The TFTR lithium blanket module program
Journal Article
·
· J. Fusion Energy; (United States)
The Lithium Blanket Module (LBM) is an approximately 80X80X80 cm cubic module, representative of a helium-cooled lithium oxide fusion reactor blanket module, that will be installed on the TFTR (Tokamak Fusion Test Reactor) in late 1986. The principal objective of the LBM Program is to perform a series of neutron transport and tritium-breeding measurements throughout the LBM when it is exposed to the TFTR toroidal fusion neutron source, and to compare these data with the predictions of Monte Carlo (MCNP) neutronics codes. The LBM consists of 920 2.5-cm diameter breeder rods constructed of lithium oxide (Li/sub 2/O) pellets housed in thin-walled stainless steel tubes. Procedures for mass-producing 25,000 Li/sub 2/O pellets with satisfactory reproducibility were developed using purified Li/sub 2/O powder, and fabrication of all the breeder rods was completed in early 1985. Tritium assay methods were investigated experimentally using both small lithium metal samples and LBM-type pellets. This work demonstrated that the thermal extraction method will be satisfactory for accurate evaluation of the minute concentrations of tritium expected in the LBM pellets (0.1-1nCi/g).
- Research Organization:
- Princeton Plasma Physics Lab., Princeton, NJ
- OSTI ID:
- 5194576
- Journal Information:
- J. Fusion Energy; (United States), Journal Name: J. Fusion Energy; (United States) Vol. 4:1; ISSN JFEND
- 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
ALKALI METAL COMPOUNDS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
BREEDING PELLETS
BREEDING RATIO
CHALCOGENIDES
COMPUTER-AIDED DESIGN
CONVERSION RATIO
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
LITHIUM COMPOUNDS
LITHIUM OXIDES
MATERIALS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
OXIDES
OXYGEN COMPOUNDS
RADIATION TRANSPORT
RADIOASSAY
RADIOISOTOPES
REACTOR COMPONENTS
TFTR TOKAMAK
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALI METAL COMPOUNDS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
BREEDING PELLETS
BREEDING RATIO
CHALCOGENIDES
COMPUTER-AIDED DESIGN
CONVERSION RATIO
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
LITHIUM COMPOUNDS
LITHIUM OXIDES
MATERIALS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
OXIDES
OXYGEN COMPOUNDS
RADIATION TRANSPORT
RADIOASSAY
RADIOISOTOPES
REACTOR COMPONENTS
TFTR TOKAMAK
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES