Implications of Zircaloy creep and growth to light water reactor performance-Reference-Cited by-同舟云学术

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Implications of Zircaloy creep and growth to light water reactor performance

Published:1988-10 Issue: Volume:159 Page:12-21
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Franklin David G.,Adamson Ronald B.

Publisher

Elsevier BV

Subject

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

Reference27 articles.

1. Irradiation Growth of Zircaloy;Adamson;ASTM STP 633,1977

2. Zircaloy-2 Pressure Tube Elongation at the Hanford N Reactor;Alexander;ASTM STP 633,1977

3. Analysis of Irradiation Growth and Multiaxial Deformation Behavior of Nuclear Fuel Cladding;Clevinger;ASTM STP 681,1979

4. Analysis of Pressurized Water Reactor Fuel Pin Length Changes;Harbottle;ASTM STP 681,1979

5. Irradiation Growth in Cold-Worked Zircaloy-2;Murgatroyd;ASTM STP 681,1979

Cited by 26 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. On the contribution of local anisotropic creep to macroscopic irradiation-induced growth in zirconium alloy polycrystals;Philosophical Magazine;2024-09

2. A mechanistic study of grain boundary behaviour during irradiation-induced growth in zirconium;Acta Materialia;2024-09

3. Irradiation creep measurement and microstructural analysis of chromium nitride–coated zirconium alloy using pressurized tubes;Journal of Nuclear Materials;2024-01

4. Physics-based model of irradiation creep for ferritic materials under fusion energy operation conditions;Journal of Applied Physics;2022-12-14

5. Polycrystalline simulations of in-reactor deformation of recrystallized Zircaloy-4 tubes: Fast Fourier Transform computations and mean-field self-consistent model;International Journal of Plasticity;2022-06

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