Tritium experience in the Tokamak Fusion Test Reactor

Conference · Wed Jul 01 00:00:00 EDT 1998

OSTI ID:304157

Skinner, C H; Blanchard, W; Hosea, J; Mueller, D; Nagy, A ^[1]; Brooks, J N ^[2]; Hogan, J ^[3]

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1. Princeton Univ., NJ (United States). Princeton Plasma Physics Lab.
2. Argonne National Lab., IL (United States)
3. Oak Ridge National Lab., TN (United States)

Tritium management is a key enabling element in fusion technology. Tritium fuel was used in 3.5 years of successful deuterium-tritium (D-T) operations in the Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory. The D-T campaign enabled TFTR to explore the transport, alpha physics, and MHD stability of a reactor core. It also provided experience with tritium retention and removal that highlighted the importance of these issues in future D-T machines. In this paper, the authors summarize the tritium retention and removal experience in TFTR and its implications for future reactors.

• Research Organization: Princeton Univ., Princeton Plasma Physics Lab., NJ (United States)
• Sponsoring Organization: USDOE Office of Energy Research, Washington, DC (United States)
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 304157
• Report Number(s): PPPL-CFP-3030; CONF-980922-; ON: DE98057914; TRN: 99:002945
• Resource Relation: Conference: 20. symposium on fusion technology (SOFT `98), Marseille (France), 7-11 Sep 1998; Other Information: PBD: [1998]
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION
TRITIUM
TFTR TOKAMAK
THERMONUCLEAR FUELS
D-T OPERATION
TRITIUM RECOVERY
INVENTORIES
DEPOSITION