Zirconium Alloys for LWR Fuel Cladding and Core Internals-Reference-Cited by-同舟云学术

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Zirconium Alloys for LWR Fuel Cladding and Core Internals

Published:2019 Issue: Volume: Page:247-291
ISSN:
Container-title:Structural Alloys for Nuclear Energy Applications
language:
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Author:

Yagnik Suresh,Garde Anand

Publisher

Elsevier

Reference117 articles.

1. Review of Zircaloy-2 and Zircaloy-4 Properties Relevant to N. S. Savannah Reactor Design, ORNL-3281;Whitmarsh,1962

2. USN, The Decision to Use Zirconium in Nuclear Reactors;Rickover,2010

3. The Metallurgy of Zirconium;Thomas,1955

4. Development of the Zircaloys, USAEC report WAPD-T-1549;Kass,1963

5. Performance and Property Evaluation of High-Burnup Optimized ZIRLO™ Cladding;Pan,2015

Cited by 29 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. Thermal creep in a pre-hydrided Zr1 % Nb nuclear fuel cladding tube;Journal of Nuclear Materials;2024-08

2. Identification and time evolution of thionyl chloride (SOCl₂) radiolysis products;Radiochimica Acta;2024-06-21

3. EFFECT OF SURFACE MODIFICATION BY NITROGEN AND OXYGEN ON MECHANICAL PERFORMANCE OF Zr-1%Nb ALLOY;Problems of Atomic Science and Technology;2024-04-11

4. Using life cycle assessment to quantify the environmental benefits of circular economy strategies in the nuclear industry;Progress in Nuclear Energy;2024-03

5. Kinetics of Gas Carburizing of Zr–1%Nb Alloy;Materials Science;2024-03

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