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Title: Tritium assay of Li sub 2 O pellets in the LBM/LOTUS experiments

Abstract

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 bredmore » 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.« less

Authors:
; ;
Publication Date:
OSTI Identifier:
6764987
Report Number(s):
CONF-860610-Summs.
Journal ID: ISSN 0003-018X; CODEN: TANSA; TRN: 90-022116
Resource Type:
Conference
Journal Name:
Transactions of the American Nuclear Society; (USA)
Additional Journal Information:
Journal Volume: 52; Conference: American Nuclear Society annual meeting, Reno, NV (USA), 15-20 Jun 1986; Journal ID: ISSN 0003-018X
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; 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

Citation Formats

Quanci, J, Azam, S, and Bertone, P. Tritium assay of Li sub 2 O pellets in the LBM/LOTUS experiments. United States: N. p., 1986. Web.
Quanci, J, Azam, S, & Bertone, P. Tritium assay of Li sub 2 O pellets in the LBM/LOTUS experiments. United States.
Quanci, J, Azam, S, and Bertone, P. 1986. "Tritium assay of Li sub 2 O pellets in the LBM/LOTUS experiments". United States.
@article{osti_6764987,
title = {Tritium assay of Li sub 2 O pellets in the LBM/LOTUS experiments},
author = {Quanci, J and Azam, S and Bertone, P},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/6764987}, journal = {Transactions of the American Nuclear Society; (USA)},
issn = {0003-018X},
number = ,
volume = 52,
place = {United States},
year = {Wed Jan 01 00:00:00 EST 1986},
month = {Wed Jan 01 00:00:00 EST 1986}
}

Conference:
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