Computer aided design of operational units for tritium recovery from Li{sub 17}Pb{sub 83} blanket of a DEMO fusion reactor

Journal Article · Wed Mar 01 04:00:00 EST 1995 · Fusion Technology

OSTI ID:219727

Malara, C ^[1]; Viola, A ^[2]

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1. Institute Regional des Materiaux Avances c/o Safety Technology Inst., Ispra (Italy)
2. Univ. of Cagliari (Italy)

The problem of tritium recovery from Li{sub 17}Pb{sub 83} blanket of a DEMO fusion reactor is analyzed with the objective of limiting tritium permeation into the cooling water to acceptable levels. To this aim, a mathematical model describing the tritium behavior in blanket/recovery unit circuit has been formulated. By solving the model equations, tritium permeation rate into the cooling water and tritium inventory in the blanket are evaluated as a function of dimensionless parameters describing the combined effects of overall resistance for tritium transfer from Li{sub 17}Pb{sub 83} alloy to cooling water, circulating rate of the molten alloy in blanket/recovery unit circuit and extraction efficiency of tritium recovery unit. The extraction efficiency is, in turn, evaluated as a function of the operating conditions of recovery unit. The design of tritium recovery unit is then optimized on the basis of the above parametric analysis and the results are herein reported and discussed for a tritium permeation limit of 10 g/day into the cooling water. 14 refs., 9 figs., 2 tabs.

• OSTI ID: 219727
• Report Number(s): CONF-930937--
• Journal Information: Fusion Technology, Journal Name: Fusion Technology Journal Issue: 2T Vol. 27; ISSN 0748-1896; ISSN FUSTE8
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
99 GENERAL AND MISCELLANEOUS
BREEDING BLANKETS
CALCULATION METHODS
COMPUTER-AIDED DESIGN
INVENTORIES
LEAD ALLOYS
LITHIUM ALLOYS
MATHEMATICAL MODELS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTORS
TRITIUM RECOVERY
USES