Evaluation of fracture resistance of ruptured, oxidized, and quenched Zircaloy cladding by four-point-bend tests
Author:
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
http://www.tandfonline.com/doi/pdf/10.1080/00223131.2014.912968
Reference15 articles.
1. Failure-Bearing Capability of Oxidized Zircaloy-4 Cladding under Simulated Loss-of-Coolant Condition
2. Effect of Pre-Hydriding on Thermal Shock Resistance of Zircaloy-4 Cladding under Simulated Loss-of-Coolant Accident Conditions
3. Behavior of High Burn-up Fuel Cladding under LOCA Conditions
4. Zircaloy-4 Cladding Embrittlement due to Inner Surface Oxidation under Simulated Loss-of-Coolant Condition
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1. The effect of a cyclic bending load on the bending resistance of ballooned, ruptured, and oxidized Zircaloy-4 cladding;Journal of Nuclear Science and Technology;2023-12-17
2. The effect of spacer grids on the stress applied to a post-LOCA cladding tube under horizontal vibrations;Journal of Nuclear Science and Technology;2023-08-22
3. DLI-MOCVD CrxCy coating to prevent Zr-based cladding from inner oxidation and secondary hydriding upon LOCA conditions;Journal of Nuclear Materials;2021-07
4. Toward a more reliable evaluation of fuel fracture during LOCA;Journal of the Atomic Energy Society of Japan;2021
5. Evaluation of the maximum bending stress of pre-hydrided Zircaloy-4 cladding tube after simulated loss-of-coolant-accident test;Annals of Nuclear Energy;2020-09
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