Transient oxidation of Zircaloy fuel cladding in high temperature steam-Reference-Cited by-同舟云学术

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Transient oxidation of Zircaloy fuel cladding in high temperature steam

Published:1988-08 Issue: Volume:158 Page:217-223
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Shang-Shiang Hsu,Chuen-Horng Tsai

Publisher

Elsevier BV

Subject

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

Reference15 articles.

1. Code of Federal Regulations (CFR): 10 CFR 50.46: Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors,1983

2. High-temperature oxidation of zircaloy-2 and zircaloy-4 in steam

3. A study of Zircaloy-4-steam oxidation reaction kinetics;Biederman;EPRI NP-225,1976

4. Zirconium metal-water oxidation kinetics IV;Cathcart;Reaction rate studies, ORNL/NUREG-17,1977

Cited by 3 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. The effect of high pressure steam on the oxidation of low-Sn Zircaloy-4 at temperatures between 700 and 900°C;Journal of Nuclear Materials;2012-01

2. INFLUENCE OF HEAT-FLUX ON ISOTHERMAL OXIDATION OF ZIRCALOY-4 IN HIGH-TEMPERATURE STEAM;J NUCL SCI TECHNOL;1995

3. Influence of Heat Flux on Isothermal Oxidation of Zircaloy-4 in High Temperature Steam;Journal of Nuclear Science and Technology;1995-04

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