Preparations for deuterium tritium experiments on the Tokamak Fusion Test Reactor

Technical Report · Fri Apr 01 04:00:00 EST 1994

DOI:https://doi.org/10.2172/10144065· OSTI ID:10144065

Hawryluk, R J; Adler, H; Alling, P; Ancher, C; Anderson, H; Anderson, J W; Arunasalam, V; Ascione, G; Ashcroft, D; Barnes, G ^[1]

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1. and others

The final hardware modifications for tritium operation have been completed for the Tokamak Fusion Test Reactor (TFTR). These activities include preparation of the tritium gas handling system, installation of additional neutron shielding, conversion of the toroidal field coil cooling system from water to a Fluorinet{sup {trademark}} system, modification of the vacuum system to handle tritium, preparation and testing of the neutral beam system for tritium operation and a final deuterium-deuterium (D-D) run to simulate expected deuterium-tritium (D-T) operation. Testing of the tritium system with low concentration tritium has successfully begun. Simulation of trace and high power D-T experiments using D-D have been performed. The physics objectives of D-T operation are production of {approximately} 10 megawatts (MW) of fusion power, evaluation of confinement and heating in deuterium-tritium plasmas, evaluation of {alpha}-particle heating of electrons, and collective effects driven by alpha particles and testing of diagnostics for confined {alpha}-particles. Experimental results and theoretical modeling in support of the D-T experiments are reviewed.

• Research Organization: Princeton Univ., NJ (United States). Plasma Physics Lab.
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 10144065
• Report Number(s): PPPL--2987; ON: DE94010359
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700310
700460
CONFINEMENT
DEUTERIUM
FUELS
HEATING AND FUELING SYSTEMS
PLASMA CONFINEMENT
RESEARCH PROGRAMS
TFTR TOKAMAK
THERMONUCLEAR FUELS
TRITIUM
TRITIUM RECOVERY