Mode Conversion Heating and Current Drive Experiments in TFTR

Majeski, R.; Rogers, J. H.; Batha, S. H.; Budny, R.; Fredrickson, E. D.; Grek, B.; Hill, K. W.; Hosea, J.; LeBlanc, B.; Levinton, F. M.; Murakami, M.; Phillips, C. K.; Ramsey, A. T.; Schilling, G.; Taylor, G.; Wilson, J. R.; Zarnstorff, M. C.

doi:10.1103/physrevlett.76.764

Cited by 52 publications

(63 citation statements)

References 18 publications

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“…With a transmitter frequency of 20 MHz (the lowest practical frequency for the existing PPPL sources), on axis heating can be obtained at central magnetic fields as low as 1.3T. Localized electron heating can be produced in H- 3 He for a wide range of species mixes and wavenumbers. However, ion heating is predicted for low concentrations of either hydrogen (light ion minority) or helium (heavy ion minority).…”

Section: Mode Conversion In H-3 Hementioning

confidence: 99%

Section: Mode Conversion Heatingmentioning

confidence: 99%

“…Efficient, localized electron heating using mode conversion was demonstrated in TFTR [3], and more recently has been extensively utilized in C-MOD [4]. In tokamaks, a low field side launch of the fast wave in D- 3 He has now been most commonly employed. Mode conversion with a high field side launch, which is efficient with a wider variety of ion species mixes, has now been utilized successfully in stellarators, notably CHS [5].…”

Section: Mode Conversion Heatingmentioning

confidence: 99%

“…However, ion heating is predicted for low concentrations of either hydrogen (light ion minority) or helium (heavy ion minority). In Figure 2 (a -c) power deposition profiles for mode conversion in varying H- 3 He mixes are shown. Fig.…”

Section: Mode Conversion In H-3 Hementioning

confidence: 99%

“…The most promising and flexible ion system for mode conversion heating in NCSX is H - 3 He, which should permit localized ion or electron heating (or electron current drive), either on or off axis. With a transmitter frequency of 20 MHz (the lowest practical frequency for the existing PPPL sources), on axis heating can be obtained at central magnetic fields as low as 1.3T.…”

Section: Mode Conversion In H-3 Hementioning

confidence: 99%

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Mode conversion heating scenarios for the National Compact Stellarator experiment

Majeski¹,

Wilson²,

Zarnstorff³

2001

AIP Conference Proceedings

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Radio frequency heating scenarios for the National Compact Stellarator eXperiment (NCSX) are considered. The focus here is on mode conversion from the fast to the slow ion Bernstein wave as either an electron or "bulk" ion heating technique, using a high-field side launch to directly access the ion-ion hybrid layer. Modeling for the planned parameters of NCSX (R ave~1 .4 m, a ave~0 .4 m, B T (0)~1.2-2T, n e (0)~2-5×10 19 m -3 , T e (0)~T i (0)~1-2 keV) for mode conversion in D-H and D-3 He plasmas is presented. Possible types of high-field side antennas are also briefly discussed.

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Section: Mode Conversion In H-3 Hementioning

confidence: 99%

Section: Mode Conversion Heatingmentioning

confidence: 99%

Section: Mode Conversion Heatingmentioning

confidence: 99%

Section: Mode Conversion In H-3 Hementioning

confidence: 99%

Section: Mode Conversion In H-3 Hementioning

confidence: 99%

See 3 more Smart Citations

Mode conversion heating scenarios for the National Compact Stellarator experiment

Majeski¹,

Wilson²,

Zarnstorff³

2001

AIP Conference Proceedings

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Plasma wall interaction and tritium retention in TFTR

Skinner

Amarescu

Ascione

et al. 1997

Journal of Nuclear Materials

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Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. AbstractThe Tokamak Fusion Test Reactor (TFTR) has been operating safely and routinely with deuterium-tritium fuel for more than two years. In this time, TFTR has produced an impressive number of record breaking results including core fusion power, -2 MW/m3, comparable to that expected for ITER. Advances in wall conditioning via lithium pellet injection have played an essential role in achieving these results.Deuterium-tritium operation has also provided a special opportunity to address the issues of tritium recycling and retention. Tritium reten tion over two years of operation was approximately 40%. Recently the in-torus tritium inventory was reduced by half through a combination of glow discharge cleaning, moist-air soaks, and plasma discharge cleaning. The tritium inventory is not a constraint in continued operations. We present recent results from TFTR in the context of plasma wall interactions and deuterium-tritium issues.

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First experiments on ICRF discharge generation by a W7-X-like antenna in the Uragan-2M stellarator

Moiseenko

Kovtun

Wauters³

et al. 2020

J. Plasma Phys.

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In support of the ICRF experiments planned on the Wendelstein 7-X (W7-X) stellarator, i.e. fast ion generation, wall conditioning, target plasma production and heating, a first experimental study on plasma production has been made in the Uragan-2M (U-2M) stellarator using W7-X-like two-strap antenna. In all the experiments, antenna monopole phasing was used. The W7-X-like antenna operation with launched radiofrequency power of ~100 kW have been performed in helium (p = (4–14) × 10−2 Pa) with the vacuum vessel walls pre-loaded with hydrogen. Production of plasma with a density higher than 1012 cm−3 was observed near the first harmonic of the hydrogen cyclotron frequency. Operation at first hydrogen harmonic is feasible in W7-X future ICRF experiments.

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Mode Conversion Heating and Current Drive Experiments in TFTR

Cited by 52 publications

References 18 publications

Mode conversion heating scenarios for the National Compact Stellarator experiment

Mode conversion heating scenarios for the National Compact Stellarator experiment

Plasma wall interaction and tritium retention in TFTR

First experiments on ICRF discharge generation by a W7-X-like antenna in the Uragan-2M stellarator

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