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
Similar Records
Transport of beryllium-7 in a lithium loop
Transport of /sup 7/Be in a lithium loop
Corrosion behavior of materials selected for FMIT lithium system
Journal Article
·
Sun Jul 01 00:00:00 EDT 1984
· Fusion Technol.; (United States)
·
OSTI ID:5595562
Transport of /sup 7/Be in a lithium loop
Conference
·
Thu Jul 01 00:00:00 EDT 1982
·
OSTI ID:6697229
Corrosion behavior of materials selected for FMIT lithium system
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:6062353
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700206* -- Fusion Power Plant Technology-- Environmental Aspects
ALKALI METALS
ALKALINE EARTH ISOTOPES
ALLOYS
BERYLLIUM 7
BERYLLIUM ISOTOPES
BETA DECAY RADIOISOTOPES
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COATINGS
COBALT
CORROSION RESISTANT ALLOYS
DAYS LIVING RADIOISOTOPES
DIFFUSION
DIMENSIONS
ELECTRON CAPTURE RADIOISOTOPES
ELEMENTS
EVEN-ODD NUCLEI
GETTERS
HAZARDS
HEALTH HAZARDS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
LITHIUM
MATERIALS
METALS
MOLYBDENUM ALLOYS
NICKEL
NICKEL ALLOYS
NUCLEI
RADIATION HAZARDS
RADIOISOTOPES
REMOVAL
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTORS
THICKNESS
TRANSITION ELEMENTS
700206* -- Fusion Power Plant Technology-- Environmental Aspects
ALKALI METALS
ALKALINE EARTH ISOTOPES
ALLOYS
BERYLLIUM 7
BERYLLIUM ISOTOPES
BETA DECAY RADIOISOTOPES
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COATINGS
COBALT
CORROSION RESISTANT ALLOYS
DAYS LIVING RADIOISOTOPES
DIFFUSION
DIMENSIONS
ELECTRON CAPTURE RADIOISOTOPES
ELEMENTS
EVEN-ODD NUCLEI
GETTERS
HAZARDS
HEALTH HAZARDS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
LITHIUM
MATERIALS
METALS
MOLYBDENUM ALLOYS
NICKEL
NICKEL ALLOYS
NUCLEI
RADIATION HAZARDS
RADIOISOTOPES
REMOVAL
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTORS
THICKNESS
TRANSITION ELEMENTS