Oxide/α and α/β phase interface advance kinetics in steam oxidised zircaloy-2-Reference-Cited by-同舟云学术

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Oxide/α and α/β phase interface advance kinetics in steam oxidised zircaloy-2

Published:1982-01 Issue:1 Volume:105 Page:93-102
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Brown A.F.,Tucker M.O.,Healey T.,Simpson C.J.

Publisher

Elsevier BV

Subject

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

Reference16 articles.

1. Proc. ANS Topical Meeting on Water Reactor Safety;Hobson,1973

2. Proc. Fourth Intern. Conf. on Zirconium in the Nuclear Industry;Chung,1979

3. Proc. Fourth Intern. Conf. on Zirconium in the Nuclear Industry;Sawatsky,1979

4. Proc. Specialist Meeting on the Behaviour of Water Reactor Fuel Elements under Accident Conditions;Malang,1976

Cited by 7 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. Study of oxide and α-Zr(O) growth kinetics from high temperature steam oxidation of Zircaloy-4 cladding;Journal of Nuclear Materials;2015-12

2. Assessment of oxygen diffusion coefficients by studying high-temperature oxidation behaviour of Zr1Nb fuel cladding in the temperature range of 1100–1300 °C;Journal of Nuclear Materials;2015-01

3. Microstructure evolution in Zr1Nb fuel cladding during high-temperature oxidation;Journal of Nuclear Materials;2011-09

4. Mathematical model for the kinetics of oxidation on cladding-stream side in UO2–zircaloy reaction;Materials Science and Engineering: A;2004-05

5. Corium Oxidation at Temperatures above 2000 K;Nuclear Technology;2001-02

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