Study Plan for Material Corrosion Test in Lead and Bismuth Eutectic at High Temperature
Conference
·
OSTI ID:20997049
- Tokyo Institute of Technology, 2-12-1 Ookayama, Meguro-ku, Tokyo 152-8550 (Japan)
A concept of steam lift pump type lead-bismuth cooled fast reactor (SLPLFR) is proposed as high temperature and high efficiency Pb-Bi cooled fast reactors. Fe-Al alloy-surface treated steels and ceramics of SiC, Si{sub 3}N{sub 4} and SiC/SiC composites have been chosen as candidates of cladding and structural materials, respectively. A corrosion test plan is proposed, where compatibility of steels applied with Al-Fe alloy-surface treatment and the ceramics will be tested in high temperature Pb-Bi flow. A conceptual design of a test apparatus for the corrosion test is provided. (authors)
- Research Organization:
- The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
- OSTI ID:
- 20997049
- Resource Relation:
- Conference: 14. International conference on nuclear engineering (ICONE 14), Miami - Florida (United States), 17-20 Jul 2006; Other Information: Country of input: France
- Country of Publication:
- United States
- Language:
- English
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