. US NRC Spent Fuel Project Office, Interim Staff Guidance-11, Revision 1, 2000.

3. US NRC Spent Fuel Project Office, Interim Staff Guidance-11, Revision 2, 2002.

4. US NRC Spent Fuel Project Office, Interim Staff Guidance-11, Revision 3, 2003.

5. Standard Review Plan for Dry Cask Storage Systems, NUREG-1536 Revision 1;U.S. Nuclear Regulatory Commission (NRC),2010

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1. Development of a coupled fuel (GIFT) and thermal (COBRA-SFS) analysis code for dry storage analysis and its application for the spent fuel safety analyses;Nuclear Engineering and Design;2024-11

2. The influence of solid solution hydrogen and precipitated hydride on the creep behavior of Zircaloy-4;Journal of Nuclear Materials;2024-11

3. Numerical study of transient temperature thermal stress coupled heat transfer in spent fuel storage cask based on Gaussian random heat source;Annals of Nuclear Energy;2024-06

4. Machine learning-aided damage identification of mock-up spent nuclear fuel assemblies in a sealed dry storage canister;Engineering Applications of Artificial Intelligence;2024-02

5. The Influence of Hydrogen on the Creep Behavior of Zircaloy-4 Cladding in Low Burnup Regime;2024

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