Plasma wall interaction and tritium retention in TFTR

Conference · Wed May 01 04:00:00 EDT 1996

OSTI ID:270817

Skinner, C. H. ^[1]; Amarescu, E. ^[1]; Ascione, G. ^[1]; Synakowski, E. ^[1]

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1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

The Tokamak Fusion Test Reactor (TFTR) has been operating safely and routinely with deuterium-tritium fuel for more than two years. In this time, TFTR has produced an impressive number of record breaking results including core fusion power, ~ 2 MW/m³, comparable to that expected for ITER. Advances in wall conditioning via lithium pellet injection have played an essential role in achieving these results. Deuterium-tritium operation has also provided a special opportunity to address the issues of tritium recycling and retention. Tritium retention over two years of operation was approximately 40%. Recently, the in-torus tritium inventory was reduced by half through a combination of glow discharge cleaning, moist-air soaks, and plasma discharge cleaning. The tritium inventory is not a constraint in continued operations. The authors present recent results from TFTR in the context of plasma wall interactions and deuterium-tritium issues.

• Research Organization: Princeton Univ., NJ (United States). Plasma Physics Lab.
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 270817
• Report Number(s): PPPL--3189; CONF-960569--7; ON: DE96012020
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
D-T OPERATION
FUEL CYCLE
INVENTORIES
LIMITERS
PLASMA DENSITY
RECYCLING
TFTR TOKAMAK
THERMONUCLEAR REACTOR FUELING
THERMONUCLEAR REACTOR MATERIALS
TRITIUM
TRITIUM RECOVERY