Mathematical model applied to permeation problems of process designs for tritium recovery from liquid blankets

Journal Article · Mon Sep 01 04:00:00 EDT 1986 · Fusion Technol.; (United States)

OSTI ID:5067428

Baratti, R; Polcaro, A M; Ricci, P F; Viola, A

A mathematical model has been developed to determine the amount of tritium that permeates the cooling circuit of a tritium breeding blanket containing the liquid eutectic alloy 17Li-83Pb. This model, which has been applied to phase 2A of the International Tokamak Reactor/Next European Torus project, is used to predict the effect of the operating conditions of the blanket, as well as those of a spray tower employed as a tritium recovery unit, and the kinetic parameters for the permeation and desorption processes. The results of this theoretical study indicate that the amount of permeated tritium proved to be not very different for the maximum (10.82 kPa/sup 1/2/ . m/sup 3/(mol . T)/sup -1/) and minimum (0.7 kPa/sup 1/2/ . m/sup 3/(mol . T)/sup -1/) values of Sievert's constant (K/sub s/) existing in literature. This amount, moreover, can be reduced to 0.1 to 0.01 g/day of tritium by the presence of small oxide barriers (a permeation reduction factor of ..cap alpha..approx. =100) on the cooling tubes and by the easy operating conditions of the spray tower, which include a droplet diameter of 0.5 mm; a tritium pressure of 0.13 kPa at 673K; and a residence time of 0.5 s.

• Research Organization: Univ. of Cagliari, Piazza D'Armi 09100, Cagliari
• OSTI ID: 5067428
• Journal Information: Fusion Technol.; (United States), Journal Name: Fusion Technol.; (United States) Vol. 10:2; ISSN FUSTE
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360104 -- Metals & Alloys-- Physical Properties
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201 -- Fusion Power Plant Technology-- Blanket Engineering
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
ALLOYS
BREEDING BLANKETS
CHALCOGENIDES
COOLING
COOLING SYSTEMS
DESORPTION
DROPLETS
ELEMENTS
ENERGY SYSTEMS
FLUIDS
HIGH TEMPERATURE
LEAD ALLOYS
LEAD BASE ALLOYS
LIQUID METALS
LIQUIDS
LITHIUM ALLOYS
LOW PRESSURE
MATHEMATICAL MODELS
METALS
NET TOKAMAK
OXIDES
OXYGEN COMPOUNDS
PARTICLES
PERMEABILITY
RADIATION DOSE UNITS
REACTOR COMPONENTS
RECOVERY
SIEVERT UNIT
SPRAY COOLING
THERMONUCLEAR REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTORS
TIME DEPENDENCE
TOKAMAK TYPE REACTORS
TRITIUM RECOVERY
UNITS