Tritium assay of Li sub 2 O pellets in the LBM/LOTUS experiments
One of the objectives of the Lithium Blanket Module (LBM) program is to test the ability of advanced neutronics codes to model the tritium breeding characteristics of a fusion blanket exposed to a toroidal fusion neutron source. The LBM consists of over 20,000 cylindrical lithium oxide pellets and numerous diagnostic pellets and wafers. The LBM has been irradiated at the Ecole Polytechnique Federale de Lausanne (EPFL) LOTUS facility with a Haefely sealed neutron generator that gives a point deuterium-tritium neutron source up to 5 {times} 10{sup 12} 14-MeV n/s. Both Princeton Plasma Physics Laboratory (PPL) and EPFL assayed the tritium bred at various positions in the LBM. EPFL employed a dissolution technique while PPL recovered the tritium by a thermal extraction method. EPFL uses 0.38-g, 75% TD, lithium oxide diagnostic wafers to evaluate the tritium bred in the LBM. PPPL employs a thermal extraction method to determine the tritium bred in lithium oxide samples. In the initial experiments, diagnostic pellets and wafers were placed at five locations in the LBM central removable test rod at distances of 3, 9, 21, 36, and 48 cm from the front face of the module. The two sets of data for the tritium bred in the LBM along its centerline as a function of distance from the front face of the module were compared with each other, and with the predictions of two-dimensional neutronics codes. 1 ref.
- OSTI ID:
- 6764987
- Report Number(s):
- CONF-860610-Summs.; CODEN: TANSA; TRN: 90-022116
- Journal Information:
- Transactions of the American Nuclear Society; (USA), Vol. 52; Conference: American Nuclear Society annual meeting, Reno, NV (USA), 15-20 Jun 1986; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Tritium assay of Li/sub 2/O in the LBM/LOTUS experiments
The LBM program at the EPFL/LOTUS Facility
Related Subjects
BREEDING BLANKETS
NEUTRON TRANSPORT
TRITIUM
BREEDING RATIO
BREEDING PELLETS
COMPARATIVE EVALUATIONS
COMPUTER CODES
IRRADIATION
LITHIUM OXIDES
LOTUS FACILITY
MEASURING METHODS
PERFORMANCE TESTING
TRITIUM RECOVERY
ALKALI METAL COMPOUNDS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHALCOGENIDES
CONVERSION RATIO
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
LITHIUM COMPOUNDS
NEUTRAL-PARTICLE TRANSPORT
NUCLEI
ODD-EVEN NUCLEI
OXIDES
OXYGEN COMPOUNDS
RADIATION TRANSPORT
RADIOISOTOPES
REACTOR COMPONENTS
RECOVERY
TESTING
YEARS LIVING RADIOISOTOPES
700201* - Fusion Power Plant Technology- Blanket Engineering