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1. SiC as a core-edge integrated wall solution in DIII-D

Author

S. Zamperini, T. Abrams, J. Nichols, E. Unterberg, A. Lasa, P. Stangeby, S. Bringuier, D. Rudakov, and J.D. Elder

Subjects
nuclear fusion, DIII-D, impurity transport, silicon carbide, wall conditioning, DIVIMP, Nuclear engineering. Atomic power, TK9001-9401
Abstract

Silicon carbide (SiC) is a promising material for use in a fusion reactor due to its low hydrogenic diffusivity, high temperature strength and resilience under neutron irradiation [1,2]. To assess SiC as a main wall material in DIII-D, simulations with TRIM.SP and DIVIMP are performed on a well-diagnosed L-mode discharge. The effective charge, Zeff, across the separatrix is used as a figure of merit in comparing SiC to the current graphite walls. It is found that SiC is expected to reduce Zeff, potentially by as much as ∼50 %. It is discussed how SiC may be expected to “self-condition” and create wall conditions similar to siliconization, further lowering Zeff due to efficient oxygen gettering. The potential benefits are reviewed and a path towards SiC walls in DIII-D is presented.

Published
2023
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2. DIII-D research to provide solutions for ITER and fusion energy

Author

C.T. Holcomb, for the DIII-D Team:, J. Abbate, A. Abe, A. Abrams, P. Adebayo-Ige, S. Agabian, S. Ahmed, N. Aiba, N. Akcay, T. Akiyama, R. Albosta, P. Aleynikov, S. Allen, H. Anand, J. Anderson, Y. Andrew, M. Ashburn, A. Ashourvan, M. Austin, G. Avdeeva, D. Ayala, M. Ayub, E. Bagdy, S. Banerjee, K. Barada, L. Bardoczi, O. Bardsley, J. Barr, E. Bass, A. Battey, Z. Bayler, L. Baylor, T. Bechtel, M. Beidler, E. Belli, T. Benedett, Z. Bergstrom, M. Berkel, T. Bernard, N. Bertelli, R. Bielajew, G. Bodner, J. Boedo, R. Boivin, T. Bolzonella, P. Bonoli, A. Bortolon, S. Bose, M. Boyer, W. Boyes, L. Bradley, R. Brambila, A. Braun, D. Brennan, S. Bringuier, L. Brodsky, M. Brookman, J. Brooks, D. Brower, W. Brown, J. Buck, S. Buczek, D. Burgess, M. Burke, K. Burrell, J. Butt, R. Buttery, I. Bykov, P. Byrne, A. Cacheris, K. Callahan, J. Callen, D. Campbell, J. Candy, J. Canik, L. Cappelli, T. Carlstrom, R. Carr, W. Carrig, B. Carter, T. Carter, I. Carvalho, W. Cary, L. Casali, L. Ceelen, M. Cengher, M. Cha, R. Chaban, V. Chan, B. Chapman, I. Char, J. Chen, R. Chen, X. Chen, Y. Chen, J. Chiriboga, E. Cho, G. Choi, W. Choi, H. Choudhury, S. Chowdhury, C. Chrystal, Y. Chung, R. Churchill, R. Clark, M. Clement, J. Coburn, S. Coda, R. Coffee, C. Collins, J. Colmenares-Fernandez, W. Conlin, R. Coon, T. Cote, A. Creely, N. Crocker, C. Crowe, B. Crowley, T. Crowley, M. Curie, D. Curreli, A. Dal Molin, J. Damba, E. Dart, A. Dautt-Silva, K. Davda, A. De, N. de Boucaud, Y. de Jong, P. DE VRIES, A. de-Villeroche, G. DeGrandchamp, J. deGrassie, D. Demers, S. Denk, E. DeShazer, S. Di Genova, A. Diallo, A. Dimits, R. Ding, S. Ding, D. Donovan, X. Du, J. Dunsmore, A. Dupuy, J. Duran, A. Dvorak, F. Effenberg, N. Eidietis, D. Elder, D. Eldon, Y. Elsey, D. Ennis, K. Erickson, D. Ernst, M. Fajardo, H. Farre-Kaga, M. Fenstermacher, N. Ferraro, J. Ferron, A. Feyrer, P. Fimognari, R. Finden, D. Finkenthal, R. Fitzpatrick, S. Flanagan, B. Ford, W. Fox, S. Freiberger, L. Fu, K. Gage, V. Gajaraj, I. Garcia, F. Garcia, A. Garcia, M. Garcia Munoz, D. Garnier, A. Garofalo, A. Gattuso, B. Geiger, K. Gentle, Y. Ghai, K. Gill, F. Glass, P. Gohil, X. Gong, J. Gonzalez-Martin, Y. Gorelov, V. Graber, R. Granetz, C. Gray, C. Greenfield, B. Grierson, R. Groebner, W. Grosnickle, M. Groth, S. Gu, H. Guo, J. Guterl, W. Guttenfelder, R. Hager, S. Hahn, M. Halfmoon, J. Hall, V. Hall-Chen, F. Halpern, G. Hammett, X. Han, C. Hansen, E. Hansen, J. Hanson, M. Hanson, A. Harris, R. Harvey, S. Haskey, D. Hatch, W. Hayashi, A. Hayes, W. Heidbrink, J. Herfindal, J. Hicok, E. Hinson, T. Hisakado, C. Holcomb, C. Holland, L. Holland, E. Hollmann, A. Holm, I. Holmes, K. Holtrop, R. Hong, R. Hood, L. Horvath, S. Houshmandyar, N. Howard, E. Howell, W. Hu, Y. Hu, Q. Hu, Y. Huang, J. Huang, A. Huang, A. Hubbard, J. Hughes, D. Humphreys, J. Hurtado, A. Hyatt, K. Imada, V. Izzo, A. Jalalvand, S. Jardin, A. Jarvinen, Y. Jeon, H. Ji, X. Jian, L. Jian, Y. Jiang, C. Johnson, J. Johnson, M. Jones, S. Joung, P. Jouzdani, E. Jung, E. Kallenberg, R. Kalling, D. Kaplan, A. Kaptanoglu, D. Kellman, J. Kennedy, F. Khabanov, J. Kim, H. Kim, E. Kim, S. Kim, K. Kim, C. Kim, T. Kim, J. King, A. Kinsey, D. Kirk, D. Klasing, A. Kleiner, M. Knolker, M. Kochan, B. Koel, J. Koenders, M. Koepke, R. Kolasinski, E. Kolemen, E. Kostadinova, M. Kostuk, G. Kramer, R. Kube, N. Kumar, R. La Haye, F. Laggner, C. Lahban, H. Lan, R. Landry, R. Lantsov, L. Lao, C. Lasnier, C. Lau, R. Leccacorvi, J. Leddy, M. Lee, S. Lee, K. Lee, R. Lee, M. Lehnen, A. Leonard, E. Leppink, M. LeSher, J. Lestz, J. Leuer, N. Leuthold, G. Li, X. Li, Y. Li, L. Li, N. Li, Z. Li, D. Lin, Z. Lin, Y. Lin, E. Linsenmayer, J. Liu, D. Liu, C. Liu, Z. Liu, Y. Liu, A. Loarte-Prieto, S. Loch, L. LoDestro, N. Logan, J. Lohr, J. Lore, U. Losada Rodriguez, J. Loughran, M. Lowell, T. Luce, N. Luhmann, P. Lunia, R. Lunsford, L. Lupin-Jimenez, A. Lvovskiy, B. Lyons, X. Ma, J. MacDonald, T. Macwan, R. Maingi, M. Major, L. Malhotra, M. Margo, C. Marini, A. Marinoni, A. Maris, E. Martin, J. Mateja, R. Mattes, R. Maurizio, D. Mauzey, L. McAllister, G. McArdle, J. McClenaghan, K. McCollam, G. McKee, K. McLaughlin, A. McLean, V. Mehta, E. Meier, S. Meitner, J. Menard, O. Meneghini, G. Merlo, S. Messer, W. Meyer, C. Michael, D. Miller, M. Miller, J. Mitchell, E. Mitra, C. Moeller, M. Mohamed, S. Molesworth, K. Montes, S. Mordijck, S. Morosohk, A. Moser, D. Mueller, S. Munaretto, C. Murphy, C. Muscatello, R. Myers, A. Nagy, D. Nath, M. Navarro, R. Nazikian, T. Neiser, A. Nelson, P. Nesbet, F. Nespoli, P. Nguyen, D. Nguyen, R. Nguyen, J. Nichols, M. Nocente, L. Nuckols, R. Nygren, T. Odstrcil, M. Okabayashi, E. Olofsson, D. Orlov, D. Orozco, N. Osborne, T. Osborne, F. OShea, D. Pace, D. Packard, A. Pajares Martinez, C. Pakosta, C. Pan, M. Pandya, D. Panici, A. Pankin, Y. Park, J. Park, C. Parker, S. Parker, P. Parks, M. Parsons, S. Paruchuri, C. Paz-Soldan, T. Pederson, W. Peebles, B. Penaflor, E. Perez, L. Periasamy, R. Perillo, C. Petty, M. Pharr, D. Pierce, C. Pierren, S. Pierson, A. Pigarov, L. Pigatto, D. Piglowski, S. Pinches, R. Pinsker, R. Pitts, J. Pizzo, M. Podesta, Z. Popovic, M. Porkolab, Q. Pratt, G. Prechel, I. Pusztai, P. Puthan-Naduvakkate, J. Qian, X. Qin, O. Ra, T. Raines, K. Rakers, K. Rath, J. Rauch, C. Rea, R. Reed, A. Reiman, M. Reinke, R. Reksoatmodjo, Q. Ren, J. Ren, Y. Ren, M. Rensink, T. Rhodes, N. Richner, J. Ridzon, G. Riggs, J. Riquezes, P. Rodriguez Fernandez, T. Rognlien, G. Ronchi, L. Rondini, R. Rosati, A. Rosenthal, M. Ross, J. Rost, A. Rothstein, J. Roveto, J. Ruane, D. Rudakov, R. Rupani, G. Rutherford, S. Sabbagh, J. Sachdev, N. Sadeghi, A. Salmi, F. Salvador, B. Sammuli, C. Samuell, A. Sandorfi, C. Sang, D. Santa, J. Sarff, O. Sauter, H. Savelli, C. Schaefer, H. Schamis, J. Schellpfeffer, D. Schissel, L. Schmitz, O. Schmitz, P. Schroeder, K. Schultz, E. Schuster, F. Sciortino, F. Scotti, J. Scoville, A. Seltzman, J. Seo, J. Serrano, I. Sfiligoi, M. Shafer, R. Shapov, H. Shen, N. Shi, D. Shiraki, B. Short, R. Shousha, H. Si, C. Sierra, G. Sinclair, P. Sinha, G. Sips, C. Skinner, T. Slendebroek, J. Slief, R. Smirnov, S. Smith, D. Smith, G. Snoep, P. Snyder, W. Solomon, X. Song, A. Sontag, V. Soukhanovskii, D. Spong, J. Squire, G. Staebler, L. Stagner, T. Stange, P. Stangeby, E. Starling, S. Stewart, T. Stoltzfus-Dueck, S. Storment, E. Strait, D. Su, L. Sugiyama, P. Sun, Y. Sun, X. Sun, C. Sung, W. Suttrop, Y. Suzuki, R. Sweeney, B. Taczak, Y. Takemura, S. Tang, W. Tang, G. Tardini, D. Taussig, K. Teixeira, K. Thackston, D. Thomas, K. Thome, Y. Tinguely, M. Tobin, J. Tooker, A. Torrezan de Sousa, P. Traverso, G. Trevisan, E. Trier, D. Truong, C. Tsui, F. Turco, A. Turnbull, L. Turner, E. Unterberg, B. Van Compernolle, R. van Kampen, M. Van Zeeland, B. Victor, R. Vieira, E. Viezzer, S. Vincena, D. Vollmer, J. Wai, M. Walker, R. Waltz, W. Wampler, L. Wang, Y. Wang, H. Wang, Z. Wang, G. Wang, A. Wang, J. Watkins, M. Watkins, T. Watts, L. Webber, K. Weber, W. Wehner, X. Wei, D. Weisberg, A. Welander, A. Welsh, A. White, R. Wilcox, G. Wilkie, T. Wilks, M. Willensdorfer, H. Wilson, A. Wingen, M. Wu, D. Wu, S. Wukitch, J. Xia, R. Xie, Z. Xing, G. Xu, X. Xu, Z. Yan, X. Yang, L. Yang, S. Yang, J. Yang, M. Yoo, G. YU, J. Yu, A. Zalzali, A. Zamengo, V. Zamkovska, S. Zamperini, K. Zarrabi, E. Zeger, K. Zeller, L. Zeng, X. Zhang, J. Zhang, B. Zhang, B. Zhao, C. Zhao, Y. Zheng, Y. Zhu, J. Zhu, J. Ziegel, J. Zimmerman, and C. Zuniga

Subjects
DIII-D, tokamak, overview, Nuclear and particle physics. Atomic energy. Radioactivity, QC770-798
Abstract

The DIII-D tokamak has elucidated crucial physics and developed projectable solutions for ITER and fusion power plants in the key areas of core performance, boundary heat and particle transport, and integrated scenario operation, with closing the core-edge integration knowledge gap being the overarching mission. New experimental validation of high-fidelity, multi-channel, non-linear gyrokinetic turbulent transport models for ITER provides strong confidence it will achieve Q ⩾ 10 operation. Experiments identify options for easing H-mode access in hydrogen, and give new insight into the isotopic dependence of transport and confinement. Analysis of 2,1 islands in unoptimized low-torque IBS demonstration discharges suggests their onset time occurs randomly in the constant β phase, most often triggered by non-linear 3-wave coupling, thus identifying an NTM seeding mechanism to avoid. Pure deuterium SPI for disruption mitigation is shown to provide favorable slow cooling, but poor core assimilation, suggesting paths for improved SPI on ITER. At the boundary, measured neutral density and ionization source fluxes are strongly poloidally asymmetric, implying a 2D treatment is needed to model pedestal fuelling. Detailed measurements of pedestal and SOL quantities and impurity charge state radiation in detached divertors has validated edge fluid modelling and new self-consistent ‘pedestal-to-divertor’ integrated modeling that can be used to optimize reactors. New feedback adaptive ELM control minimizes confinement reduction, and RMP ELM suppression with sustained high core performance was obtained for the first time with the outer strike point in a W-coated, compact and unpumped small-angle slot divertor. Advances have been made in integrated operational scenarios for ITER and power plants. Wide pedestal intrinsically ELM-free QH-modes are produced with more reactor-relevant conditions, Low torque IBS with W-equivalent radiators can exhibit predator-prey oscillations in T _e and radiation which need control. High- β _P scenarios with q _min > 2, q _95 –7.9, β _N > 4, β _T –3.3% and H _98y2 > 1.5 are sustained with high density ( $\bar n$ = 7E19 m ^−3 , f _G –1) for 6 τ _E , improving confidence in steady-state tokamak reactors. Diverted NT plasmas achieve high core performance with a non-ELMing edge, offering a possible highly attractive core-edge integration solution for reactors.

Published
2024
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3. Dependence of particle and power dissipation on divertor geometry and plasma shaping in DIII-D small-angle-slot divertor

Author

H.Q. Wang, X. Ma, R. Maurizio, H.Y. Guo, D.M. Thomas, J.G. Watkins, M.W. Shafer, A.W. Hyatt, A.L. Moser, J. Ren, A. McLean, F. Scotti, and P. Stangeby

Subjects
Nuclear engineering. Atomic power, TK9001-9401
Abstract

Dedicated experiments in DIII-D find that magnetic shaping and divertor target geometry significantly affect the divertor plasma conditions and divertor detachment process in the small-angle-slot (SAS) divertor. The compact SAS divertor in DIII-D provides a good testbed for understanding the effects of a tightly closed divertor on particle and power dissipation, and for application to core–edge integration solutions. A longer outer leg facilitates the achievement of divertor dissipation in the SAS divertor, while a shorter leg leads to higher electron temperatures near the divertor target plate and requires higher upstream densities to achieve the same level of divertor detachment. In addition, with the ion B × ∇B drift away from the SAS divertor and the outer strike point (OSP) near the outer corner, the target temperature is lower for a particular upstream density than with the OSP on a slanted or flat surface, leading to lower heat flux even when the particle flux remains similar. In contrast, with the ion B × ∇B drift into the SAS divertor, a strike point at the inner slanted surface exhibits a lower upstream density to achieve divertor detachment than a strike point either at the outer corner or the outer slanted target. Experimental results and SOLPS-ITER simulations with full drifts suggest the strong interplay between drift flows and the neutral distribution resulted from target shaping. Furthermore, in-slot gas puffing has been shown to achieve global divertor detachment with an onset density about 10 % lower than that using main-chamber gas puffing when the outer strike point is placed at the inner slanted surface. Corresponding modelling reveals that the local gas puffing enhances the neutral ionization which potentially facilitates the achievement of divertor dissipation. However, such improvement diminishes when the strike point is at the outer corner, which also indicates the geometric dependence on divertor performance in the SAS divertor. Even with different strike point locations, complete divertor detachment with very low particle and heat fluxes at the divertor targets and a high confinement core with normalized energy confinement factor H98 > 1.0 can be simultanesouly achieved with the SAS divertor with ion B × ∇B drift into SAS divertor, demonstrating the benefit of a closed divertor for exploration of core–edge integration.

Published
2022
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4. Transport of tungsten to collector probes in DIII-D

Author

S. Zamperini, D. Donovan, E. Unterberg, P. Stangeby, J. Nichols, J. Duran, D. Elder, A. Neff, D. Rudakov, and M. Zach

Subjects
Nuclear engineering. Atomic power, TK9001-9401
Abstract

Collector probes have long been used to measure impurity fluxes in the scrape off layer (SOL) of tokamaks. In this study, collector probes were inserted in the main SOL of DIII-D during the tungsten Metal Rings Campaign, and the W deposits on the probes were analyzed ex situ using Rutherford backscattering spectrometry analysis to obtain radial profiles of W deposition. A simple picture is hypothesized for how the W transports through the SOL from the target to the two sides of the probe, based on a long-theorized impurity accumulation at the crown (i.e. the top) of the plasma. The patterns observed in the deposition profiles along the probes support the hypothesized picture; however, 3D modeling and further experimental studies are needed to support more definitive conclusions.

Published
2019
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5. Binary segmentation of medical images using implicit spline representations and deep learning

Author

Barrowclough, Oliver J. D., Muntingh, Georg, Nainamalai, Varatharajan, and Stangeby, Ivar

Subjects
Electrical Engineering and Systems Science - Image and Video Processing, Computer Science - Computer Vision and Pattern Recognition, Computer Science - Machine Learning, 68U10, 68T45, I.4.6
Abstract

We propose a novel approach to image segmentation based on combining implicit spline representations with deep convolutional neural networks. This is done by predicting the control points of a bivariate spline function whose zero-set represents the segmentation boundary. We adapt several existing neural network architectures and design novel loss functions that are tailored towards providing implicit spline curve approximations. The method is evaluated on a congenital heart disease computed tomography medical imaging dataset. Experiments are carried out by measuring performance in various standard metrics for different networks and loss functions. We determine that splines of bidegree $(1,1)$ with $128\times128$ coefficient resolution performed optimally for $512\times 512$ resolution CT images. For our best network, we achieve an average volumetric test Dice score of almost 92%, which reaches the state of the art for this congenital heart disease dataset., Comment: 17 pages, 5 figures

Published
2021
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6. A geometrical approach to evaluating the heat flux peaking factor on first wall components

Author

Mitteau, R. and Stangeby, P.

Subjects
Physics - Plasma Physics
Abstract

In magnetic fusion experiments, a simple technique to evaluate the heat flux on first wall components is a key to controlled plasma surface interaction. The heat flux can be characterized by the peaking factor which is the ratio of the peak heat flux to the average heat flux. The peaking factor can be calculated exactly using simple derivations and standard software tools. This analysis is applied to an Iter class experiment for plasma wall contact during start up phases at 15 MW, in idealised, realistic and misaligned situations. Even though the peaking factors are usually above 10, the peak heat load on the wall remains moderate at a few MW/m${}^2$.

Published
2020
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7. Impact of ELM control techniques on tungsten sputtering in the DIII-D divertor and extrapolations to ITER

Author

Abrams, T., Unterberg, E. A., Rudakov, D. L., Leonard, A. W., Schmitz, O., Shiraki, D., Baylor, L. R., Stangeby, P. C., Thomas, D. M., and Wang, H. Q.

Subjects
Physics - Plasma Physics, Physics - Atomic Physics
Abstract

The free-streaming plus recycling model (FSRM) has recently been developed to understand and predict tungsten gross erosion rates from the divertor during edge localized modes (ELMs). In this work, the FSRM was tested against experimental measurements of W sputtering during ELMs, conducted via fast WI spectroscopy. Good agreement is observed using a variety of controlling techniques, including gas puffing, neutral beam heating, and plasma shaping to modify the pedestal stability boundary and thus the ELM behavior. ELM mitigation by pellet pacing was observed to strongly reduce W sputtering by flushing C impurities from the pedestal and reducing the divertor target electron temperature. No reduction of W sputtering was observed during the application of resonant magnetic perturbations (RMPs), in contrast to the prediction of the FSRM. Potential sources of this discrepancy are discussed. Finally, the framework of the FSRM is utilized to predict intra-ELM W sputtering rates in ITER. It is concluded that W erosion during ELMs in ITER will be caused mainly by free-streaming fuel ions, but free-streaming seeded impurities (N or Ne) may increase the erosion rate significantly if present in the pedestal at even the 1% level. Impurity recycling is not expected to cause significant W erosion in ITER due to the very low target electron temperature.

Published
2019
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8. Properties of Spline Spaces Over Structured Hierarchical Box Partitions

Author

Stangeby, Ivar and Dokken, Tor

Subjects
Mathematics - Numerical Analysis, 65N50
Abstract

Given a spline space spanned by Truncated Hierarchical B-splines (THB), it is always possible to construct a spline space spanned by Locally Refined B-splines (LRB) that contains the THB-space. Starting from configurations where the two spline spaces are equal, we adress what happens to the properties of the LRB-space when it is modified by local one-directional refinement at convex corners of, and along edges between dyadic refinement regions. We show that such local modifications can reduce the number of B-splines over each element to the minimum prescribed by the polynomial bi-degree, and that such local refinements can be used for improving the condition numbers of mass and stiffness matrices., Comment: 29 pages, 17 figures. Supmitted to the proceedings of IGAA 2018, (Springer)

Published
2019

9. Measured signatures of low energy, physical sputtering in the line shape of neutral carbon emission

Author

Brooks, NH, Isler, RC, Whyte, DG, Fenstermacher, ME, Groebner, RJ, Stangeby, PC, W.W.Heidbrink, Jackson, GL, Mahdavi, MA, West, WP, and Team, The DIII-D

Subjects
Engineering, Materials Engineering, carbon, helium, impurity sources, spectroscopy, sputtering, Energy, Materials engineering
Abstract

The most important mechanisms for introducing carbon into the DIII-D divertors [J.L. Luxon, Nucl. Fusion 42 (2002) 614] are physical and chemical sputtering. Previous investigations have indicated that operating conditions where one or the other of these is dominant can be distinguished by using CD and C2 emissions to infer C I influxes from dissociation of hydrocarbons and comparing to measured C I influxes. The present work extends these results through detailed analysis of the C I spectral line shapes. In general, it is found that the profiles are actually asymmetric and have shifted peaks. These features are interpreted as originating from a combination of an anisotropic velocity distribution from physical sputtering (the Thompson model) and an isotropic distribution from molecular dissociation. The present study utilitzes pure helium plasmas to benchmark C I spectral profiles arising from physical sputtering alone. © 2004 Elsevier B.V. All rights reserved.

Published
2005

11. DIII-D research advancing the physics basis for optimizing the tokamak approach to fusion energy

Author

M. E. Fenstermacher, J. Abbate, S. Abe, T. Abrams, M. Adams, B. Adamson, N. Aiba, T. Akiyama, P. Aleynikov, E. Allen, S. Allen, H. Anand, J. Anderson, Y. Andrew, T. Andrews, D. Appelt, R. Arbon, N. Ashikawa, A. Ashourvan, M. Aslin, Y. Asnis, M. Austin, D. Ayala, J. Bak, I. Bandyopadhyay, S. Banerjee, K. Barada, L. Bardoczi, J. Barr, E. Bass, D. Battaglia, A. Battey, W. Baumgartner, L. Baylor, J. Beckers, M. Beidler, E. Belli, J. Berkery, T. Bernard, N. Bertelli, M. Beurskens, R. Bielajew, S. Bilgili, B. Biswas, S. Blondel, J. Boedo, I. Bogatu, R. Boivin, T. Bolzonella, M. Bongard, X. Bonnin, P. Bonoli, M. Bonotto, A. Bortolon, S. Bose, N. Bosviel, S. Bouwmans, M. Boyer, W. Boyes, L. Bradley, R. Brambila, D. Brennan, S. Bringuier, L. Brodsky, M. Brookman, J. Brooks, D. Brower, G. Brown, W. Brown, M. Burke, K. Burrell, K. Butler, R. Buttery, I. Bykov, P. Byrne, A. Cacheris, K. Callahan, J. Callen, G. Campbell, J. Candy, J. Canik, P. Cano-Megias, N. Cao, L. Carayannopoulos, T. Carlstrom, W. Carrig, T. Carter, W. Cary, L. Casali, M. Cengher, G. Cespedes Paz, R. Chaban, V. Chan, B. Chapman, I. Char, A. Chattopadhyay, R. Chen, J. Chen, X. Chen, M. Chen, Z. Chen, M. Choi, W. Choi, G. Choi, L. Chousal, C. Chrobak, C. Chrystal, Y. Chung, R. Churchill, M. Cianciosa, J. Clark, M. Clement, S. Coda, A. Cole, C. Collins, W. Conlin, A. Cooper, J. Cordell, B. Coriton, T. Cote, J. Cothran, A. Creely, N. Crocker, C. Crowe, B. Crowley, T. Crowley, D. Cruz-Zabala, D. Cummings, M. Curie, D. Curreli, A. Dal Molin, B. Dannels, A. Dautt-Silva, K. Davda, G. De Tommasi, P. De Vries, G. Degrandchamp, J. Degrassie, D. Demers, S. Denk, S. Depasquale, E. Deshazer, A. Diallo, S. Diem, A. Dimits, R. Ding, S. Ding, W. Ding, T. Do, J. Doane, G. Dong, D. Donovan, J. Drake, W. Drews, J. Drobny, X. Du, H. Du, V. Duarte, D. Dudt, C. Dunn, J. Duran, A. Dvorak, F. Effenberg, N. Eidietis, D. Elder, D. Eldon, R. Ellis, W. Elwasif, D. Ennis, K. Erickson, D. Ernst, M. Fasciana, D. Fedorov, E. Feibush, N. Ferraro, J. Ferreira, J. Ferron, P. Fimognari, D. Finkenthal, R. Fitzpatrick, P. Fox, W. Fox, L. Frassinetti, H. Frerichs, H. Frye, Y. Fu, K. Gage, J. Galdon Quiroga, A. Gallo, Q. Gao, A. Garcia, M. Garcia Munoz, D. Garnier, A. Garofalo, A. Gattuso, D. Geng, K. Gentle, D. Ghosh, L. Giacomelli, S. Gibson, E. Gilson, C. Giroud, F. Glass, A. Glasser, D. Glibert, P. Gohil, R. Gomez, S. Gomez, X. Gong, E. Gonzales, A. Goodman, Y. Gorelov, V. Graber, R. Granetz, T. Gray, D. Green, C. Greenfield, M. Greenwald, B. Grierson, R. Groebner, W. Grosnickle, M. Groth, H. Grunloh, S. Gu, W. Guo, H. Guo, P. Gupta, J. Guterl, W. Guttenfelder, T. Guzman, S. Haar, R. Hager, S. Hahn, M. Halfmoon, T. Hall, K. Hallatschek, F. Halpern, G. Hammett, H. Han, E. Hansen, C. Hansen, M. Hansink, J. Hanson, M. Hanson, G. Hao, A. Harris, R. Harvey, S. Haskey, E. Hassan, A. Hassanein, D. Hatch, R. Hawryluk, W. Hayashi, W. Heidbrink, J. Herfindal, J. Hicok, D. Hill, E. Hinson, C. Holcomb, L. Holland, C. 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Honda, M, Hong, R, Hood, R, Horton, A, Horvath, L, Hosokawa, M, Houshmandyar, S, Howard, N, Howell, E, Hoyt, D, Hu, W, Hu, Y, Hu, Q, Huang, J, Huang, Y, Hughes, J, Human, T, Humphreys, D, Huynh, P, Hyatt, A, Ibanez, C, Ibarra, L, Icasas, R, Ida, K, Igochine, V, In, Y, Inoue, S, Isayama, A, Izacard, O, Izzo, V, Jackson, A, Jacobsen, G, Jaervinen, A, Jalalvand, A, Janhunen, J, Jardin, S, Jarleblad, H, Jeon, Y, Ji, H, Jian, X, Joffrin, E, Johansen, A, Johnson, C, Johnson, T, Jones, C, Joseph, I, Jubas, D, Junge, B, Kalb, W, Kalling, R, Kamath, C, Kang, J, Kaplan, D, Kaptanoglu, A, Kasdorf, S, Kates-Harbeck, J, Kazantzidis, P, Kellman, A, Kellman, D, Kessel, C, Khumthong, K, Kim, E, Kim, H, Kim, J, Kim, S, Kim, K, Kim, C, Kimura, W, King, M, King, J, Kinsey, J, Kirk, A, Kiyan, B, Kleiner, A, Klevarova, V, Knapp, R, Knolker, M, Ko, W, Kobayashi, T, Koch, E, Kochan, M, Koel, B, Koepke, M, Kohn, A, Kolasinski, R, Kolemen, E, Kostadinova, E, Kostuk, M, Kramer, G, Kriete, D, Kripner, L, Kubota, S, Kulchar, J, Kwon, K, La Haye, R, Laggner, F, Lan, H, Lantsov, R, Lao, L, Esquisabel, A, Lasnier, C, Lau, C, Leard, B, Lee, J, Lee, R, Lee, M, Lee, Y, Lee, C, Lee, S, Lehnen, M, Leonard, A, Leppink, E, Lesher, M, Lestz, J, Leuer, J, Leuthold, N, Li, X, Li, K, Li, E, Li, G, Li, L, Li, Z, Li, J, Li, Y, Lin, Z, Lin, D, Liu, X, Liu, J, Liu, Y, Liu, T, Liu, C, Liu, Z, Liu, D, Liu, A, Loarte-Prieto, A, Lodestro, L, Logan, N, Lohr, J, Lombardo, B, Lore, J, Luan, Q, Luce, T, Di Cortemiglia, T, Luhmann, N, Lunsford, R, Luo, Z, Lvovskiy, A, Lyons, B, Ma, X, Madruga, M, Madsen, B, Maggi, C, Maheshwari, K, Mail, A, Mailloux, J, Maingi, R, Major, M, Makowski, M, Manchanda, R, Marini, C, Marinoni, A, Maris, A, Markovic, T, Marrelli, L, Martin, E, Mateja, J, Matsunaga, G, Maurizio, R, Mauzey, P, Mauzey, D, Mcardle, G, Mcclenaghan, J, Mccollam, K, Mcdevitt, C, Mckay, K, Mckee, G, Mclean, A, Mehta, V, Meier, E, Menard, J, Meneghini, O, Merlo, G, Messer, S, Meyer, W, Michael, C, Michoski, C, Milne, P, Minet, G, Misleh, A, Mitrishkin, Y, Moeller, C, Montes, K, Morales, M, Mordijck, S, Moreau, D, Morosohk, S, Morris, P, Morton, L, Moser, A, Moyer, R, Moynihan, C, Mrazkova, T, Mueller, D, Munaretto, S, Burgos, J, Murphy, C, Murphy, K, Muscatello, C, Myers, C, Nagy, A, Nandipati, G, Navarro, M, Nave, F, Navratil, G, Nazikian, R, Neff, A, Neilson, G, Neiser, T, Neiswanger, W, Nelson, D, Nelson, A, Nespoli, F, Nguyen, R, Nguyen, L, Nguyen, X, Nichols, J, Nocente, M, Nogami, S, Noraky, S, Norausky, N, Nornberg, M, Nygren, R, Odstrcil, T, Ogas, D, Ogorman, T, Ohdachi, S, Ohtani, Y, Okabayashi, M, Okamoto, M, Olavson, L, Olofsson, E, Omullane, M, Oneill, R, Orlov, D, Orvis, W, Osborne, T, Pace, D, Canal, G, Martinez, A, Palacios, L, Pan, C, Pan, Q, Pandit, R, Pandya, M, Pankin, A, Park, Y, Park, J, Parker, S, Parks, P, Parsons, M, Patel, B, Pawley, C, Paz-Soldan, C, Peebles, W, Pelton, S, Perillo, R, Petty, C, Peysson, Y, Pierce, D, Pigarov, A, Pigatto, L, Piglowski, D, Pinches, S, Pinsker, R, Piovesan, P, Piper, N, Pironti, A, Pitts, R, Pizzo, J, Plank, U, Podesta, M, Poli, E, Poli, F, Ponce, D, Popovic, Z, Porkolab, M, Porter, G, Powers, C, Powers, S, Prater, R, Pratt, Q, Pusztai, I, Qian, J, Qin, X, Ra, O, Rafiq, T, Raines, T, Raman, R, Rauch, J, Raymond, A, Rea, C, Reich, M, Reiman, A, Reinhold, S, Reinke, M, Reksoatmodjo, R, Ren, Q, Ren, Y, Ren, J, Rensink, M, Renteria, J, Rhodes, T, Rice, J, Roberts, R, Robinson, J, Fernandez, P, Rognlien, T, Rosenthal, A, Rosiello, S, Rost, J, Roveto, J, Rowan, W, Rozenblat, R, Ruane, J, Rudakov, D, Ruiz, J, Rupani, R, Saarelma, S, Sabbagh, S, Sachdev, J, Saenz, J, Saib, S, Salewski, M, Salmi, A, Sammuli, B, Samuell, C, Sandorfi, A, Sang, C, Sarff, J, Sauter, O, Schaubel, K, Schmitz, L, Schmitz, O, Schneider, J, Schroeder, P, Schultz, K, Schuster, E, Schwartz, J, Sciortino, F, Scotti, F, Scoville, J, Seltzman, A, Seol, S, Sfiligoi, I, Shafer, M, Sharapov, S, Shen, H, Sheng, Z, Shepard, T, Shi, S, Shibata, Y, Shin, G, Shiraki, D, Shousha, R, Si, H, Simmerling, P, Sinclair, G, Sinha, J, Sinha, P, Sips, G, Sizyuk, T, Skinner, C, Sladkomedova, A, Slendebroek, T, Slief, J, Smirnov, R, Smith, J, Smith, S, Smith, D, Snipes, J, Snoep, G, Snyder, A, Snyder, P, Solano, E, Solomon, W, Song, J, Sontag, A, Soukhanovskii, V, Spendlove, J, Spong, D, Squire, J, Srinivasan, C, Stacey, W, Staebler, G, Stagner, L, Stange, T, Stangeby, P, Stefan, R, Stemprok, R, Stephan, D, Stillerman, J, Stoltzfus-Dueck, T, Stonecipher, W, Storment, S, Strait, E, Su, D, Sugiyama, L, Sun, Y, Sun, P, Sun, Z, Sun, A, Sundstrom, D, Sung, C, Sungcoco, J, Suttrop, W, Suzuki, Y, Suzuki, T, Svyatkovskiy, A, Swee, C, Sweeney, R, Sweetnam, C, Szepesi, G, Takechi, M, Tala, T, Tanaka, K, Tang, X, Tang, S, Tao, Y, Tao, R, Taussig, D, Taylor, T, Teixeira, K, Teo, K, Theodorsen, A, Thomas, D, Thome, K, Thorman, A, Thornton, A, Ti, A, Tillack, M, Timchenko, N, Tinguely, R, Tompkins, R, Tooker, J, De Sousa, A, Trevisan, G, Tripathi, S, Ochoa, A, Truong, D, Tsui, C, Turco, F, Turnbull, A, Umansky, M, Unterberg, E, Vaezi, P, Vail, P, Valdez, J, Valkis, W, Van Compernolle, B, Van Galen, J, Van Kampen, R, Van Zeeland, M, Verdoolaege, G, Vianello, N, Victor, B, Viezzer, E, Vincena, S, Wade, M, Waelbroeck, F, Wai, J, Wakatsuki, T, Walker, M, Wallace, G, Waltz, R, Wampler, W, Wang, L, Wang, H, Wang, Y, Wang, Z, Wang, G, Ward, S, Watkins, M, Watkins, J, Wehner, W, Wei, Y, Weiland, M, Weisberg, D, Welander, A, White, A, White, R, Wiesen, S, Wilcox, R, Wilks, T, Willensdorfer, M, Wilson, H, Wingen, A, Wolde, M, Wolff, M, Woller, K, Wolz, A, Wong, H, Woodruff, S, Wu, M, Wu, Y, Wukitch, S, Wurden, G, Xiao, W, Xie, R, Xing, Z, Xu, X, Xu, C, Xu, G, Yan, Z, Yang, X, Yang, S, Yokoyama, T, Yoneda, R, Yoshida, M, You, K, Younkin, T, Yu, J, Yu, M, Yu, G, Yuan, Q, Zaidenberg, L, Zakharov, L, Zamengo, A, Zamperini, S, Zarnstorff, M, Zeger, E, Zeller, K, Zeng, L, Zerbini, M, Zhang, L, Zhang, X, Zhang, R, Zhang, B, Zhang, J, Zhao, L, Zhao, B, Zheng, Y, Zheng, L, Zhu, B, Zhu, J, Zhu, Y, Zsutty, M, Zuin, M, Lawrence Livermore National Laboratory, Princeton Plasma Physics Laboratory, Princeton University, General Atomics, Max-Planck-Institut für Plasmaphysik, Imperial College London, National Institute for Fusion Science, Universidade de São Paulo, University of Texas at Austin, ITER, College of William and Mary, University of California Los Angeles, University of California San Diego, Columbia University, Massachusetts Institute of Technology, Oak Ridge National Laboratory, Eindhoven University of Technology, Oak Ridge Associated Universities, West Virginia University, University of Tennessee, Knoxville, National Research Council of Italy, Stony Brook University, Purdue University, University of Seville, University of Science and Technology of China, Carnegie Mellon University, Institute for Plasma Research, Peking University, University of California Davis, University of California Irvine, Commonwealth Fusion Systems, University of Liverpool, University of Illinois at Urbana-Champaign, University of Milan - Bicocca, Georgia Institute of Technology, Southwestern Institute of Physics, University of Toronto, Auburn University, Polytechnic University of Turin, Universidade Lisboa, Association CCFE, KTH Royal Institute of Technology, San Diego State University, Durham University, Lehigh University, Fusion and Plasma Physics, University of Washington, Department of Applied Physics, Sandia National Laboratories, Ghent University, Technical University of Denmark, CEA, University of Colorado Boulder, Harvard University, National Technical University of Athens, Coventry University, University of Stuttgart, Czech Academy of Sciences, Harvey Mudd College, Seoul National University, Donghua University, University of York, Dalian University of Technology, University of California Berkeley, Los Alamos National Laboratory, United States Department of Energy, University of British Columbia, Pacific Northwest National Laboratory, University of Wisconsin, Michigan State University, University of Strathclyde, Pennsylvania State University, Rensselaer Polytechnic Institute, University of Southern California, Chalmers University of Technology, University of Virginia, University of Naples Federico II, University of Oxford, VTT Technical Research Centre of Finland, National Institute of Technology, University of Connecticut, DIFFER, CIEMAT, Hanyang University, Brigham Young University, UiT The Arctic University of Norway, Australian National University, Russian Research Centre Kurchatov Institute, Forschungszentrum Jülich, Zhejiang University, The University of Tokyo, University of Michigan, Agenzia nazionale per le nuove tecnologie, l'energia e lo sviluppo economico sostenibile, Aalto-yliopisto, Aalto University, DIII-D Team, Complex Ionized Media, Elementary Processes in Gas Discharges, Applied Physics and Science Education, Science and Technology of Nuclear Fusion, and Control Systems Technology

Subjects
Nuclear and High Energy Physics, Tokamak, Technology and Engineering, DIII-D, Nuclear engineering, TOKAMAKS, MITIGATION, law.invention, Plasma physics, mitigation, law, plasma physic, tokamak, Physics, Core-edge integration, Basis (linear algebra), plasma physics, core-edge integration, scenarios, Fusion power, Condensed Matter Physics, SCENARIOS, fusion energy, Fusion energy
Abstract

Funding Information: This material is based upon work supported by the US Department of Energy, Office of Science, Office of Fusion Energy Sciences, using the DIII-D National Fusion Facility, a DOE Office of Science user facility, under Awards DE-FC02-04ER54698 and DE-AC52-07NA27344. Publisher Copyright: © 2022 IAEA, Vienna. DIII-D physics research addresses critical challenges for the operation of ITER and the next generation of fusion energy devices. This is done through a focus on innovations to provide solutions for high performance long pulse operation, coupled with fundamental plasma physics understanding and model validation, to drive scenario development by integrating high performance core and boundary plasmas. Substantial increases in off-axis current drive efficiency from an innovative top launch system for EC power, and in pressure broadening for Alfven eigenmode control from a co-/counter-I p steerable off-axis neutral beam, all improve the prospects for optimization of future long pulse/steady state high performance tokamak operation. Fundamental studies into the modes that drive the evolution of the pedestal pressure profile and electron vs ion heat flux validate predictive models of pedestal recovery after ELMs. Understanding the physics mechanisms of ELM control and density pumpout by 3D magnetic perturbation fields leads to confident predictions for ITER and future devices. Validated modeling of high-Z shattered pellet injection for disruption mitigation, runaway electron dissipation, and techniques for disruption prediction and avoidance including machine learning, give confidence in handling disruptivity for future devices. For the non-nuclear phase of ITER, two actuators are identified to lower the L-H threshold power in hydrogen plasmas. With this physics understanding and suite of capabilities, a high poloidal beta optimized-core scenario with an internal transport barrier that projects nearly to Q = 10 in ITER at ∼8 MA was coupled to a detached divertor, and a near super H-mode optimized-pedestal scenario with co-I p beam injection was coupled to a radiative divertor. The hybrid core scenario was achieved directly, without the need for anomalous current diffusion, using off-axis current drive actuators. Also, a controller to assess proximity to stability limits and regulate β N in the ITER baseline scenario, based on plasma response to probing 3D fields, was demonstrated. Finally, innovative tokamak operation using a negative triangularity shape showed many attractive features for future pilot plant operation.

Published
2022
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13. Separatrix-to-Wall Simulations of Impurity Transport with a Fully Three-Dimensional Wall in DIII-D

Author

Zamperini, Shawn, Abrams, T., Nichols, J. H., Elder, J. D., Duran, J. D., Stangeby, P. C., Donovan, D. C., Rudakov, D. L., Wingen, A., and Crowe, C.

Abstract

AbstractA novel multicode workflow to interpret collector probe deposition patterns in DIII-D has been developed. The components of the workflow consist of a detailed computer-aided-design file of the vessel wall and the scrape-off-layer (SOL) codes MAFOT, OSM, DIVIMP, and 3DLIM. A special-purpose toolkit enables passing the output of these codes among each other to provide a full-SOL picture of impurity transport. A demonstration of the workflow is described to support evidence of near-SOL tungsten parallel accumulation during trace W impurity experiments on DIII-D. Iteration between simulated deposition patterns in 3DLIM and DIVIMP predicts a region of elevated W density near the separatrix about halfway between the outboard midplane and the top of the plasma. This workflow will be used to better interpret collector probe experiments on DIII-D.

Published
2023
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14. Latest JET results in deuterium and deuterium - tritium plasmas

Author

I. D. Young, N. Bainbridge, N. Dolgetta, R. A. M. Van der Linden, Philip Andrew, S. M. Scott, C. Caldwell-Nichols, R. Reichle, D. Campling, J. Mills, D.F.H. Start, P. G. Doyle, L.-G. Eriksson, A. Taroni, F.G. Rimini, T. Winkel, G. Corrigan, P. Breger, J. J. Davis, W. Zwingmann, M. Cox, L. Scibile, M. Gadeberg, B. Alper, S. Knipe, M.L. Watkins, P. Schild, C. D. Challis, A. Meigs, T. Lovegrove, C. Ingesson, E. Traneus, E. Deksnis, R. Mohanti, P. Miele, D.J. Ward, D. Stork, L. Galbiati, H. E. Clarke, M.A. Pick, B. Fischer, A. M. Edwards, L. Svensson, R. König, W. Parsons, M. De Benedetti, P. Noll, S. Papastergiou, N. C. Hawkes, B. Esposito, D. Ciric, G. McCracken, F. Hurd, A. Burt, R.D. Monk, J.K. Ehrenberg, J.P. Christiansen, A. Vadgama, J. M. Adams, R. D. Gill, J.G. Cordey, A. Gibson, Wolfgang Kerner, P. E. Stott, D. O'Brien, D. Bond, D. Young, T. Elevant, G. Vlases, M. Fichtmuller, R. Ostrom, M. von Hellermann, J. Tait, B. Haist, J.C.M. de Haas, P. Smith, R. Giannella, R. Claesen, N. P. Hawkes, M. Ottaviani, G. Fishpool, A. Howman, P. A. McCullen, A. C. Bell, A. Tabasso, R. Simonini, K. Guenther, N. Zornig, Q. Yu, V. Schmidt, N. Deliyanakis, J. How, Y. Baranov, I. Coffey, Michael Loughlin, S. A. Arshad, B. Patel, B. E. Keen, L. Lauro-Taroni, A. Kaye, P. Kupschus, D. Chiron, Shane Cooper, P. Chuilon, H. Altmann, M. Brandon, T. T. C. Jones, Y. Ul'Haq, D.V. Bartlett, F. Junique, F. Soldner, B. Ingram, C. Terella, R. Smith, G. Newbert, C. Lowry, B. Schunke, B.J.D. Tubbing, L. D. Horton, J. Jacquinot, N. G. Kidd, P. Card, J.P. Coad, P.R. Thomas, P. Barker, F. Nave, A. Sibley, P. Stangeby, T. P. Hughes, R. Parkinson, G.A. Cottrell, C. F. Maggi, S. E. Sharapov, R. Saunders, C. Gowers, A. Gondhalekar, J.A. Hoekzema, D. Wilson, A. Tanga, H. Brelen, E. Springmann, A.W. Edwards, S. J. Davies, K. Fullard, D. Martin, L. Roquemore, Ambrogio Fasoli, R. Walton, P.D. Morgan, A. Peacock, G. Murphy, J. G. Krom, W. Zhang, M. Salisbury, S. Clement, C. Gormezano, P. Nielsen, K. D. Lawson, G. Conway, M. J. Watson, D. Godden, O. Pogutse, G. Saibene, H. Guo, T. Wade, J. W. Farthing, J. L. Hemmerich, P. Svensson, S. Puppin, S. K. Erents, J.A. Dobbing, M. Johnson, P. Strachen, Henrik Bindslev, L. Rossi, P. Twyman, K. Blackler, H. Jaeckel, T. Bonicelli, S. E. Dorling, G. Matthews, M. L. Browne, B. Schokker, P. van Belle, A. C. Maas, J. F. Jaeger, H. Duquenoy, A. Rolfe, H. McBryan, P. Ageladarakis, Filippo Sartori, O.N. Jarvis, S. Ericsson, T. Hender, A. Paynter, T. Businaro, V. Riccardo, M. Huart, M. J. Mantsinen, F. Milani, A. Rossi, M. Keilhacker, P. Brennan, P. J. Lomas, Robin Barnsley, Annika Ekedahl, M. Endler, G. Radford, J. F. Junger, A. V. Chankin, P. Stubberfield, Jan Egedal, E. M. Jones, N. Davies, H.P.L. de Esch, B. Balet, D.D.R. Summers, C. Perry, A. Santagiustina, G. T. A. Huysmans, V. V. Parail, K. Thomsen, D. Bailey, J. Mart, A. Dines, M. Irving, G.J. Sadler, V.P. Bhatnagar, E. Righi, E. Oord, R. Stagg, A. C. C. Sips, W. J. Brewerton, R. T. Ross, H. D. Falter, F. Jensen, Sean Conroy, V. Marchese, Nicholas Watkins, M. Lennholm, J. Spence, M.F. Stamp, T. Budd, P. J. Harbour, M. Schmid, M. Buzio, B. Macklin, S. L. Dmitrenko, P. Smeulders, R. Middleton, D.H.J. Goodall, F.B. Marcus, J. Dorr, S. J. Cox, K.-D. Zastrow, A. Perevezentsev, A. J. Bickley, R. J. H. Pearce, D. N. Borba, M. Tabellini, J. Lingertat, E. Bertolini, R. Cusack, R. Lasser, J. Plancoulaine, N. Peacock, M. Wheatley, J. Ellis, M. Baronian, R. Prentice, A. Haigh, W. Obert, and C. J. Hancock

Subjects
Jet (fluid), Materials science, Plasma, Condensed Matter Physics, Ion, law.invention, Nuclear physics, Shear (sheet metal), Ignition system, Nuclear Energy and Engineering, Deuterium, Physics::Plasma Physics, law, Tritium, Neutron
Abstract

All major JET systems have been fully commissioned for D-T and the DTE1 series of experiments has started with the D-T fuel mixture and operating conditions foreseen for ITER. In the area of ITER physics, significant results have been produced in both D-D and D-T. In D-D, the LH threshold power database has been extended, the bounds on edge-electron temperature and density in ELMy H-modes have been defined and the advantages of Types I and III ELMy discharges have been compared. In D-T plasmas, the isotope effect on H-mode threshold power and transport has been determined so that a more accurate assessment can be made of the ignition margin and heating requirements for ITER. Trace tritium experiments have provided first particle transport measurements and an assessment of the ITER reference ion-cyclotron resonance-frequency heating scenarios has been started, In the area of fusion performance, record D-D neutron yields have been obtained by controlling the plasma and current profiles in hot ion ELM-free H-modes and optimized shear modes. In D-T, internal transport barriers have been readily established in optimized shear discharges and Alfven eigenmodes have been observed.

Published
1997
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15. Review of neutral beam heating on JET for physics experiments and the production of high fusion performance plasmas

Author

R. König, N. Peacock, E. Martin, L. Lauro-Taroni, D.V. Bartlett, B. Ingram, G. Vlases, A. Sibley, C. Terella, C. Lowry, N. A. Gottardi, T. Elevant, G. Saibene, J. Christiansen, M. Baronian, A. Tesini, T. Raimondi, A. J. Bickley, J. How, H. van der Beken, A. Haigh, N. C. Hawkes, M. C. Ramos de Andrade, H. Morsi, G. Murphy, M. Botman, A. Dines, A. Gondhalekar, C. Gormezano, M. Irving, H. Brelen, M. Tabellini, B. Schunke, B.J.D. Tubbing, G. Sadler, P. R. Thomas, C. Gowers, P. E. Stott, G. Corrigan, S. Cooper, W. J. Brewerton, H. D. Falter, M. Keilhacker, A. Korotkov, V. Marchese, M. Cox, P. Breger, M. Nilsen, T. Szabo, M. L. Watkins, R. Claesen, C. J. Hancock, I. D. Young, S. Ali-Arshad, M. J. Watson, O. N. Jarvis, E. Bertolini, C. Walker, S. Clement, Y. Baranov, W. Bailey, G. Celentano, C. Froger, K. D. Lawson, D. Stork, D.F.H. Start, A. Cherubini, R. Monk, S. L. Dmitrenko, H. Jaeckel, S. Richards, C. A. Steed, L. G. Eriksson, S. F. Mills, S. J. Booth, P. G. Doyle, P. Meriguet, R. J. M. Pearce, H. Duquenoy, G. Radford, R. Prentice, F. Jensen, M. A. Pick, C. D. Challis, B. Alper, R. Wolf, J. Lingertat, F. Soldner, M. O'Mullane, N. Deliyanakis, P. Nielsen, A. C. Bell, R. Lasser, E. Deksnis, J. P. Coad, P. J. Harbour, E. M. Jones, T. Budo, F. Marcus, N. Davies, B. Balet, F.G. Rimini, M. Comiskey, T. Wade, P. Burton, T. Bonicelli, P. Gaze, K. Fullard, D. Martin, W. Zwingmann, T. Winkel, M. Ottaviani, P. Massmann, J. O'Rourke, D. Bond, P. Boucquey, P. Barabaschi, R. D. Gill, M. Cooke, B. Patel, W. Suverkroop, A. Kaye, D. Chiron, T. Businaro, D. Goodall, M.F. Stamp, G. B. Denne-Hinnov, R. Ostrom, A. Girard, L. Horton, F. Trevalion, C. Woodward, J. Ehrenberg, M. Johnson, A. Loarte, S. Puppin, R. Simoni, J. Jacquinot, A. Galetsas, W. Obert, M. Schmid, J. F. Junger, J. F. Jaeger, P. Andrew, L. Rossi, K. Borras, P. Smeulders, R. Reichle, A. Rolfe, J. Plancoulaine, P. Chuilon, T. T. C. Jones, R. Barnsley, A. Gibson, P. Card, N. Dolgetta, R. Rookes, M. Rapisarda, A. Colton, P. Schild, H. Buttgereit, M. von Hellermann, C. Perry, Henrik Bindslev, M. Garribba, F. Hurd, J. Mart, C. Sborchia, S. M. Scott, K. Blackler, A. Santagiustina, G. Bosia, C. Cottrell, I. Coffey, G. Newbert, S. Papastergiou, P. Butcher, L. Svensson, G. Vayakis, O. Da Costa, T. Hender, S. Weber, C. F. Maggi, V. V. Parail, P. Froissard, A. Taroni, A.E. Costley, J. P. Poffe, V.P. Bhatnagar, A. C. Maas, Y. Agarici, K. Thomsen, H. McBryan, Francesco Porcelli, H. Altmann, T. J. Wijnands, T. Brown, R. T. Ross, D. O'Brien, R. N. Litunovski, J. J. Davies, R. Russ, P. Kupschus, Annika Ekedahl, G. Magyar, G. Fishpool, H. Deesch, A. C. C. Sips, N. G. Kidd, C. Caldwell-Nichols, T. P. Hughes, M. Newmann, R. Sartori, S. Corti, S. K. Erents, T. Martin, R. Haange, A. M. Edwards, J.A. Dobbing, M. Gadeberg, G. Matthews, Laurie Porte, M. Wykes, D. Wilson, S. J. Davies, J. M. Adams, D. Ward, Wolfgang Kerner, L. Zannelli, J. G. Cordey, A. Tanga, P. Peacock, P. Bertoldi, H. Summers, L. Galbiati, W. J. Dickson, N. P. Hawkes, Michael Loughlin, David Campbell, D. Summers, P. Stangeby, D. Campling, J. L. Hemmerich, G. Benali, S. E. Dorling, J.A. Hoekzema, P. Haynes, J. L. Salanave, F. Junique, M. Salisbury, M. Brusati, J. Wesson, E. Oord, R. Giannella, M. Bures, J. Freiling, G. Janeschitz, M. Huart, E. Righi, G. Sanazzaro, P. J. Lomas, G. Deschamps, P. Stubberfield, M. Lennholm, E. Thompson, B. Macklin, P. J. Howarth, L. P. D. F. Jones, B. E. Keen, P. Noll, M. Brandon, R. Smith, P. Barker, F. Nave, P.D. Morgan, and P. Crawley

Subjects
Physics, Fusion, Jet (fluid), Mechanical Engineering, Nuclear engineering, Plasma, Neutral beam injection, Ion, Nuclear physics, Nuclear Energy and Engineering, Nuclear fusion, General Materials Science, Tritium, Beam (structure), Civil and Structural Engineering
Abstract

The JET neutral beam injection system has proved to be both effective and reliable as a plasma heating device. The ion heating and plasma fuelling characteristics of the system are ideally suited to the production of high fusion performance plasmas while the flexibility in the choice of beam species (H, D, T, 3 He or 4 He) and the ability to inject into almost any JET plasma configuration allows a wide variety of related physics experiments to be carried out. The capability to inject (for the first time) tritium beams was essential to the successful execution of the first tritium experiments in which 1.7 MW of power from DT fusion reactions was generated.

Published
1995
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16. Overview of high performance H-modes in JET

Author

A. C. C. Sips, A.E. Costley, F. Hurd, G. Saibene, M. Salisbury, M. Brusati, C. Perry, P. J. Harbour, T. Martin, J. P. Poffe, Laurie Porte, H. van der Beken, N. C. Hawkes, J. Wesson, M. Bures, G. Janeschitz, M. Huart, A. Santagiustina, G. Bosia, H. Altmann, J. L. Salanave, A. Dines, N. G. Kidd, F. Junique, E. Righi, P. J. Lomas, P. G. Doyle, J. G. Cordey, G. Magyar, V. V. Parail, K. Thomsen, A. Gondhalekar, M. Irving, C. Gowers, R. Ostrom, C. Woodward, A. Galetsas, A. Loarte, P. Card, P. Trevalion, A. M. Edwards, T. P. Hughes, F. Jensen, M. Newman, C. Caldwell-Nichols, N. Peacock, P. Smeulders, A. Korotkov, A. Colton, P. Chuilon, T. T. C. Jones, F.G. Rimini, T. Winkel, P. Stubberfield, M. A. Pick, J.A. Hoekzema, T. Szabo, J. M. Adams, R. Prentice, Wolfgang Kerner, L. Zannelli, M. Rapisarda, D.F.H. Start, L. G. Eriksson, P. Schild, M. Wykes, D. Wilson, S. J. Davies, A. Sibley, P. Haynes, B. Alper, R. Wolf, T. Elevant, R. T. Ross, J. O'Rourke, E. Thompson, C. J. Hancock, R. Haange, P. E. Stott, A. Tesini, B. Macklin, M. Baronian, W. J. Brewerton, M.F. Stamp, L. P. D. F. Jones, A. C. Maas, B. E. Keen, A. Taroni, H. Morsi, G. Murphy, H. D. Falter, M. Keilhacker, I. D. Young, M. von Hellermann, A. Girard, A. Haigh, M. Cooke, A. Cherubini, Henrik Bindslev, D. Goodall, L. Horton, S. K. Erents, J.A. Dobbing, M. Gadeberg, E. Deksnis, G. Matthews, M. Comiskey, T. Wade, F. Marcus, M. Schmid, P. Burton, M. Garribba, G. Newbert, P. Barabaschi, A. Peacock, V. Marchese, C. Froger, K. D. Lawson, P. Noll, M. Brandon, G. Sadler, P. R. Thomas, C. F. Maggi, W. Bailey, D. Ward, K. Blackler, A. Rolfe, T. J. Wijnands, R. Barnsley, G. Celentano, R. Russ, Annika Ekedahl, G. Vayakis, T. Bonicelli, P. Froissard, C. Walker, J. Jacquinot, J. Plancoulaine, P. Kupschus, N. Dolgetta, Y. Agarici, D. Summers, M. Ottaviani, H. Brelen, S. Ali-Arshad, C. Sborchia, R. Claesen, C. A. Steed, S. F. Mills, A. Gibson, R. Smith, B. Schunke, B.J.D. Tubbing, J. Mart, H. McBryan, L. Svensson, J. J. Davis, S. M. Scott, R. J. M. Pearce, J. P. Coad, F. Soldner, T. Budd, P. Stangeby, E. M. Jones, V.P. Bhatnagar, C. D. Challis, R. Rookes, D. Campling, I. Coffey, W. Zwingmann, A. C. Bell, E. Oord, D. O'Brien, P. Gaze, N. Davies, D. Bond, David Campbell, P. Barker, F. Nave, G. B. Denne-Hinnov, S. Papastergiou, R. Monk, S. L. Dmitrenko, B. Balet, P. Butcher, L. Rossi, K. Borras, O. Da Costa, R. Giannella, P. Massmann, R. D. Gill, R. Sartori, J. Lingertat, S. Weber, R. N. Litunovski, H. Buttgereit, J. Ehrenberg, B. Patel, R. Lasser, N. A. Gottardi, A. Kaye, T. Brown, J. Christiansen, T. Businaro, L. Lauro-Taroni, C. Gormezano, O. N. Jarvis, S. Clement, A. J. Bickley, J. Freiling, D.V. Bartlett, D. Chiron, M. Botman, B. Ingram, C. Terella, C. Lowry, W. Obert, M. Tabellini, S. Corti, S. Cooper, P. Bertoldi, E. Bertolini, H. Summers, P.D. Morgan, P. Crawley, R. Reichle, Francesco Porcelli, G. Sanazzaro, G. Corrigan, T. Raimondi, G. Deschamps, M. J. Watson, M. C. Ramos de Andrade, G. Fishpool, H. Deesch, J. L. Hemmerich, G. Benali, Y. Baranov, H. Jaeckel, S. E. Dorling, G. Radford, S. J. Booth, J. F. Junger, H. Duquenoy, M. Lennholm, L. Galbiati, W. J. Dickson, N. P. Hawkes, R. Simonini, Michael Loughlin, T. Hender, M. Cox, P. Breger, W. Suverkropp, M. Nilsen, M. L. Watkins, S. Puppin, D. Stork, S. Richards, P. Nielsen, P. Boucquey, G.A. Cottrell, A. Tanga, P. J. Howarth, K. Fullard, D. Martin, M. Johnson, J. F. Jaeger, P. Andrew, P. Meriguet, Ralf König, M. O'Mullane, N. Deliyanakis, E. Martin, G. Vlases, and J. How

Subjects
Physics, Nuclear Energy and Engineering, Diamagnetism, Plasma, Atomic physics, Condensed Matter Physics, Phenomenology (particle physics), Scaling, Ion
Abstract

An account is given of the high performance plasmas established by development of the H-mode regime in JET in the experimental campaigns up to 1992. High performance in this case is measured in terms of the confinement enhancement achieved over the L-mode scaling as measured using the plasma diamagnetism. Three JET H-mode regimes have achieved enhancement factors (H G DIA ) over Goldston L-mode scaling of 2.5 < H G DIA < 4.0. These are the Pellet Enhanced Performance (PEP) H-MODE, the high bootstrap fraction (high β POL ) H-mode and the Hot Ion (HI) H-mode. The phenomenology of these three regimes is reviewed and contrasts and common threads are elucidated

Published
1994
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21. First results with the modified JET

Author

S. Clement, P. Nielsen, D. V. Bartlett, R. Goulding, M. Bures, P. Boucquey, R. Claesen, M. Cox, P. Breger, W. Suverkropp, M. L. Watkins, S. Richards, C. J. Hancock, I. D. Young, P. Card, T. Raimondi, H. Jaeckl, R. Ostrom, J. Mart, Henrik Bindslev, E. van der Goot, C. Woodward, D. Summers, R. König, B. Schunke, T. Hender, E. Thompson, F. Sartori, F. Cecil, P. Chuilon, T. T. C. Jones, S. Milani, G. Saibene, R. Prentice, B. Macklin, L. Svensson, J. Lingertat, P. Smeulders, R. L. Shaw, N. Watkins, R. J. M. Pearce, H. van der Beken, N. C. Hawkes, J. Jacquinot, P. Stubberfield, N. G. Kidd, T. P. Hughes, T. Elevant, R. Monk, W. Zwingmann, J.A. Hoekzema, S. Papastergiou, G. Vlases, R. Lasser, B. Fischer, S. L. Dmitrenko, C. D. Challis, L. Lauro-Taroni, F. Hurd, R. T. Ross, R. Cusack, D. Wilson, H. Brelen, David Campbell, A. C. Maas, G. Cottrell, E. Bertolini, J. How, J. Plancoulaine, R. Russ, O. Da Costa, K. Lawson, J. P. Poffe, N. Peacock, L. Porte, L. Galbiati, S. Ali-Arshad, B. Ingram, B. Alper, R. Wolf, K. Fullard, E. Oord, H. Altmann, A. M. Edwards, C. Terella, C. Lowry, D. Martin, E. Deksnis, A. Rossi, D. O'Brien, S. J. Davies, J. J. Davis, F. Marcus, R. Giannella, C. Walker, V. Bhatnagar, C. A. Steed, A. Gibson, F. Jensen, A. Ekedahl, M. Baronian, J. M. Adams, M. A. Pick, E. M. Jones, N. P. Hawkes, G. D'Antona, P. Schild, L. Horton, J. Freiling, D. Bond, G. Sadler, Wolfgang Kerner, D. Stork, N. Davies, S. K. Erents, R. Simonini, Michael Loughlin, M. Stamp, M. Schmid, P. J. Harbour, L. Zannelli, M. Schaffer, R. D. Gill, F. Nguyen, M. Gadeberg, A. Tanga, A. Haigh, B. Balet, F. Junique, G. Matthews, M. Johnson, G. Sanazzaro, P. R. Thomas, T. Budd, J. L. Hemmerich, G. Benali, A. Peacock, S. E. Dorling, G. McCormick, J. Dobbing, J. F. Jaeger, P. Andrew, P. Froissard, C. Perry, A. Santagiustina, M. von Hellermann, W. Bailey, D. Ward, C. Caldwell-Nichols, B. Patel, G. Celentano, T. Wade, V. V. Parail, T. Businaro, E. Lazzaro, A. C. Bell, G. Vayakis, G. Fishpool, H. Deesch, F. Rimini, S. Colombi, S. Puppin, B. Tubbing, W. Obert, A. C. C. Sips, F. Soldner, J. Christiansen, A. Sibley, N. Zornig, A. Rookes, M. Salisbury, A. Kaye, D. Chiron, N. A. Gottardi, J. Wesson, S. Sharapov, T. Martin, S. Weber, P. Lomas, D. Campling, P. Lamalle, A. Rolfe, M. Cooke, D. Goodall, A. J. Bickley, N. Deliyanakis, P. Morgan, A. Tesini, B. Fechner, I. Hutchinson, M. Garribba, R. Reichle, F. Porcelli, R. Barnsley, G. Newbert, G. Murphy, M. Tabellini, P. Stangeby, M. Huart, S. Cooper, E. Righi, L. Rossi, K. Borras, L. G. Eriksson, C. F. Maggi, C. Froger, J. G. Cordey, N. Dolgetta, H. Buttgereit, O. Pogutse, Y. Agarici, S. M. Scott, S. Ishida, D. F. Start, P. E. Stott, A. Meigs, W. J. Brewerton, H. D. Falter, M. Keilhacker, J. P. Coad, V. Marchese, A. Dines, A. Gondhalekar, M. Irving, C. Gowers, H. Guo, K. Thomsen, C. Laviron, C. Gormezano, A. Taroni, A. Howman, P. Kupschus, T. Szabo, M. Ottaviani, P. Burton, P. Ageladarakis, O. N. Jarvis, J. Ehrenberg, P. Savrukhin, T. Bonicelli, M. J. Watson, Y. Baranov, H. Duquenoy, T. Brown, Ambrogio Fasoli, P. G. Doyle, P. Crawley, G. Radford, L. P. D. F. Jones, B. E. Keen, P. Noll, M. Brandon, U. Gerstel, T. Winkel, R. Smith, J. F. Junger, E. Lyadina, P. Barker, F. Nave, P. J. Howarth, M. Lennholm, K. Blackler, H. McBryan, C. Grisolia, R. Sartori, and H. Summers

Subjects
Physics, Jet (fluid), Nuclear engineering, Divertor, Plasma, Condensed Matter Physics, Power (physics), Nuclear physics, Nuclear Energy and Engineering, ___, Power handling, Electron heating, Current (fluid), Scaling
Abstract

JET was extensively modified in the 1992/93 shutdown. The new pumped divertor and many new systems were brought into operation early in 1994. Operations have progressed to 4MA plasma current and, with substantial additional heating, H-mode confinement results confirm the expected scaling. The high power handling capability of the pumped divertor with sweeping is estimated at 20MW for 20s. H-mode plasmas have large Type I ELMs. With lower hybrid heating alone, 2MA full current drive has been achieved with good efficiency, with ICRF power, effective heating and direct electron heating have been demonstrated.

Published
1994
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22. Impact of Thermo-Oxidative Wall Conditioning on the Performance of Diagnostic Mirrors for ITER

Author

Litnovsky, A., Matveeva, M., Rudakov, D. L., Chrobak, C. P., Allen, S. L., Leonard, A. W., Taylor, P. L., Wong, C. P. C., Fitzpatrick, B. W. N., Davis, J. W., Haasz, A. A., Stangeby, P. C., Breuer, U., Philipps, V., and MÖller, S.

Abstract

AbstractThermo-oxidation is controlled exposure in an oxygen-containing atmosphere at elevated temperature and is being considered as a technique for the de-tritiation of carbon-based codeposits in ITER. In addition, unplanned oxidation may also occur during accidental air ingress. The impact of thermo-oxidation on ITER diagnostic mirrors causes concerns. A dedicated study was performed in DIII-D, where molybdenum and copper mirrors were installed in the main chamber, in the divertor, and at a location remote from the plasma and exposed for ~2 hours to a mixture containing 80% helium and 20% oxygen at a total pressure of 1.27 kPa. Mirrors in the main chamber and in the divertor were exposed at 350°C to 360°C whereas the temperature of mirrors in the remote area was ~160°C.Reflectivity of all mirrors was degraded after thermo-oxidation showing a decrease in the UV range from 60% to 10% for molybdenum mirrors and a 90% drop for copper mirrors at the wavelength 250 nm. The reflectivity of mirrors exposed at lower temperature was less degraded. Surface analyses revealed formation of oxides on all mirrors.In ITER, shutters planned for mirror protection are ineffective against thermo-oxidation. Nevertheless, in-situ cleaning systems planned for ITER mirrors may efficiently remove oxide layers.

Published
2012
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23. Assessment of Collateral Effects of Thermo-Oxidation on DIII-D In-Vessel Components in Preparation for In Situ Oxidation in DIII-D

Author

Fitzpatrick, B. W. N., Davis, J. W., Haasz, A. A., McLean, A. G., Stangeby, P. C., Allen, S. L., Ellis, R., and West, W. P.

Abstract

AbstractCarbon-based codeposits formed in carbon-containing fusion devices have the potential to dominate tritium retention in the torus. One of the tritium removal techniques currently being studied is thermo-oxidation, which is unique in its ability to remove tritium from codeposits without mechanical intervention in the torus and in its ability to remove tritium from codeposits in tile gaps and shaded areas. In preparation for an oxidation experiment planned to be performed in DIII-D, we have investigated the potential collateral effects of thermo-oxidation on DIII-D in-vessel components. Laboratory oxidation experiments were performed at 2 Torr ([approximately]270 Pa) and 15 Torr ([approximately]2 kPa) O2pressure and temperatures in the range 100 to 350°C (373 to 623 K) for 2 to 8 h. After oxidation, components were examined for visual or mechanical change, and when appropriate, mass changes were also obtained. In some cases, optical diagnostics were also performed. The specimens were mostly spare/surplus components and spanned a wide variety of materials and functions, e.g., cryopump components; structural, mechanical, and diagnostic components; and fast-wave antennas. The effect of oxidation was found to be negligible for nearly all DIII-D components and materials tested.

Published
2010
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24. Particle and parallel momentum balance equations with inclusion of drifts, for modelling strong- to weakly-collisional edge plasmas

Author

Chankin, A. V. and Stangeby, P. C.

Abstract

A system of plasma particle and parallel momentum balance equations is derived appropriate for understanding the role of drifts in the edge and for edge modelling, particularly in the scrape-off layer (SOL) of tokamaks, stellarators and other magnetic confinement devices. The formulation allows for strong collisionality-but also covers the case of weak collisionality and strong drifts, a combination often encountered in the SOL. The most important terms are identified by assessing the magnitude of characteristic velocities and fluxes for the plasma edge region. Explanations of the physical nature of each term are provided. A number of terms that are sometimes not included in edge modelling has been included in the parallel momentum balance equation after detailed analysis of the parallel component of the gradient of the total pressure-stress tensor. This includes terms related to curvature and divergence of the field lines, as well as further contributions coming from viscous forces related mainly to the ion centrifugal drift. All these terms are shown to be roughly of the same order of magnitude as convective momentum fluxes related to drifts and therefore should be included in the momentum balance equation.

Published
2006
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25. Far SOL transport and main wall plasma interaction in DIII-D

Author

Rudakov, D.L. DR, Boedo, J.A. JB, Moyer, R.A. RM, Stangeby, P.C. PS, Watkins, J.G. JW, Whyte, D.G. DW, Zeng, L. LZ, Brooks, N.H. NB, Doerner, R.P. RD, Evans, T.E. TE, Fenstermacher, M.E. MF, Groth, M. MG, Hollmann, E.M. EH, Krasheninnikov, S.I. SK, Lasnier, C.J. CL, Leonard, A.W. AL, Mahdavi, M.A. MM, McKee, G.R. GM, McLean, A.G. AM, Pigarov, A.Yu. AP, Wampler, W.R. WW, Wang, G. GW, West, W.P. WW, and Wong, C.P.C. CW

Abstract

Far Scrape-Off Layer (SOL) and near-wall plasma parameters in DIII-D depend strongly on the discharge parameters and confinement regime. In L-mode discharges cross-field transport increases with the average discharge density and flattens far SOL profiles, thus increasing plasma contact with the low field side (LFS) main chamber wall. In H-mode between edge localized modes (ELMs) the plasma–wall contact is weaker than in L-mode. During ELM fluxes of particles and heat to the LFS wall increase transiently above the L-mode values. Depending on the discharge conditions, ELMs are responsible for 30–90% of the net ion flux to the outboard chamber wall. ELMs in high density discharges feature intermittent transport events similar to those observed in L-mode and attributed to blobs of dense hot plasma formed inside the separatrix and propagating radially outwards. Though the blobs decay with radius, some of them survive long enough to reach the outer wall and possibly cause sputtering. In lower density H-modes, ELMs can feature blobs of pedestal density propagating all the way to the outer wall.

Published
2005

26. Overview of the Alcator C-Mod program

Author

Greenwald, M. MG, Andelin, D. DA, Basse, N. NB, Bernabei, S. SB, Bonoli, P. PB, Böse, B. BB, Boswell, C. CB, Bravenec, R. RB, Carreras, B. BC, Cziegler, I. IC, Edlund, E. EE, Ernst, D. DE, Fasoli, C. CF, Ferrara, M. MF, Fiore, C. CF, Granetz, R. RG, Grulke, O. OG, Hender, T. TH, Hosea, J. JH, Howell, D.H. DH, Hubbard, A. AH, Hughes, J. JH, Hutchinson, I. IH, Ince-Cushman, A. AI, Irby, J. JI, LaBombard, B. BL, LaHaye, R. RL, Lin, L. LL, Lin, Y. YL, Lipschultz, B. BL, Liptac, J. JL, Lisgo, S. SL, Lynn, A. AL, Marmar, E. EM, Marr, K. KM, Mikkelsen, D.R. DM, McDermott, R. RM, Mossessian, D. DM, Parisot, A. AP, Parker, R. RP, Phillips, C. CP, Phillips, P. PP, Porkolab, M. MP, Redi, M. MR, Rice, J. JR, Rowan, W. WR, Sampsell, M. MS, Schilling, G. GS, Scott, S. SS, Scoville, J.T. JS, Smick, N. NS, Snipes, J. JS, Stangeby, P. PS, Tang, V. VT, Terry, J. JT, Ulrickson, M. MU, Wallace, G. GW, Whyte, D. DW, Wilson, J. JW, Wright, J. JW, Wolfe, S. SW, Wukitch, S. SW, Youngblood, B. BY, Yuh, H. HY, Zhurovich, K. KZ, and Zweben, S. SZ

Abstract

Research on the Alcator C-Mod tokamak has emphasized RF heating, self-generated flows, momentum transport, scrape-off layer (SOL) turbulence and transport and the physics of transport barrier transitions, stability and control. The machine operates with PRF up to 6 MW corresponding to power densities on the antenna of 10 MW m−2. Analysis of rotation profile evolution, produced in the absence of external drive, allows transport of angular momentum in the plasma core to be computed and compared between various operating regimes. Momentum is clearly seen diffusing and convecting from the plasma edge on time scales similar to the energy confinement time and much faster than neo-classical transport. SOL turbulence and transport have been studied with fast scanning electrostatic probes situated at several poloidal locations and with gas puff imaging. Strong poloidal asymmetries are found in profiles and fluctuations, confirming the essential ballooning character of the turbulence and transport. Plasma topology has a dominant effect on the magnitude and direction of both core rotation and SOL flows. The correlation of self-generated plasma flows and topology has led to a novel explanation for the dependence of the H-mode power threshold on the ∇B drift direction. Research into internal transport barriers has focused on control of the barrier strength and location. The foot of the barrier could be moved to larger minor radius by lowering q or BT. The barriers, which are produced in C-Mod by off-axis RF heating, can be weakened by the application of on-axis power. Gyro-kinetic simulations suggest that the control mechanism is due to the temperature dependence of trapped electron modes which are destabilized by the large density gradients. A set of non-axisymmetric coils was installed allowing intrinsic error fields to be measured and compensated. These also enabled the determination of the mode locking threshold and, by comparison with data from other machines, provided the first direct measurement of size scaling for the threshold. The installation of a new inboard limiter resulted in the reduction of halo currents following disruptions. This effect can be understood in terms of the change in plasma contact with the altered geometry during vertical displacement of the plasma column. Unstable Alfven eigenmodes (AE) were observed in low-density, high-power ICRF heated plasmas. The damping rate of stable AEs was investigated with a pair of active MHD antennae.

Published
2005

27. Developing Models for the DIII-D Boundary Plasma

Author

Porter, G. D., Rognlien, T. D., Rensink, M. E., Wolf, N. S., and Stangeby, P. C.

Abstract

AbstractDevelopment of the comprehensive codes used to study the boundary region of the DIII-D tokamak has been done in parallel with improvement of the diagnostics of this important region of the plasma. These codes have been used to interpret the diagnostic data and to assist in the design of improved divertor configurations. The development of codes used for analysis on DIII-D is described briefly. Model validation by comparing with the extensive DIII-D boundary region diagnostic data is also discussed.

Published
2005
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28. Pedestal Studies in DIII-D

Author

Groebner, R. J., Osborne, T. H., Fenstermacher, M. E., Leonard, A. W., Mahdavi, M. A., Moyer, R. A., Owen, L. W., Porter, G. D., Snyder, P. B., Stangeby, P. C., Rhodes, T. L., and Wolf, N. S.

Abstract

AbstractStudies of the H-mode pedestal in the DIII-D tokamak are presented. The global energy confinement increases as the plasma pressure on top of the pedestal increases. The best empirical description for a pedestal width parameter is Δpe∝ (βpolPED)0.4, where Δpeis the width of the electron pressure pedestal and βpolPEDis the poloidal beta at the top of the pedestal. The edge profiles of electron density ne, electron temperature Te, and ion temperature Tican all have different shapes. Thus, a simple width scaling for the edge might not exist, and studies of the physics of individual profiles have been initiated. A model for the neprofile, based on self-consistent treatment of edge particle sources and edge particle transport, agrees with several experimental observations. The steep gradient region for the Teprofile often extends farther into the plasma than the nepedestal step. Magnetohydrodynamic stability provides the ultimate limits to the evolution of the pedestal and usually leads to edge instabilities called edge-localized modes (ELMs). However, the absence of ELMs in a regime called the Quiescent H-mode shows that large pedestals can be produced without ELMs.

Published
2005
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29. The magnitude of plasma flux to the main-wall in the DIII-D tokamak

Author

Whyte, D G, Lipschultz, B L, Stangeby, P C, Boedo, J, Rudakov, D L, Watkins, J G, and West, W P

Abstract

The magnitude of plasma contact with main-wall surfaces is examined on the DIII-D poloidal divertor tokamak. A 'window-frame' technique has been developed for axisymmetric surfaces to provide measurements of total plasma flux (ions?s?1) to the walls, Iwall. Despite the use of a separatrix-wall gap that is 2-3 times the radial e-folding length of the plasma parameters near the separatrix, increasing e-folding lengths away from the separatrix result in an Iwallof similar magnitude to the ion flux received by the divertor plate, Idiv. The Iwall/Idivratio increases strongly with line-averaged density and ranges from ~0.1-0.2 with attached outer divertor plasmas to ~1 with detached divertor plasmas. These observations hold during core density scans in both low (L-mode) and high (H-mode) confinement energy confinement regimes, and their importance to core fuelling and impurities is discussed. It is found that the magnitude of Iwallcannot be accurately measured by arbitrary main chamber D-? views due to the strong poloidal and toroidal asymmetry of the plasma contact. However D-? measurements reflect the relative trends of main-chamber recycling. Based on scrape-off layer (SOL) profiles in the shadow of the main-wall baffle, the far SOL cross-field particle transport is best described as convective with an effective velocity ~100?m?s?1.

Published
2005
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30. Comparison of H-mode barrier width with a model of neutral penetration length

Author

Groebner, R.J., Mahdavi, M.A., Leonard, A.W., Osborne, T.H., Wolf, N.S., Porter, G.D., Stangeby, P.C., Brooks, N.S., Colchin, R.J., and Owen, L.W.

Abstract

Pedestal studies in DIII-D find that the width of the region of steep gradient in the H-mode density is comparable with the neutral penetration length, as computed from a simple analytic model. This model has analytic solutions for the edge plasma and neutral density profiles, which are obtained from the coupled particle continuity equations for electrons and deuterium atoms. In its range of validity (edge temperature between 40 and 500 eV), the analytic model quantitatively predicts the observed decrease in the width as the pedestal density increases and the observed strong increase in the gradient of the density as the pedestal density increases. The model successfully predicts that L-mode and H-mode profiles with the same pedestal density have gradients that differ by less than a factor of 2. The width of the density barrier, measured from the edge of the electron temperature barrier, is the lower limit for the observed width of the temperature barrier. These results support the hypothesis that particle fuelling is an important part of the physics that determines the structure of the H-mode transport barrier.

Published
2004

31. ELM driven divertor target currents on TCV

Author

Pitts, R.A. RP, Alberti, S. SA, Blanchard, P. PB, Horacek, J. JH, Reimerdes, H. HR, and Stangeby, P.C. PS

Abstract

There is currently both considerable interest in the physics of ELM transport in the scrape-off layer (SOL) and concern over the impact of the ELM power and particle loads on the divertor targets of future fusion reactors. This paper describes some experimental observations of the reaction of target floating potentials and currents during ELMs in TCV, relying principally on fast measurements of these parameters using tile embedded Langmuir probe arrays. Clear evidence is presented for rapid modifications in the local target floating potentials occurring long before the characteristic rise of hydrogenic excitation emission due to local recycling provoked by the arrival at the target of the ELM ion flux. This precursor activity appears to be synchronous with the growth of MHD modes in the main chamber. Simple conditional averaging is used to derive a ‘coherent ELM’ and thus generate the radial distribution of the current to probes held at the target potential. At some locations, the coherent ELM can also be used to estimate the time evolution of the local target electron temperature, density and power flux, even though these quantities are not directly measured. The time delays between the reactions of currents, floating potentials and derived temperature are consistent with the expections of recently published kinetic simulations of ELM energy transport down a one-dimensional SOL plasma. The strong potential variations observed during the ELM are the result of current flows at the targets. These currents are generally of opposite sign at inner and outer divertors and are thus consistent, at least in part, with a thermoelectric origin in which the driven current is produced by an in/out divertor temperature asymmetry near the strike point of nearly a factor 2, probably due to the generation of divertor asymmetries by the ELM heat pulse. Such asymmetries are commonly observed in low to medium density L-modes for the particular TCV magnetic equilibrium studied in this paper. The total current balance during the ELM is satisfied only to within a factor 2, so that, whilst some of the driven current flows parallel to field lines in the SOL, there is an apparent additional negative current to the inner divertor during the ELM whose origin remains unexplained. It might, however, be due, in part, to increased plasma–wall interaction in the main chamber during the ELM event.

Published
2003

32. ELMs mitigation by manipulation of divertor target currents

Author

Stangeby, P.C.

Abstract

The very high heat flux density onto divertor targets that occurs during edge localized modes (ELMs) poses problems for the design of burning plasma fusion devices such as ITER. Large (net) currents flow to diverter targets during ELMs. If the current to a target tile is made to pass to machine earth through an external resistor then the plasma potential in the flux tube subtended by that tile will be increased above that in toroidally adjacent flux tubes which are subtended by tiles connected directly to machine earth. Thus, an electric field E perpendicular to B and in the poloidal plane will arise between toroidally adjacent flux tubes resulting in a time-dependant radial E×B drift during the ELM pulse, potentially distributing the energy deposited on the target over a large area. A number of uncertainties in this picture will require experimental resolution.

Published
2003

33. Evolution of TFTR scrape-off plasmas with neutral beam injection

Author

D.B. Heifetz, R. Papes, Dennis M. Manos, P. Stangeby, M. Ulrickson, Robert Budny, S. J. Kilpatrick, and D. K. Owens

Subjects
Nuclear and High Energy Physics, Chemistry, Flux, Plasma, Neutral beam injection, Ion, symbols.namesake, Nuclear Energy and Engineering, Physics::Plasma Physics, Ionization, Limiter, symbols, Langmuir probe, General Materials Science, Atomic physics, Beam (structure)
Abstract

Langmuir probe radial scans were achieved for several types of neutral beam heated 0.8 MA discharges in TFTR. The I(V) characteristics were analysed to derive ne and Te profiles and extrapolated to infer the global particle confinement time τp(t). A one-dimensional edge model was used to infer transport coefficients before and during neutral beam injection. The model indicates that ionization in the scrape-off increases the ion flux to the limiter by a factor ∼ 2 and alters the transport coefficients.

Published
1987
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34. JET: Recent results and edge phenomena

Author

J.A. Tagle, P.E. Stott, P.D. Morgan, K. Sonnenberg, M.F. Stamp, J.P. Coad, H. Bergsåker, J Jacquinot, J.P. Christiansen, B. Denne, P. R. Thomas, K.J. Dietz, S.K. Erents, K. Thomsen, David Campbell, D. Goodall, A. Boschi, F.C. Schüller, E. Lazzaro, G. Duesing, H. Brinkschulte, J. Partridge, M. Valisa, G. Israel, W. Møller, J. Hemmerich, S. Gregoli, A. Gondhalekar, J. G. Cordey, M. J. Forrest, J. von Seggern, P. Harbour, B. Emmoth, W. Engelhardt, M. Bures, R. Behrisch, R.J. Bickerton, P. Stangeby, G.M. McCracken, P. J. Lomas, E. Thompson, E. Braun, K.H. Behringer, L. De Kock, P. Børgesen, A. Tanga, Jochen Linke, P.P. Lallia, C. Lowry, D. Summers, K. Koizlik, and M.L. Watkins

Subjects
Nuclear and High Energy Physics, Jet (fluid), Tokamak, Hydrogen, Chemistry, Plasma parameters, chemistry.chemical_element, Plasma, law.invention, symbols.namesake, Nuclear Energy and Engineering, law, Limiter, symbols, Langmuir probe, General Materials Science, Atomic physics, Joule heating
Abstract

Ohmic heating studies in hydrogen and deuterium up to currents of Ip = 5 MA have been completed and additional heating experiments by means of ICRH and NBI are now in process. With ICRH powers up to 7 MW, the global energy confinement time τE is observed to deteriorate with increasing heating power. NBI experiments are at a more preliminary stage, but also show deterioration in τE. Detailed studies of confinement time scaling in ohmically heated discharges show a strong dependence of plasma size, τE ∼ R1.7a1.3, but a much weaker dependence on q and ne than seen in smaller experiments. Boundary phenomena have been studied from early 1984. Data on the impurity coverage of limiters and wall have been collected during three successive experimental campaigns. Substantial amounts of wall material have consistently been found on the limiters and a large inventory of hydrogen isotopes concentrated on the colder edges. The wall in the shadow of protective elements shows non-uniform erosion. Langmuir probe measurements of edge plasma parameters have been taken in OH, RF and NB discharges. Additional heating leads generally to a temperature increase of the scrape-off layer. Model calculations using data from these diagnostics seem to produce a consistent picture of impurity production in the scrape-off layer which agrees reasonably well with spectroscopic observations.

Published
1987
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35. Initial limiter and getter operation in TFTR

Author

E. Nieschmidt, J. Isaacson, George W. Taylor, R. J. Knize, D.J. Grove, J. Timberlake, C. E. Thomas, David W. Johnson, D. McCarthy, R. Hulse, J. D. Strachan, R. J. Hawryluk, Dale Meade, S. D. Scott, S. S. Medley, Manfred Bitter, R. Kaita, Stanley Kaye, D. R. Mikkelsen, S. J. Kilpatrick, J. Sinnis, W. R. Blanchard, M. Ulrickson, K. W. Hill, F. Tenney, Dennis M. Manos, P. C. Efthimion, J. Sredniawski, Joseph L. Cecchi, A. T. Ramsey, M. Murakami, S. L. Davis, N. R. Sauthoff, K. M. Young, N. Bretz, D. Dimock, J. Coonrod, K. McGuire, B. L. Doyle, A. L. Roquemore, D. Mueller, B. Grek, C. E. Bush, D. C. McCune, H. F. Dylla, S. von Goeler, J.F. Schivell, D. Heifetz, P. Stangeby, Samuel A. Cohen, Robert James Goldston, H. W. Hendel, M. G. Bell, R. Little, R. J. Fonck, L. C. Johnson, D. K. Owens, S. Sesnic, J. Kiraly, G. D. Tait, and H. H. Towner

Subjects
Nuclear and High Energy Physics, Materials science, Plasma heating, Nuclear engineering, Zirconium alloy, Alloy, Plasma, engineering.material, Nuclear Energy and Engineering, Getter, Limiter, Electric heating, engineering, General Materials Science, Joule heating
Abstract

During the recent ohmic heating experiments on TFTR, the movable limiter array, preliminary inner bumper limiter, and prototype ZrAl alloy bulk getter surface pumping system were brought into operation. This paper summarizes the operational experience and plasma characteristics obtained with these components. The near-term upgrades of these systems are also discussed.

Published
1984
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36. Fluctuation-driven transport in the DIII-D boundary

Author

Rudakov, D L, Boedo, J A, Moyer, R A, Krasheninnikov, S, Leonard, A W, Mahdavi, M A, McKee, G R, Porter, G D, Stangeby, P C, Watkins, J G, West, W P, Whyte, D G, and Antar, G

Abstract

Cross-field fluctuation-driven transport is studied in edge and scrape-off layer (SOL) plasmas in the DIII-D tokamak using a fast reciprocating Langmuir probe array allowing local measurements of the fluctuation-driven particle and heat fluxes. Two different non-diffusive mechanisms that can contribute strongly to the cross-field transport in the SOL of high-density discharges are identified and compared. The first of these involves intermittent transport events that are observed at the plasma separatrix and in the SOL. Intermittence has qualitatively similar character in L-mode and ELM-free H-mode. Low-amplitude ELMs observed in high-density H-mode produce in the SOL periods with cross-field transport enhanced to L-mode levels and featuring intermittent events similar to those in L-mode. The intermittent transport events are compatible with the concept of plasma filaments propagating across the SOL due to E×B drifts. The intermittent character of the transport in the SOL is also in agreement with predictions of the non-linear numerical simulations performed with an imposed driving flux. Another type of non-diffusive transport is often seen in high-density H-modes with prolonged ELM-free periods, where the transport near the separatrix is dominated by quasi-coherent modes driving particle and/or heat fluxes exceeding L-mode levels. These modes may play an important role by providing particle and/or heat exhaust between ELMs.

Published
2002
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37. High performance H mode plasmas at densities above the Greenwald limit

Author

Mahdavi, M.A., Osborne, T.H., Leonard, A.W., Chu, M.S., Doyle, E.J., Fenstermacher, M.E., McKee, G.R., Staebler, G.M., Petrie, T.W., Wade, M.R., Allen, S.L., Boedo, J.A., Brooks, N.H., Colchin, R.J., Evans, T.E., Greenfield, C.M., Porter, G.D., Isler, R.C., Haye, R.J. La, Lasnier, C.J., Maingi, R., Moyer, R.A., Schaffer, M.J., Stangeby, P.G., Watkins, J.G., West, W.P., Whyte, D.G., and Wolf, N.S.

Abstract

Densities of up to 40% above the Greenwald limit are reproducibly achieved in high confinement (HITER89P = 2) ELMing H mode discharges. Simultaneous gas fuelling and divertor pumping were used to obtain these results. Confinement of these discharges, similar to moderate density H mode, is characterized by a stiff temperature profile, and is therefore sensitive to the density profile. A particle transport model is presented that explains the roles of divertor pumping and geometry for access to high densities. The energy loss per ELM at high density is a factor of five lower than the predictions of an earlier scaling, based on data from lower density discharges.

Published
2002
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46. Simple models for the radial and poloidal E B drifts in the scrape-off layer of a divertor tokamak: Effects on in/out asymmetries

Author

Stangeby, P.C. and Chankin, A.V.

Abstract

The influence of radial and poloidal E B drifts in the scrape-off layer (SOL) of a divertor tokamak is considered. For B in the `forward' direction (the ∇B ion drift towards a lower X point, single null divertor configuration), the poloidal drift tends to increase the plasma pressure and the recycling rates at the outer target, lowering the temperature there - as compared with the inner target. When the radial drift dominates, these asymmetries are reversed. The radial drift is estimated to be more important than the poloidal drift for high ne operation (the `high recycling' regime). The poloidal drift case is analysed by using a simple, isothermal model and boundary conditions at the targets which allow for the effect of drift. The radial drift case is modelled on the basis of a heuristic analysis of the viscous drag experienced by the return parallel flow along the SOL which is induced by the radial drift fluxes. Poloidal drifts can result in substantially reduced plasma contact at one target (`detachment'); simultaneous detachment at both targets due to poloidal drifts appears to be less likely. Radial drifts could result in detachment at one or both targets, but the type of detachment involved does not appear to be consistent with that experimentally observed. The experimental observations made in the Tokamak de Varennes, with divertor biasing arranged to increase/decrease the radial electric field in the SOL, relative to its natural level, are broadly consistent with the poloidal drift model

Published
1996

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