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Overview of recent studies related to lead-alloy-cooled fast reactors

Journal Article · · AIP Conference Proceedings
DOI:https://doi.org/10.1063/1.4725436· OSTI ID:22004174
; ; ;  [1]
  1. Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, N1-18, 2-12-1, O-okayama, Meguro-ku, Tokyo 152-8550 (Japan)
The recent progress of the studies related to lead alloy-cooled reactors (LFR) and the accelerator driven system (ADS) is summarized. The compatibility of materials with lead alloys has been clarified under steady and transient temperature conditions. Higher Cr content, Si and Al addition and Al-Fe alloy-coating improved the corrosion resistance of steels. The Al-Fe alloy-coated steel was not corroded even under high temperature transient conditions. The ceramics of SiC and Si{sub 3}N{sub 4} are expected to be used as cladding material for high temperature LFR. For the analytical consideration of mass transport in lead alloy circuit, the diffusion coefficient of Ni was measured using the capillary methods. A new bubble visualization method in LBE using gamma-ray radiography was developed. The thermal interaction of lead-bismuth eutectic (LBE) and lead droplets with sub-cooled water, and the behaviors of droplet fragmentation were investigated, and the visualization of volatile liquids in high temperature liquids was achieved.
OSTI ID:
22004174
Journal Information:
AIP Conference Proceedings, Journal Name: AIP Conference Proceedings Journal Issue: 1 Vol. 1448; ISSN 0094-243X; ISSN APCPCS
Country of Publication:
United States
Language:
English