Effect of Alloying Elements, Cold Work, and Hydrogen on the Irradiation-Induced Growth Behavior of Zirconium Alloy Variants-Reference-Cited by-同舟云学术

Effect of Alloying Elements, Cold Work, and Hydrogen on the Irradiation-Induced Growth Behavior of Zirconium Alloy Variants

Published:2018-01-01 Issue: Volume: Page:748-795
ISSN:
Container-title:Zirconium in the Nuclear Industry: 18th International Symposium
language:
Short-container-title:

Author:

Yagnik Suresh¹,Adamson Ronald²,Kobylyansky Gennady³,Chen Jen-Hung⁴,Gilbon Didier⁵,Ishimoto Shinji⁶,Fukuda Takuji⁷,Hallstadius Lars⁸,Obukhov Alexander³,Mahmood Sheikh⁹

Affiliation:

1. EPRI, 3420 Hillview Ave., Palo Alto, CA, 94304

2. Zircology Plus, 36848 Montecito Dr., Fremont, CA 94536

3. Research Institute of Atomic Reactors, Dimitrovgrad-10, 433510 RU

4. Institute of Nuclear Energy Research, Lungtan, Taoyuan, 325 TW

5. CEA, Saclay Center, Gif-sur-Yvette, 91191 FR

6. Global Nuclear Fuel, Yokosuka-Shi, Kanagawa-ken, 239-0836 JP

7. Nuclear Fuel Industry, Tokai-mura, Naka-gun, Ibaraki 319-1198 JP

8. Westinghouse, Vasteras, 72163 SE

9. 4437-C Valley Ave. Pleasanton, CA 94566 US

Publisher

ASTM International

Cited by 30 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. Stress and Temperature Dependence of Irradiation Creep in Zircaloy-4 Studied Using Proton Irradiation;Journal of Nuclear Materials;2024-09

4. Formation of pure zirconium islands inside c-component loops in high-burnup fuel cladding;Journal of Nuclear Materials;2024-08

5. A spatially resolved analysis of dislocation loop and nanohardness evolution in proton irradiated Zircaloys;Acta Materialia;2024-05