Experiments on TFTR supershot plasmas

Strachan, J.; Bell, M.G.; Janos, A.; Kaye, S. M.; Kilpatrick, S. J.; Manos, D. M.; Mansfield, D. K.; Mueller, D.; Owens, Kevin G.; Pitcher, C. S.; Snipes, J. A.; Timberlake, J.

doi:10.1016/s0022-3115(06)80008-5

Cited by 26 publications

(20 citation statements)

References 10 publications

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“…. 108 15 Energy dependence of the erosion yield of carbon by deuterium ions at room temperature (open symbols) and at the maximum temperature for chemical erosion, T max , (solid symbols) (see Fig. 14).…”

Section: Plasma-edge and Plasma-materials Interaction Issues In Next-smentioning

confidence: 99%

“…In TFTR the ratio of D α to C-II emission (see glossary) was used during supershot conditioning as a convenient measure of wall conditions [108] (Fig. 56).…”

Section: (January 2001)mentioning

confidence: 99%

“…Many machines have expanded graphite coverage to include virtually all of the vacuum vessel wall, in addition to the limiter/divertor plates (e.g., DIII-D [105]). In some cases, the inner wall is used as a large area limiter, and such structures, if carefully constructed, are able to handle enormous power loads, greatly exceeding the power limits of divertor plates (e.g., TFTR [106][107][108]). …”

mentioning

confidence: 99%

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Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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The major increase in discharge duration and plasma energy in a next step DT fusion reactor will give rise to important plasma-material effects that will critically influence its operation, safety and performance. Erosion will increase to a scale of several centimetres from being barely measurable at a micron scale in today's tokamaks. Tritium co-deposited with carbon will strongly affect the operation of machines with carbon plasma facing components. Controlling plasma-wall interactions is critical to achieving high performance in present day tokamaks, and this is likely to continue to be the case in the approach to practical fusion reactors. Recognition of the important consequences of these phenomena stimulated an internationally co-ordinated effort in the field of plasma-surface interactions supporting the Engineering Design Activities of the International Thermonuclear Experimental Reactor project (ITER), and significant progress has been made in better understanding these issues. The paper reviews the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next step fusion reactors. Two main topical groups of interaction are considered: (i) erosion/redeposition from plasma sputtering and disruptions, including dust and flake generation and (ii) tritium retention and removal. The use of modelling tools to interpret the experimental results and make projections for conditions expected in future devices is explained. Outstanding technical issues and specific recommendations on potential R&D avenues for their resolution are presented.

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Section: Plasma-edge and Plasma-materials Interaction Issues In Next-smentioning

confidence: 99%

“…In TFTR the ratio of D α to C-II emission (see glossary) was used during supershot conditioning as a convenient measure of wall conditions [108] (Fig. 56).…”

Section: (January 2001)mentioning

confidence: 99%

mentioning

confidence: 99%

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Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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“…. This lower density rise in NSTX is attributed to the more effective removal of absorbed deuterium in the walls, and the subsequent reduction in recycling, due to the intense and energetic wall conditioning of the He conditioning discharge as compared to that of the only applying HeGDC as was also found on TFTR [9]. We intend to investigate if this result is due to the GDC geometry.…”

Section: Comparison Of Applying Hegdc Between Discharges and Helium Dmentioning

confidence: 91%

Development of NSTX Particle Control Techniques

Kugel

Maingi

Bell

et al. 2004

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NSTX High Harmonic Fast Wave (HHFW) current drive discharges will require density control for acceptable efficiency. In NSTX, this involves primarily controlling impurity influxes and recycling. We have compared boronization on hot and cold surfaces, varying helium glow discharge conditioning (HeGDC) durations, helium discharge cleaning, brief daily boronization, and between discharge boronization to reduce and control spontaneous density rises. Access to Ohmic H-modes was enabled by boronization on hot surfaces, however, the duration of the effectiveness of hot and cold boronization was comparable. A 15 min HeGDC between discharges was needed for reproducible L-H transitions. He discharge conditioning yielded slower density rises than 15 min of HeGDC. Brief daily boronization followed by a comparable duration of applied HeGDC restored and enhanced good conditions. Additional brief boronizations between discharges did not improve plasma performance (reduced recycling, reduced impurity luminosities, earlier L-H transitions, longer plasma current flattops, higher stored energies) if conditions were already good.Between discharge boronization required increases in the NSTX duty cycle due to the need for additional HeGDC to remove codeposited D.

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“…The reduced Dα emission would correlate with a confinement improvement of 10% under the normal supershot scaling. [13] Improvements in energy confinement in tokamaks have recently been associated with the formation of flow shear layers which suppress the turbulence responsible for anomalous transport [14]. In this context, it should be noted that the poloidal velocity v θ of carbon impurities about 15 cm inside the last closed flux surface increased from 1 km/s to 5Êkm/s just after the Xe puff.…”

Section: Thermal Transport Experimentsmentioning

confidence: 99%

Highly Radiative Plasmas for Local Transport Studies and Power and Particle Handling in Reactor Regimes

Bell¹,

Bell²,

Budny³

et al. 1998

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To study the applicability of artificially enhanced impurity radiation for mitigation of the plasma-limiter interaction in reactor regimes, krypton and xenon gases were injected into TFTR supershots and high-l i plasmas. At neutral beam injection (NBI) powers P B ³ 30ÊMW, carbon influxes (blooms) were suppressed, leading to improved energy confinement and neutron production in both D and DT plasmas, and the highest DT fusion energy production (7.6ÊMJ) in a TFTR pulse. Comparisons of the measured radiated power profiles with predictions of the MIST impurity transport code have guided studies of highly-radiative plasmas in ITER. The response of the electron and ion temperatures to greatly increased radiative losses from the electrons was used to study thermal transport mechanisms.

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Experiments on TFTR supershot plasmas

Cited by 26 publications

References 10 publications

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

Development of NSTX Particle Control Techniques

Highly Radiative Plasmas for Local Transport Studies and Power and Particle Handling in Reactor Regimes

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