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

Conference · Wed Jan 01 00:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5637900

Quanci, J; Azam, S; Bertone, P

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 x 10/sup 12/ 14-MeV n/s. Both Princeton Plasma Physics Lab. (PPPL) and EPFL assayed the tritium bred at various positions in the LBM. EPFL employed a dissolution technique while PPPL recovered the tritium by a thermal extraction method.

• Research Organization: Princeton Plasma Physics Lab., NJ
• OSTI ID: 5637900
• Report Number(s): CONF-860610-; TRN: 88-008099
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 52; Conference: American Nuclear Society annual meeting, Reno, NV, USA, 15 Jun 1986
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BREEDING BLANKETS
BREEDING RATIO
TFTR TOKAMAK
BREEDING PELLETS
LITHIUM OXIDES
NEUTRON SOURCE FACILITIES
QUALITATIVE CHEMICAL ANALYSIS
SPATIAL DISTRIBUTION
ALKALI METAL COMPOUNDS
CHALCOGENIDES
CHEMICAL ANALYSIS
CONVERSION RATIO
DISTRIBUTION
LITHIUM COMPOUNDS
OXIDES
OXYGEN COMPOUNDS
REACTOR COMPONENTS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700201* - Fusion Power Plant Technology- Blanket Engineering