A study of the breakaway oxidation behavior of zirconium cladding materials-Reference-Cited by-同舟云学术

A study of the breakaway oxidation behavior of zirconium cladding materials

Published:2011-11 Issue:1-3 Volume:418 Page:186-197
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Kim Hyun-Gil,Kim Il-Hyun,Choi Byung-Kwon,Park Jeong-Yong

Publisher

Elsevier BV

Subject

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

Reference15 articles.

1. F.J. Erbacher, S. Leistikow, Zirconium in the Nuclear Industry, ASTM STP 939 1987, pp. 451.

2. H.M. Chung, T.F. Kassner, Embrittlement Criteria for Zircaloy Fuel Cladding Applicable to Accident Situations in Light-Water Reactors: Summary Report NUREG/CR-1344, ANL-79-48, 1980.

3. The oxidation behavior of Zircaloy-4 in steam between 600 and 1600°C

4. Oxidation kinetics and related phenomena of zircaloy-4 fuel cladding exposed to high temperature steam and hydrogen-steam mixtures under PWR accident conditions

5. Breakaway phenomenon of Zr-based alloys during a high-temperature oxidation

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