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Title: Experience with deuterium-tritium plasmas heated by high power neutral beams

Abstract

The Tokamak Fusion Test Reactor has operated since November of 1993 with a deuterium-tritium fuel mixture for selected discharges. The majority of the tritium has been introduced as energetic neutral atoms of up to 120 keV injected by the neutral beam systems, with some of the twelve ion sources run on pure tritium and some on deuterium to optimize the fuel mixture in the core plasma. A maximum beam power of 39.6 megawatts has been injected, and deuterium-tritium fusion power production has reached 10.7 megawatts, achieving central fusion power densities comparable to or greater than those expected for the International Thermonuclear Reactor, and allowing the first studies of fusion-produced alpha particle behavior in reactor grade plasmas. Energy confinement in deuterium-tritium plasmas is better than in similar deuterium plasmas for most plasma regimes. Innovative techniques to manipulate the plasma current and pressure profiles are permitting studies of enhanced confinement regimes.

Authors:
; ; ; ; ;
Publication Date:
Research Org.:
Princeton Univ., Plasma Physics Lab., NJ (United States)
Sponsoring Org.:
USDOE Office of Energy Research, Washington, DC (United States)
OSTI Identifier:
663169
Report Number(s):
CONF-961110-32; PPPL-CFP-3691
ON: DE97005303; TRN: 99:000001
DOE Contract Number:  
AC02-76CH03073
Resource Type:
Conference
Resource Relation:
Conference: 14. international conference on the application of accelerators in research and industry, Denton, TX (United States), 6-9 Nov 1996; Other Information: PBD: [1996]
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION; TFTR TOKAMAK; D-T OPERATION; BEAM INJECTION HEATING; THERMONUCLEAR FUELS; THERMONUCLEAR REACTOR FUELING; TRITIUM RECOVERY; MAINTENANCE; PERFORMANCE

Citation Formats

Grisham, L R, Kamperschroer, J H, O`Connor, T, Oldaker, M, Stevenson, T, and Von Halle, A. Experience with deuterium-tritium plasmas heated by high power neutral beams. United States: N. p., 1996. Web.
Grisham, L R, Kamperschroer, J H, O`Connor, T, Oldaker, M, Stevenson, T, & Von Halle, A. Experience with deuterium-tritium plasmas heated by high power neutral beams. United States.
Grisham, L R, Kamperschroer, J H, O`Connor, T, Oldaker, M, Stevenson, T, and Von Halle, A. 1996. "Experience with deuterium-tritium plasmas heated by high power neutral beams". United States. https://www.osti.gov/servlets/purl/663169.
@article{osti_663169,
title = {Experience with deuterium-tritium plasmas heated by high power neutral beams},
author = {Grisham, L R and Kamperschroer, J H and O`Connor, T and Oldaker, M and Stevenson, T and Von Halle, A},
abstractNote = {The Tokamak Fusion Test Reactor has operated since November of 1993 with a deuterium-tritium fuel mixture for selected discharges. The majority of the tritium has been introduced as energetic neutral atoms of up to 120 keV injected by the neutral beam systems, with some of the twelve ion sources run on pure tritium and some on deuterium to optimize the fuel mixture in the core plasma. A maximum beam power of 39.6 megawatts has been injected, and deuterium-tritium fusion power production has reached 10.7 megawatts, achieving central fusion power densities comparable to or greater than those expected for the International Thermonuclear Reactor, and allowing the first studies of fusion-produced alpha particle behavior in reactor grade plasmas. Energy confinement in deuterium-tritium plasmas is better than in similar deuterium plasmas for most plasma regimes. Innovative techniques to manipulate the plasma current and pressure profiles are permitting studies of enhanced confinement regimes.},
doi = {},
url = {https://www.osti.gov/biblio/663169}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1996},
month = {12}
}

Conference:
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