Fracture-mechanics-based evaluation of failure limit on pre-cracked and hydrided Zircaloy-4 cladding tube under biaxial stress states
Author:
Affiliation:
1. Nuclear Safety Research Center, Japan Atomic Energy Agency, Ibaraki, Japan
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.1080/00223131.2019.1709996
Reference24 articles.
1. NEA. Nuclear fuel behaviour under reactivity-initiated accident (RIA) conditions. France: Nuclear Energy Agency, OECD; 2010, Report NEA No. 6847. ISBN 978-92-64-99113-2.
2. Stress biaxiality in high-burnup PWR fuel cladding under reactivity-initiated accident conditions
3. Behavior of High-Burnup PWR Fuels with Low-Tin Zircaloy-4 Cladding under Reactivity-Initiated-Accident Conditions
4. Anisotropic behavior and rupture of hydrided ZIRCALOY-4 sheets
Cited by 2 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. A study on the fracture pattern change of high-burnup fuel cladding failed by pellet-cladding mechanical interaction failure under reactivity-initiated accident conditions;Journal of Nuclear Science and Technology;2024-02-15
2. Evaluation of anisotropic elastic and plastic parameters of zircaloy-4 fuel cladding from biaxial stress test data and their application to a fracture mechanics analysis;Journal of Nuclear Science and Technology;2022-04-20
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