Thermal convection loop experiments and analysis of mass transport process in Lithium/Fe-12Cr-1MoVW systems

Technical Report · Fri Jan 01 04:00:00 EST 1988

DOI:https://doi.org/10.2172/6265916· OSTI ID:6265916

Bell, G. E.C.

Lithium is an attractive coolant and breeder material for first- generation fusion reactor blankets. The compatibility of lithium with structural alloys, in the form of mass transport and deposition, may impose restrictions on blanket operating parameters such as temperature and lithium purity. A ferritic steel, such as Fe-12CrlMoVW, is a candidate for use as a structural alloy in a self-cooled lithium blanket design. Experimental data on mass transport in lithium/Fe-12CrlMoVW were obtained from two thermal convection loops which spanned the fusion relevant temperature range; one operated from 360 to 505/degree/C for 3040 hours and the other from 525 to 655/degree/C for 2510 hours. The experimental effort was supported by analysis of the mechanisms and processes of mass transport and deposition. It was found that mass transport and deposition, as measured by specimen weight change, were not simple functions of temperature for the entire temperature range investigated. The mass transfer behavior and surface morphology at low temperatures were dominated by impurity reactions of nitrogen and carbon in the lithium with the steel. In the experiment between 360 and 505/degree/C, nitrogen levels were sufficient below 450/degree/C to allow the formation of the adherent, protective corrosion product Li/sub 9/CrN/sub 5/. Weight losses in the 360 to 505/degree/C experiment were insensitive to temperature below 450/degree/C. Between 450 and 505/degree/C, the precipitation of carbon in the form of chromium-rich M/sub 23/C/sub 6/ (M = Fe or Cr) carbides, due to the formation of Li/sub 9/CrN/sub 5/ and corresponding release of carbon, resulted in weight gains for the highest temperature specimens in the experiment. 98 refs., 83 figs., 9 tabs.

• Research Organization: California Univ., Los Angeles (USA)
• DOE Contract Number: AC05-76OR00033
• OSTI ID: 6265916
• Report Number(s): DOE/OR/00033-T421; ON: DE89010609
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700204 -- Fusion Power Plant Technology-- Cooling Systems
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALI METALS
ALLOYS
BREEDING BLANKETS
CONVECTION
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
FERRITIC STEELS
HEAT TRANSFER
IRON ALLOYS
IRON BASE ALLOYS
LITHIUM
MASS TRANSFER
MATERIALS
METALS
REACTOR COMPONENTS
STEELS
THERMONUCLEAR REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS