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ICRF heating and transport of deuterium-tritium plasmas in TFTR
[report]
1995
unpublished
This paper describes results of the first experiments utilizing high-power ion cyclotron range of frequency (ICRF) to heat deuterium-tritium (D-T) plasmas in reactor-relevant regimes on the Tokamak Fusion Test Reactor (TFTR). Results from these experiments have Qo Q5 11) MINOR RADIUS, r/a J w MURAKAMI 5
doi:10.2172/10115936
fatcat:cdtf3stiobei5ma6sv5zgxau6e