Surface erosion and tritium inventory analysis for CIT (Compact Ignition Tokamak)

Conference · Sat Sep 01 04:00:00 EDT 1990

OSTI ID:6308185

Brooks, J N ^[1]; Dylla, H F ^[2]; Pontau, A E; Wilson, K L ^[3]

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1. Argonne National Lab., IL (USA)
2. Princeton Univ., NJ (USA). Plasma Physics Lab.
3. Sandia National Labs., Livermore, CA (USA)

The expected buildup of co-deposited tritium on the CIT carbon divertor and first wall surfaces and operational methods of minimizing the inventory have been examined. The analysis uses impurity transport computer codes, and associated plasma and tritium retention models, to compute the thickness of redeposited sputtered carbon and the resulting co-deposited tritium inventory on the divertor plates and first wall. Predicted erosion/growth rates are dominated by the effect of gaps between carbon tiles. The overall results appear favorable, showing stable operation (finite self-sputtering) and acceptably low ({approximately}25 Ci/pulse) co-deposited tritium rates, at high surface temperature (1700{degree}C) design conditions. These results, however, are highly speculative due to serious model inadequacies at the high sputtering rates predicted. If stable operation is obtainable, the prospects appear good for adequate tritium inventory control via helium-oxygen glow discharge cleaning. 25 refs.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: W-31109-ENG-38; AC04-76DR00789; AC02-76CH03073
• OSTI ID: 6308185
• Report Number(s): CONF-901007-42; ON: DE91006361
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201 -- Fusion Power Plant Technology-- Blanket Engineering
700202 -- Fusion Power Plant Technology-- Magnet Coils & Fields
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
CLOSED PLASMA DEVICES
COMPACT IGNITION TOKAMAK
DIVERTORS
EROSION
FIRST WALL
IMPURITIES
PLASMA IMPURITIES
RECOVERY
SPUTTERING
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
TRITIUM RECOVERY