Corrosion Behavior of FBR Candidate Materials in Stagnant Pb-Bi at Elevated Temperature-Reference-Cited by-同舟云学术

Corrosion Behavior of FBR Candidate Materials in Stagnant Pb-Bi at Elevated Temperature

Published:2004-03 Issue:3 Volume:41 Page:265-270
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

FURUKAWA Tomohiro,MÜLLER Georg,SCHUMACHER Gustav,WEISENBURGER Alfons,HEINZEL Annette,ZIMMERMANN Frank,AOTO Kazumi

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

http://www.tandfonline.com/doi/pdf/10.1080/18811248.2004.9715484

Reference18 articles.

1. Lead, bismuth, tin and their alloys as nuclear coolants

2. Gromov, B. F., Orlov, Y. I., Martynov, P. N. and Gulevsky, V. A. Proc. Heavy Liquid Metal Coolants in Nucl. Technology (HLMC-98). Vol. 1, pp.87–100.

3. Romano, A. J., Klamut, C. J. and Gurinsky, D. H. 1963. BNL 811

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