Tritium retention and release analysis for US-ITER blanket

Conference · Thu Nov 01 04:00:00 EST 1990

OSTI ID:5928209

Billone, M C; Lin, C C; Attaya, H; Gohar, Y

The US design for the ITER tritium-breeding blanket consists of layers of Be multiplier, stainless steel cladding, and Li{sub 2}O ceramic breeder. Tritium is recovered from the ceramic breeder by purging it with He + 0.2% H{sub 2}. Models have been developed to describe the purge-flow thermal-hydraulics and gas reactions and the tritium retention/release due to lattice diffusion, desorption/adsorption, solubility/precipitation, and percolation through interconnected porosity. These have been incorporated into the steady-state code TIARA for the purpose of performing design calculations for Tritium Inventory and Release Analysis. Transient calculations for pulsed operation are done with a modified version of the DISPL code. The results of both steady-state and transient analyses for tritium retention and releases are given for anticipated ITER operating conditions. 13 refs., 6 figs., 3 tabs.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: DOE; USDOE, Washington, DC (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5928209
• Report Number(s): ANL/CP-70627; CONF-901007--63; ON: DE91010629
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
ALKALI METAL COMPOUNDS
ALKALINE EARTH METALS
ALLOYS
BERYLLIUM
BREEDING BLANKETS
CHALCOGENIDES
CLOSED PLASMA DEVICES
DESIGN
ELEMENTS
ENERGY TRANSFER
FLOW MODELS
FLUID MECHANICS
HEAT TRANSFER
HIGH ALLOY STEELS
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
ITER TOKAMAK
LITHIUM COMPOUNDS
LITHIUM OXIDES
MATHEMATICAL MODELS
MECHANICS
METALS
OXIDES
OXYGEN COMPOUNDS
REACTOR COMPONENTS
RECOVERY
STAINLESS STEELS
STEELS
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
TRITIUM RECOVERY