Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Control of beryllium-7 in liquid lithium

Conference ·
OSTI ID:6227049
Radiation fields created by the production of /sup 7/Be in lithium of the Fusion Materials Irradiation Test (FMIT) Facility can be sufficiently high to prevent contact maintenance of system components. Preliminary experiments have shown that /sup 7/Be will adhere strongly to the FMIT piping and components and a good control method for /sup 7/Be must be developed. The initial experiments have been conducted in static stainless steel capsules and a Modified Thermal Convection Loop (MTCL). The average lithium film thickness on stainless steel was found to be 11 ..mu..m in the temperature range 495/sup 0/ to 571/sup 0/K from the capsule experiments. The diffusion coefficient for /sup 7/Be in stainless steel at 543/sup 0/K was calculated to be 5.31 x 10/sup -15/ cm/sup 2//sec. The cold leg of the MTCL picked up much of the /sup 7/Be activity released into the loop. The diffusion trap, located in the cold leg of the MTCL, was ineffective in removing /sup 7/Be from lithium, at the very slow flow rates (< 3.79 x 10/sup -4/ m/sup 3//s) used in the MTCL. Pure iron has been shown to be superior to coblat and nickel as a getter material for /sup 7/Be.
Research Organization:
Hanford Engineering Development Lab., Richland, WA (USA)
Sponsoring Organization:
USDOE
DOE Contract Number:
EY-76-C-14-2170
OSTI ID:
6227049
Report Number(s):
HEDL-SA-1594-FP; CONF-790125-41
Country of Publication:
United States
Language:
English