Corrosion Studies in Support of Medium-Power Lead-Alloy-Cooled Reactor
- Idaho National Engineering and Environmental Laboratory (United States)
- Massachusetts Institute of Technology (United States)
The performance of structural materials in lead or lead-bismuth eutectic (LBE) systems is evaluated. The materials evaluated included refractory metals (W, Mo, and Ta), several U.S. steels [austenitic steel (316L), carbon steels (F-22, Fe-Si), ferritic/martensitic steels (HT-9 and 410)], and several experimental Fe-Si-Cr alloys that were expected to demonstrate corrosion resistance. The materials were exposed in either an LBE rotating electrode or a dynamic corrosion cell for periods from 100 to 1000 h at temperatures of 400, 500, 600, and 700 deg. C, depending on material and exposure location. Weight change and optical scanning electron microscopy or X-ray analysis of the specimen were used to characterize oxide film thickness, corrosion depth, microstructure, and composition changes. The results of corrosion tests validate the excellent resistance of refractory metals (W, Ta, and Mo) to LBE corrosion. The tests conducted with stainless steels (410, 316L, and HT-9) produced mass transfer of elements (e.g., Ni and Cr) into the LBE, resulting in degradation of the material. With Fe-Si alloys a Si-rich layer (as SiO{sub 2}) is formed on the surface during exposure to LBE from the selective dissolution of Fe.
- OSTI ID:
- 20840217
- Journal Information:
- Nuclear Technology, Vol. 147, Issue 3; Other Information: Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/; Country of input: International Atomic Energy Agency (IAEA); ISSN 0029-5450
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
AUSTENITIC STEELS
BISMUTH
BUILDING MATERIALS
CARBON STEELS
CORROSION
CORROSION RESISTANCE
EUTECTICS
FERRITIC STEELS
LEAD
LEAD ALLOYS
LIQUID METAL COOLED REACTORS
MICROSTRUCTURE
PERFORMANCE
REFRACTORY METALS
SCANNING ELECTRON MICROSCOPY
SILICA
SILICON OXIDES
STAINLESS STEEL-410
X RADIATION