Aluminum cladding oxide growth prediction for high flux research reactors-Reference-Cited by-同舟云学术

Aluminum cladding oxide growth prediction for high flux research reactors

Published:2020-02 Issue: Volume:529 Page:151926
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Kim Yeon Soo,Chae H.T.,Van den Berghe S.,Leenaers A.,Kuzminov V.,Yacout A.M.

Funder

National Nuclear Security Administration

Publisher

Elsevier BV

Subject

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

Reference25 articles.

1. Effect of Heat Flux on the Corrosion of Aluminum by Water. Part IV. Tests Relative to the Advanced Test Reactor and Correlation with Previous Results;Griess,1964

2. Effect of Heat Flux on the Corrosion of Aluminum by Water. Part III. Final Report on Tests Relative to the High Flux Isotope Reactor;Griess,1961

3. Evaluation of Mark 22 Cladding, DPST-83-324;Ondrejcin,1983

4. R.E. Pawel, G.L. Yoder, D.K. Felde, B.H. Montgomery, M.T. Mcfee, 36(1/2) (1991) 175.

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