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Your search keyword '"Goodman T.P."' showing total 193 results
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193 results on '"Goodman T.P."'

155. ECRH and ECCD Physics in the TCV Tokamak

Author

Alberti, S., Arnoux, G., Blanchard, P., Camenen, Y., Coda, S., Goodman, T.P., Henderson, M., Hogge, J.P., Moret, J.-M., Nelson-Melby, E., Nikkola, P., Pochelon, A., Porte, L., Sauter, O., and Tran, M.Q.

156. Physics insight from plasma shaping experiments in the TCV tokamak

Author

Pochelon, A., Bortolon, A., Camenen, Y., Duval, B.P., Marinoni, A., Reimerdes, H., Scarabosio, A., Alberti, S., Angioni, C., Behn, R., Bottino, A., Brunner, S., Coda, S., Daouk, K., Fasoli, A., Furno, I., Goodman, T.P., Graves, J., Henderson, M.A., and Hof, F.

157. A revised ITER EC system baseline design proposal

Author

Henderson, M.A., Alberti, S., Chavan, R., Fasel, D., Goodman, T.P., Pagonakis, I.Gr., Sauter, O., Siravo, U., Udintsev, V.S., Zucca, C., Saibene, G., Albajar, F., Bonicelli, T., Cirant, S., Farina, D., Ramponi, G., Heidinger, R., Piosczyk, B., and Thumm, M.

158. Recent results from the EC heated plasmas in the TCV tokamak

Author

Henderson, M.A., Alberti, S., Angioni, C., Arnoux, G., Behn, R., Blanchard, P., Bosshard, P., Camenen, Y., Coda, S., Condrea, I, Goodman, T.P., Hofmann, F., J.-Ph., Hogge, Karpushov, A., Manini, A., Martynov, An., Moret, J.M., and Nikkola, P.

169. An ITER relevant evacuated waveguide transmission system for the JET-EP ECRH project

Author

Henderson, M., Alberti, S., Bird, J., Doane, J., Elendoern, B., Flemming, C., Goodman, T.P., Hoekzena, F., Hogge, J.-P., MacMillan, G., Magnin, J.-C., Pioscyk, B., Porte, L., Tran, M.Q., and Verhoeven, A.G.A.

Subjects
LRP 736, JET, ITER
Abstract

An over-moded evacuated waveguide line was chosen for use in the transmission system for the proposed JET enhanced performance project (JET-EP) electron cyclotron resonance heating (ECRH) system. A comparison between the quasi-optical, atmospheric waveguide and evacuated waveguide systems was performed for the project with a strong emphasis placed on the technical and financial aspects. The evacuated waveguide line was chosen as the optimal system in light of the above criteria. The system includes six lines of 63.5 mm waveguide for transmitting 6.0 MW(10 s) at 113.3 GHz from the gyrotrons to the launching antenna. The designed lines are on average 72 m in length and consist of nine mitre bends, for an estimated transmission efficiency of similar to90%. Each line is designed to include an evacuated switch leading to a calorimetric load, two do breaks, two gate valves, one pumpout tee, a power monitor mitre bend and a double-disc CVD window near the torus. The location of waveguide support is positioned to minimize the power converted to higher-order modes from waveguide sagging and misalignment. The two gate valves and CVD window are designed to be used as tritium barriers at the tot-us and between the J1T and J1D buildings. The last leg of the waveguide leading to the torus has to be designed to accommodate the torus movement during disruptions and thermal cycles. All lines are also designed to be compatible with the ITER ECRH system operating at 170 GHz.

174. Preliminary confinement studies during ECRH in TCV

Author

Pochelon, A., Pietrzyk, Z.A., Goodman, T.P., Henderson, M.A., Reimerdes, H., M.Q., Tran, Behn, R., Coda, S., Dutch, M.J., Duval, B.P., Furno, I., Hofmann, F., J.Ph., Hogge, Lister, J.B., Martin, Y., Moret, J.M., Nieswand, C., Rommers, J., and Sauter, O.

185. The Physics of Electron Internal Transport Barriers in the TCV Tokamak

Author

Coda, S., Asp, E., Fable, E., Goodman, T.P., Sauter, O., Udintsev, V.S., Behn, R., Henderson, M.A., Marinoni, A., Turri, G.P., and Zucca, C.

Abstract

Electron internal transport barriers (elTBs) are generated in the TCV tokamak with strong electron cyclotron resonance heating in a variety of conditions, ranging from steady-state fully noninductive scenarios to stationary discharges with a finite inductive component and finally to transient current ramps without current drive. The confinement improvement over L-mode ranges from 3 to 6; the bootstrap current fraction is invariably large and is above 70% in the highest confinement cases, with good current profile alignment permitting the attainment of steady state. Barriers are observed both in the electron temperature and density profiles, with a strong correlation both in location and in steepness. The dominant role of the current profile in the formation and properties of elTBs has been conclusively proven in a TCV experiment exploiting the large current drive efficiency of the Ohmic transformer: small current perturbations accompanied by negligible energy transfer dramatically alter the confinement. The crucial element in the formation of the barrier is the appearance of a central region of negative magnetic shear, with the barrier strength improving with increasingly steep shear. This connection has also been corroborated by transport modelling assisted by gyrofluid simulations. Rational safety-factor (q) values do not appear to play a role in the barrier formation, at least in the q range 1.3-2.3, as evidenced by the smooth dependence of the confinement enhancement on the loop voltage over a broad elTB database. MHD mode activity is however influenced by rational q values and results in a complex, sometimes cyclic, dynamic evolution.

189. Real Time Control of Plasmas and ECRH Systems on TCV

Author

Paley, J.I., Felici, F., Berrino, J., Coda, S., Cruz, N., Duval, B.P., Goodman, T.P., Martin, Y., Moret, J.-M., Piras, F., Rodrigues, A.P., Santos, B., Varandas, C.A.F., and TCV team

Subjects
Position Control, Current Drive, Tokamak, Ech, Shape, Fully Noninductive Operation

193. Real Time Control of EC Heating & Current Drive Systems on TCV

Author

Paley, J.I., Felici, F., Curchod, L., Coda, S., Goodman, T.P., and Control Systems Technology

Subjects
profile, fusion, real time, sawtooth, launchers, control, ECRH
Abstract

The ability to control, in real time, the electron cyclotron heating & current drive systems for the control of MHD instabilities is particularly important for large tokamaks operating at high performance. Several algorithms have been developed and tested on TCV to explore possible control techniques, first in simple experiments to control the plasma current and elongation and subsequently in experiments to control the sawtooth instability and profile parameters. A summary of these experiments are presented in this paper together with the application of the break-in-slope technique as a possible real time calculation of the location of EC deposition.

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