DT simulation of ICRF heated supershots in TFTR using TRANSP
Conference
·
OSTI ID:10169135
- Oak Ridge National Lab., TN (United States)
- Princeton Univ., NJ (United States). Plasma Physics Lab.
The principal goal of ion cyclotron range of frequency (ICRF) heating on the Tokamak Fusion Test Reactor (TFTR) is to enhance plasma performance during the deuterium-tritium (DT) physics phase of operations. Strongly centralized ICRF heating may play a critical role in obtaining high Q{sub DT} and high {beta}{sub {alpha}} operation in TFTR, as well as in future fusion reactors. ICRF heating of a dilute minority species leads to the formation of an energetic ion population that, in turn, provides strong central electron heating. The corresponding rise in the central electron temperature translates into an increase in the slowing-down time of either neutral beam or alpha particles in the discharge. Preliminary DT simulations of the experimental results in deuterium-deuterium (DD) plasmas performed with the TRANSP code are presented in this paper.
- Research Organization:
- Oak Ridge National Lab., TN (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 10169135
- Report Number(s):
- CONF-9304112--19; ON: DE93015817
- Country of Publication:
- United States
- Language:
- English
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