Tritium assay of Li/sub 2/O in the LBM/LOTUS experiments
Conference
·
· Fusion Technol.; (United States)
OSTI ID:6833086
The Lithium Blanket Module (LBM) is an assembly of over 20,000 cylindrical lithium oxide pellets in an array representative of a limited-coverage breeding zone for a toroidal fusion device. A principal objective of the LBM program is to test the ability of advanced neutronics coding to model the tritium breeding characteristics of a fusion device blanket. The LBM has been irradiated at the Ecole Polytechnique Federale de Lausanne (EPFL) LOTUS facility with a 14 MeV point-neutron source. Princeton Plasma Physics Laboratory (PPPL) and EPFL assayed the tritium bred in lithium oxide diagnostic samples placed at various positions in the LBM. PPPL employed a thermal extraction technique while EPFL used a dissolution method. The results for the assay are reported and compared to MCNP Monte Carlo neutronics calculations for the LBM/LOTUS system.
- Research Organization:
- Princeton Plasma Physics Lab., Princeton, NJ 08544
- OSTI ID:
- 6833086
- Report Number(s):
- CONF-860652-
- Conference Information:
- Journal Name: Fusion Technol.; (United States) Journal Volume: 10:3
- Country of Publication:
- United States
- Language:
- English
Similar Records
Tritium assay of Li/sub 2/O pellets in the LBM/LOTUS experiments
Tritium assay of Li sub 2 O pellets in the LBM/LOTUS experiments
LBM program at the LOTUS facility
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5637900
Tritium assay of Li sub 2 O pellets in the LBM/LOTUS experiments
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:6764987
LBM program at the LOTUS facility
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5503670
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
ALKALI METAL COMPOUNDS
ANNULAR SPACE
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
BREEDING PELLETS
CHALCOGENIDES
CHEMICAL ANALYSIS
COMPUTER CALCULATIONS
COMPUTER CODES
CONFIGURATION
DISSOLUTION
ENERGY RANGE
HEAT EXTRACTION
HYDROGEN ISOTOPES
IRRADIATION
ISOTOPES
LIGHT NUCLEI
LITHIUM COMPOUNDS
LITHIUM OXIDES
LOTUS FACILITY
M CODES
MEV RANGE
MEV RANGE 10-100
MONTE CARLO METHOD
NEUTRON SOURCES
NEUTRON SPECTRA
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
OXIDES
OXYGEN COMPOUNDS
PARTICLE SOURCES
QUALITATIVE CHEMICAL ANALYSIS
RADIATION SOURCES
RADIOISOTOPES
REACTOR COMPONENTS
RESEARCH PROGRAMS
SPACE
SPECTRA
THERMONUCLEAR DEVICES
TOROIDAL CONFIGURATION
TRITIUM
YEARS LIVING RADIOISOTOPES
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
ALKALI METAL COMPOUNDS
ANNULAR SPACE
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
BREEDING PELLETS
CHALCOGENIDES
CHEMICAL ANALYSIS
COMPUTER CALCULATIONS
COMPUTER CODES
CONFIGURATION
DISSOLUTION
ENERGY RANGE
HEAT EXTRACTION
HYDROGEN ISOTOPES
IRRADIATION
ISOTOPES
LIGHT NUCLEI
LITHIUM COMPOUNDS
LITHIUM OXIDES
LOTUS FACILITY
M CODES
MEV RANGE
MEV RANGE 10-100
MONTE CARLO METHOD
NEUTRON SOURCES
NEUTRON SPECTRA
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
OXIDES
OXYGEN COMPOUNDS
PARTICLE SOURCES
QUALITATIVE CHEMICAL ANALYSIS
RADIATION SOURCES
RADIOISOTOPES
REACTOR COMPONENTS
RESEARCH PROGRAMS
SPACE
SPECTRA
THERMONUCLEAR DEVICES
TOROIDAL CONFIGURATION
TRITIUM
YEARS LIVING RADIOISOTOPES