The chemistry of molten Li/sub 2/BeF/sub 4/
Conference
·
· Fusion Technol.; (United States)
OSTI ID:6832727
The LiF . BeF/sub 2/ system is a potential tritium breeder for a fusion power reactor. The chemical consequences of the TF(HF) generation are examined, particularly reactions proposed for moderating the corrosive properties of TF(HF). The use of molten Li/sub 2/BeF/sub 4/ as a tritium breeding blanket was considered by Grimes and Cantor in 1972. Renewed interest in LiF . BeF/sub 2/ compositions as tritium breeding blankets for MINIMARS (a conceptual design study of a commercial tandem mirror fusion reactor), suggests that a review of the chemical and physical properties of this system is appropriate at this time. A large fraction of the data presented here is derived from the publications of the molten salt breeder (fission) reactor program which prospered at Oak Ridge National Laboratories during the late 1960's and early 1970's. The predictions of chemical reactivity are based on the thermochemical data at 1000 K.
- Research Organization:
- Univ. of Wisconsin, Fusion Technology Institute, Nuclear Engineering Dept., 1500 Johnson Drive, Madison, WI 53706-1687
- OSTI ID:
- 6832727
- Report Number(s):
- CONF-860652-
- Conference Information:
- Journal Name: Fusion Technol.; (United States) Journal Volume: 10:3
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201 -- Fusion Power Plant Technology-- Blanket Engineering
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ACTIVATION ENERGY
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
CHEMICAL REACTION KINETICS
ENERGY
FLIBE
HYDROGEN ISOTOPES
ISOTOPES
KINETICS
LIGHT NUCLEI
MAGNETIC MIRROR TYPE REACTORS
MATERIALS
MATERIALS TESTING
MINIMARS REACTOR
MOLTEN SALTS
NATIONAL ORGANIZATIONS
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
ORNL
RADIOISOTOPES
REACTION KINETICS
REACTOR COMPONENTS
SALTS
TESTING
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS
TRITIUM
US AEC
US DOE
US ERDA
US ORGANIZATIONS
VERY HIGH TEMPERATURE
YEARS LIVING RADIOISOTOPES
700201 -- Fusion Power Plant Technology-- Blanket Engineering
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ACTIVATION ENERGY
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
CHEMICAL REACTION KINETICS
ENERGY
FLIBE
HYDROGEN ISOTOPES
ISOTOPES
KINETICS
LIGHT NUCLEI
MAGNETIC MIRROR TYPE REACTORS
MATERIALS
MATERIALS TESTING
MINIMARS REACTOR
MOLTEN SALTS
NATIONAL ORGANIZATIONS
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
ORNL
RADIOISOTOPES
REACTION KINETICS
REACTOR COMPONENTS
SALTS
TESTING
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS
TRITIUM
US AEC
US DOE
US ERDA
US ORGANIZATIONS
VERY HIGH TEMPERATURE
YEARS LIVING RADIOISOTOPES