1995
DOI: 10.1088/0029-5515/35/12/i02
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Overview of DT results from TFTR

Abstract: Experiments with plasmas having nearly equal concentrations of deuterium and tritium have been carried out on TFTR. To date (September 1995), the maximum fusion power has been 10.7 MW, using 39.5 MW of neutral beam heating, in a supershot discharge and 6.7 MW in a high /3, discharge following a current ramp-down. The fusion power density in the core of the plasma has reached 2.8 MW/m3, exceeding that expected in the International Thermonuclear Experimental Reactor (ITER). The energy confinement time 7E is obse… Show more

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Cited by 46 publications
(17 citation statements)
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“…To date, no 'anomalous' alpha particle losses due to alpha-driven collective instabilities have be observed in TFTR NBI-heated D-T discharges without ICRH [24,27]. This fact supports the expectation of classical ion behavior for the PCX alpha and triton measurements reported in this paper.…”
Section: Discussionsupporting
confidence: 88%
“…To date, no 'anomalous' alpha particle losses due to alpha-driven collective instabilities have be observed in TFTR NBI-heated D-T discharges without ICRH [24,27]. This fact supports the expectation of classical ion behavior for the PCX alpha and triton measurements reported in this paper.…”
Section: Discussionsupporting
confidence: 88%
“…For discharges in which the reactivity is enhanced due to non-thermal reactions, the ratio of PDT/PDD also decreases for Ti above 15 keV. Experimentally in high performance supershots on TFTR, the ratio of PDT/PDD is -115 if plasmas with the same stored energy are compared (Bell et al, 1994;McGuire et al, 1996;Bell et al, 1996). This ratio is especially relevant if the stored energy is constrained by P-limiting disruptions.…”
Section: Fusion Power Productionmentioning
confidence: 99%
“…Another practical consideration is that the ratio of n d n T is determined not only by the ratios of the beam fueling rate, P dp b, but also by the recycling and influx of hydrogenic species from T D plasma facing components (Bell et al, 1994). A striking result of the TFTR experiments was the low level of tritium recycling at the limiters.…”
Section: Page 34mentioning
confidence: 99%
“…Some of the early tokamaks used this configuration, including the Tokamak Fusion Test Reactor (TFTR), which was an experimental tokamak built at Princeton Plasma Physics Laboratory (in Princeton, New Jersey) around 1980 and produced 10.7 MW of nuclear fusion power in 1995 [10]. The disadvantage of the limiter configuration is that the interaction with the vessel wall occurs near to the core of the plasma.…”
Section: Magnetic Confinement In Tokamaksmentioning
confidence: 99%