Elastoplastic mechanical behavior analysis of surface-coated Zircaloy-4 cladding under multi-field coupling-Reference-Cited by-同舟云学术

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Elastoplastic mechanical behavior analysis of surface-coated Zircaloy-4 cladding under multi-field coupling

Published:2024-08 Issue: Volume: Page:
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Wang Xin,Xu Ze^ORCID,Liu Yulan,Wang Biao

Publisher

Elsevier BV

Reference29 articles.

1. Current status of materials development of nuclear fuel cladding tubes for light water reactors;Duan;Nucl. Eng. Des.,2017

2. Deformation mechanism and cyclic stress response of Zircaloy-4 alloy cladding tube during low cycle fatigue at room temperature;Guo;Int. J. Fatig.,2022

3. Thermomechanical evaluation of ATF fuel rods regarding irradiation effects;Yadollahpour;Nucl. Eng. Des.,2023

4. Simulation of the compression test of the Zr1Nb fuel cladding ring;Smolík;Acta Polytechnica CTU Proceedings,2023

5. Cracking of Cr-coated accident-tolerant fuel during normal operation and under power-ramping conditions;Hong;Nucl. Eng. Des.,2019

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