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1. High performance power handling in the absence of an H-mode edge in negative triangularity DIII-D plasmas.

Author

Scotti, F., Marinoni, A., McLean, A.G., Paz-Soldan, C., Thome, K.E., Zhao, M., Allen, S., Austin, M., Burke, M.G., Eldon, D., Fenstermacher, M., Hyatt, A., Lasnier, C.J., Leonard, A., Lore, J., Nelson, A.O., Osborne, T., Sauter, O., Truong, D., and Van Zeeland, M.A.

Subjects
PLASMA boundary layers, HEAT flux, ELECTRON temperature, PLASMA currents, PLASMA dynamics
Abstract

Experiments performed during strongly-shaped high-power diverted negative triangularity (NT) experiments in DIII-D achieved detached divertor conditions and a transient-free edge, showcasing the potential for application of NT to a core-edge integrated reactor-like scenario and providing the first characterization of the parametric dependencies for detachment onset. Detached divertor conditions will be required in future devices to mitigate divertor heat fluxes. Access to dissipative divertor conditions was investigated via an increase in upstream density. Detachment onset at the outer strike point was achieved with H-mode level confinement H 98 − y 2 ∼ 1 and reactor-relevant normalized pressures β N ∼ 2 . Confinement degradation was observed with deeper detachment, associated with the loss of an electron temperature pedestal. Differences in geometry, radial transport, impact of cross field drifts are discussed to explain differences in access to detachment in NT discharges. Higher normalized densities, with respect to equivalent discharges in positive triangularity, were necessary to achieve detachment, partially explained by the shorter parallel connection length to the targets. The effect of cross-field particle drifts (E × B, B × ∇ B) on access to detachment was demonstrated by the lower upstream density needed to access detachment with ion B × ∇ B drift directed outside of the active divertor (Greenwald fraction f Gw ∼ 0.9–1.0 vs f Gw ∼ 1.3). The upstream density at detachment onset was observed to increase linearly with plasma current with ion B × ∇ B drift into the divertor, consistent with the observed narrowing of the scrape-off layer heat flux width λ q . Edge fluid simulations capture separatrix densities needed to achieve detachment in NT plasma and their dependence on drift direction. The ability to reproduce detachment dynamics in NT plasma increases the confidence in future design studies for NT divertors. [ABSTRACT FROM AUTHOR]

Published
2024
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2. Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation

Author

Bucalossi, J., Achard, J., Agullo, O., Alarcon, T., Allegretti, L., Ancher, H., Antar, G., Antusch, S., Anzallo, V., Arnas, C., Arranger, D., Artaud, J. F., Aumeunier, M. H., Baek, S. G., Bai, X., Balbin, J., Balorin, C., Barbui, T., Barbuti, A., Barlerin, J., Basiuk, V., Batal, T., Baulaigue, O., Bec, A., Bécoulet, M., Benoit, E., Benard, E., Benard, J. M., Bertelli, N., Bertrand, E., Beyer, P., Bielecki, J., Bienvenu, P., Bisson, R., Bobkov, V., Bodner, G., Bottereau, C., Bouchand, C., Bouquey, F., Bourdelle, C., Bourg, J., Brezinsek, S., Brochard, F., Brun, C., Bruno, V., Bufferand, H., Bureau, A., Burles, S., Camenen, Y., Cantone, B., Caprin, E., Carpentier, S., Caulier, G., Chanet, N., Chellai, O., Chen, Y., Chernyshova, M., Chmielewski, P., Choe, W., Chomiczewska, A., Ciraolo, G., Clairet, F., Coenen, J., Colas, L., Colledani, G., Colnel, J., Coquillat, P., Corbel, E., Corre, Y., Costea, S., Courtois, X., Czarski, T., Daniel, R., Daumas, J., De Combarieu, M., Temmerman, G., De, De Vries, P., Dechelle, C., Deguara, F., Dejarnac, R., Delaplanche, J. M., Delgado-Aparicio, L. F., Delmas, E., Delpech, L., Desgranges, C., Devynck, P., Di Genova, S., Diab, R., Diallo, A., Diez, M., Dif-Pradalier, G., Dimitrova, M., Ding, B., Dittmar, T., Doceul, L., Domenes, M., Douai, D., Dougnac, H., Duan, X., Dubus, L., Dumas, N., Dumont, R., Durand, F., Durif, A., Durocher, A., Durodié, F., Ekedahl, A., Elbeze, D., Ertmer, S., Escarguel, A., Escourbiac, F., Ezato, K., Faisse, F., Faure, N., Fedorczak, N., Fejoz, P., Fenzi-Bonizec, C., Ferlay, F., Firdaouss, M., Fleury, L., Flouquet, D., Gallo, A., Gao, Y., Garbet, X., Garcia, J., Gardarein, J. L., Gargiulo, L., Garibaldi, P., Garitta, S., Gaspar, J., Gauthier, E., Gavila, P., Gazzotti, S., Gely, F., Geynet, M., Gharafi, S., Ghendrih, P., Giacalone, I., Gil, C., Ginoux, S., Girard, S., Giroux, E., Giruzzi, G., Goletto, C., Goniche, M., Gray, T., Grelier, E., Greuner, H., Grigore, E., Grisolia, C., Grosjean, A., Grosman, A., Guibert, D., Guilhem, D., Guillemaut, C., Guillermin, B., Guirlet, R., Gunn, J. P., Gunsu, Y., Gyergyek, T., Hakola, A., Harris, J., Hatchressian, J. C., Helou, W., Hennequin, P., Hernandez, C., Hill, K., Hillairet, J., Hirai, T., Hoang, G. T., Houry, M., Hutter, T., Imbeaux, F., Imbert, N., Ivanova-Stanik, I., Jalageas, R., Jardin, A., Jaubert, L., Jiolat, G., Jonas, A., Joubert, P., Kirschner, A., Klepper, C., Komm, M., Koubiti, M., Kovacic, J., Kozeiha, M., Krieger, K., Krol, K., Lacroix, B., Laguardia, L., Lamaison, V., Laqua, H., Lau, C., Lausenaz, Y., Lé, R., Le Bohec, M., Lefevre, N., Lemoine, N., Lerche, E., Lewerentz, M., Li, Y., Li, M., Liang, A., Linczuk, P., Linsmeier, C., Lipa, M., Litaudon, X., Liu, X., Llorens, J., Loarer, T., Loarte, A., Loewenhoff, T., Lombard, G., Lore, J., Lorenzetto, P., Lotte, P., Lozano, M., Lu, B., Lunsford, R., Luo, G., Magaud, P., Maget, P., Mahieu, J. F., Maini, P., Malard, P., Malinowski, K., Manas, P., Manenc, L., Marandet, Y., Marechal, J. L., Marek, S., Martin, C., Martin, E., Martinez, A., Martino, P., Mazon, D., Messina, P., Meunier, L., Midou, D., Mineo, Y., Missilian, M., Mitteau, R., Mitu, B., Mollard, P., Moncada, V., Mondiere, T., Morales, J., Moreau, M., Moreau, P., Moudden, Y., Moureau, G., Mouyon, D., Muraglia, M., Nagy, A., Nakano, T., Nardon, E., Neff, A., Nespoli, F., Nichols, J., Nicollet, S., Nouailletas, R., Ono, M., Ostuni, V., Parish, C., Park, H., Parrat, H., Pascal, J. Y., Pégourié, B., Pellissier, F. P., Peneliau, Y., Peret, M., Peysson, Y., Pignoly, E., Pintsuk, G., Pitts, R., Pocheau, C., Portafaix, C., Poulos, M., Prochet, P., Puig Sitjes, A., Rasinski, M., Raup, G., Regal-Mezin, X., Reux, C., Riccardi, B., Rice, J., Richou, M., Rigollet, F., Roche, H., Romazanov, J., Ruset, C., Sabot, R., Saille, A., Sakamoto, R., Salmon, T., Samaille, F., Santagiustina, A., Santraine, B., Sarazin, Y., Serre, E., Shin, H., Shiraiwai, S., Signoret, Ja., Signoret, Je., Simonin, A., Skalli Fettachi, O., Song, Y., Spring, A., Spuig, P., Sridhar, S., Stratton, B., Talatizi, C., Tamain, P., Tatali, R., Téna, M., Torre, A., Toulouse, L., Travère, J. M., Treutterer, W., Tsitrone, E., Unterberg, E., Urbanczyk, G., Van Eester, D., Van Rooij, G., Vartanian, S., Verger, J. M., Vermare, L., Vézinet, D., Vignal, N., Vincent, B., Vives, S., Volpe, D., Wallace, G., Wang, E., Wang, L., Wang, Yi., Wang, Yo., Wauters, T., Wirth, B., Wirtz, M., Wojenski, A., Wright, J., Xu, M., Yang, Q., Yang, H., Zago, B., Zagorski, Zhang, B., Zhang, X., Zou, X., Institut universitaire des systèmes thermiques industriels (IUSTI), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Laboratoire de Physique des Plasmas (LPP), Observatoire de Paris, and Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL)-École polytechnique (X)-Sorbonne Université (SU)-Université Paris-Saclay-Centre National de la Recherche Scientifique (CNRS)

Subjects
Nuclear and High Energy Physics, Tokamak, Materials science, WEST, Nuclear engineering, Phase (waves), chemistry.chemical_element, Tungsten, law.invention, [PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], law, ITER, divertor, DEMO, Engineering & allied operations, nuclear fusion, Superconductivity, [PHYS]Physics [physics], Divertor, RF power amplifier, magnetic confinement, Plasma, Condensed Matter Physics, chemistry, Heat flux, ddc:620, tokamak physics
Abstract

WEST is an MA class superconducting, actively cooled, full tungsten (W) tokamak, designed to operate in long pulses up to 1000 s. In support of ITER operation and DEMO conceptual activities, key missions of WEST are: (i) qualification of high heat flux plasma-facing components in integrating both technological and physics aspects in relevant heat and particle exhaust conditions, particularly for the tungsten monoblocks foreseen in ITER divertor; (ii) integrated steady-state operation at high confinement, with a focus on power exhaust issues. During the phase 1 of operation (2017–2020), a set of actively cooled ITER-grade plasma facing unit prototypes was integrated into the inertially cooled W coated startup lower divertor. Up to 8.8 MW of RF power has been coupled to the plasma and divertor heat flux of up to 6 MW m−2 were reached. Long pulse operation was started, using the upper actively cooled divertor, with a discharge of about 1 min achieved. This paper gives an overview of the results achieved in phase 1. Perspectives for phase 2, operating with the full capability of the device with the complete ITER-grade actively cooled lower divertor, are also described.

Published
2022

3. Aspects of steady-state operation of the Wendelstein 7-X stellarator.

Author

Geiger, J., Wolf, R. C., Beidler, C., Cardella, A., Chlechowitz, E., Erckmann, V., Gantenbein, G., Hathiramani, D., Hirsch, M., Kasparek, W., Kißlinger, J., König, R., Kornejew, P., Laqua, H. P., Lechte, C., Lore, J., Lumsdaine, A., Maaßberg, H., Marushchenko, N. B., and Michel, G.

Subjects
STELLARATORS, STEADY-state flow, ION temperature, PLASMA density, HEAT flux, CYCLOTRON resonance
Abstract

The objective of Wendelstein 7-X is to demonstrate steady-state operation at β-values of up to 5%, at ion temperatures of several keV and plasma densities of up to 2 × 1020 m-3. The second operational phase foresees a fully steady-state high heat flux (HHF) divertor. Preparations are underway to cope with residual bootstrap currents, either by electron cyclotron current drive or by HHF protection elements. The main steady-state heating system is an electron cyclotron resonance heating facility. Various technical improvements of the gyrotrons have been implemented recently. They enable a reliable operation at the 1 MW power level. Some of the technical issues preparing plasma diagnostics for steady-state operation are exemplified. This includes the protection against non-absorbed microwave radiation. [ABSTRACT FROM AUTHOR]

Published
2013
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4. Implementation of the 3D edge plasma code EMC3-EIRENE on NSTX.

Author

Lore, J. D., Canik, J. M., Feng, Y., Ahn, J.-W., Maingi, R., and Soukhanovskii, V.

Subjects
*PLASMA gases, *TOKAMAKS, *NUCLEAR physics, *MAGNETIC fields, *SYMMETRY (Physics), *HEAT flux, *PERTURBATION theory, *COMPUTER simulation, *PHYSICS software
Abstract

The 3D edge transport code EMC3-EIRENE has been applied for the first time to the NSTX spherical tokamak. A new disconnected double null grid has been developed to allow the simulation of plasma where the radial separation of the inner and outer separatrix is less than characteristic widths (e.g. heat flux width) at the midplane. Modelling results are presented for both an axisymmetric case and a case where 3D magnetic field is applied in an n = 3 configuration. In the vacuum approximation, the perturbed field consists of a wide region of destroyed flux surfaces and helical lobes which are a mixture of long and short connection length field lines formed by the separatrix manifolds. This structure is reflected in coupled 3D plasma fluid (EMC3) and kinetic neutral particle (EIRENE) simulations. The helical lobes extending inside of the unperturbed separatrix are filled in by hot plasma from the core. The intersection of the lobes with the divertor results in a striated flux footprint pattern on the target plates. Profiles of divertor heat and particle fluxes are compared with experimental data, and possible sources of discrepancy are discussed. [ABSTRACT FROM AUTHOR]

Published
2012
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5. Effect of nonaxisymmetric magnetic perturbations on divertor heat and particle flux profiles in National Spherical Torus Experiment.

Author

Ahn, J-W., Maingi, R., Canik, J. M., McLean, A. G., Lore, J. D., Park, J.-K., Soukhanovskii, V. A., Gray, T. K., and Roquemore, A. L.

Subjects
QUANTUM perturbations, MAGNETIC fields, TOKAMAKS, HEAT flux, SYMMETRY breaking, ELECTRIC coils, TOROIDAL magnetic circuits
Abstract

Small, nonaxisymmetric magnetic perturbations generated by external coils have been found to break the axisymmetry of heat and particle flux deposition pattern in the divertor area in the National Spherical Torus Experiment (NSTX). This breaking by the applied 3-D field causes strike point splitting that is represented as local peaks and valleys in the divertor profiles. In case of n = 3 fields application, the broken toroidal symmetry of the divertor profile shows 120° of spatial periodicity while data for n = 1 fields provide a fully nonaxisymmetric heat and particle deposition. Field line tracing showed good agreement with the measured heat and particle flux profiles. Higher toroidal mode number (n = 3) of the applied perturbation produced more and finer striations in the divertor profiles than in the lower mode number (n = 1) case. Following the previous result of the intrinsic strike point splitting by the n = 3 error fields [Nucl. Fusion 50, 045010 (2010); J. Nucl. Mater. (2011), doi:10.1016/j.jnucmat.2011.01.115], result of the connection length profile from field line tracing identifies intrinsic error field as a possible source of the intrinsic splitting. In determining the strike point splitting pattern, q95 is found to play an important role; higher q95 produces finer striations and induces higher fraction of heat flux to flow through the split strike point channels. Higher pedestal electron collisionality also made the striations in the Dα profile more pronounced in the given range of collisionality variation. The radial location of local peaks in the profiles during the triggered edge localized modes (ELMs) by the applied n = 3 fields stays similar before and after the application. This shows that the heat flux from the triggered ELMs follows the mode number of the applied perturbation. The external magnetic perturbation can reattach detached divertor plasma, but this can be overcome by detaching the plasma with additional divertor gas puffing. [ABSTRACT FROM AUTHOR]

Published
2011
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6. Design and analysis of the W7-X divertor scraper element.

Author

Lumsdaine, A., Tipton, J., Lore, J., McGinnis, D., Canik, J., Harris, J., Peacock, A., Boscary, J., Tretter, J., and Andreeva, T.

Subjects
*FUSION reactor divertors, *SCRAPERS (Tools), *THERMAL analysis, *COMPUTATIONAL fluid dynamics, *HEAT flux, *TEMPERATURE effect, *CHLOROFLUOROCARBONS, *DIFFUSION
Abstract

Highlights: [•] A high heat flux actively cooled divertor component is thermally modeled with CFD. [•] CFC monoblocks are analyzed to verify peak steady-state temperatures do not exceed 1200°C. [•] A field line diffusion code is developed to determine the heat flux on the divertor components. [•] Iteration is required to develop a surface that meets the criteria and fits into the limited space. [ABSTRACT FROM AUTHOR]

Published
2013
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7. Prototyping phase of the high heat flux scraper element of Wendelstein 7-X.

Author

Boscary, J., Greuner, H., Ehrke, G., Böswirth, B., Wang, Z., Clark, E., Lumsdaine, A., Tretter, J., McGinnis, D., Lore, J., and Ekici, K.

Subjects
*HEAT flux, *PROTOTYPES, *SCRAPERS (Tools), *WATER cooled reactors, *ISOSTATIC pressing, *PLASMA gases, *FUSION reactor divertors
Abstract

The water-cooled high heat flux scraper element aims to reduce excessive heat loads on the target element ends of the actively cooled divertor of Wendelstein 7-X. Its purpose is to intercept some of the plasma fluxes both upstream and downstream before they reach the divertor surface. The scraper element has 24 identical plasma facing components (PFCs) divided into 6 modules. One module has 4 PFCs hydraulically connected in series by 2 water boxes. A PFC, 247 mm long and 28 mm wide, has 13 monoblocks made of CFC NB31 bonded by hot isostatic pressing onto a CuCrZr cooling tube equipped with a copper twisted tape. 4 full-scale prototypes of PFCs have been successfully tested in the GLADIS facility up to 20 MW/m 2 . The difference observed between measured and calculated surface temperatures is probably due to the inhomogeneity of CFC properties. The design of the water box prototypes has been detailed to allow the junction between the cooling pipe of the PFCs and the water boxes by internal orbital welding. The prototypes are presently under fabrication. [ABSTRACT FROM AUTHOR]

Published
2016
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8. DIII-D research towards establishing the scientific basis for future fusion reactors

Author

L. Abadie, T. W. Abrams, J. Ahn, T. Akiyama, P. Aleynikov, J. Allcock, E. O. Allen, S. Allen, J. P. Anderson, A. Ashourvan, M. E. Austin, J. Bak, K. K. Barada, N. Barbour, L. Bardoczi, J. Barr, J. L. Barton, E. M. Bass, D. Battaglia, L. R. Baylor, J. Beckers, E. A. Belli, J. W. Berkery, N. Bertelli, J. M. Bialek, J. A. Boedo, R. L. Boivin, P. T. Bonoli, A. Bortolon, M. D. Boyer, R. E. Brambila, B. Bray, D. P. Brennan, A. R. Briesemeister, S. A. Bringuier, M. W. Brookman, D. L. Brower, B. R. Brown, W. D. Brown, D. Buchenauer, M. G. Burke, K. H. Burrell, J. Butt, R. J. Buttery, I. Bykov, J. M. Candy, J. M. Canik, N. M. Cao, L. Carbajal Gomez, L. C. Carlson, T. N. Carlstrom, T. A. Carter, W. Cary, L. Casali, M. Cengher, V. S. Chan, B. Chen, J. Chen, M. Chen, R. Chen, Xi Chen, W. Choi, C. Chrobak, C. Chrystal, R. M. Churchill, M. Cianciosa, C. F. Clauser, M. Clement, J. Coburn, C. S. Collins, A. W. Cooper, B. M. Covele, J. W. Crippen, N. A. Crocker, B. J. Crowley, A. Dal Molin, E. M. Davis, J. S. deGrassie, C. A. del-Castillo-Negrete, L. F. Delgado-Aparicio, A. Diallo, S. J. Diem, R. Ding, S. Ding, W. Ding, J. L. Doane, D. C. Donovan, J. Drake, D. Du, H. Du, X. Du, V. Duarte, J. D. Duran, N. W. Eidietis, D. Elder, D. Eldon, W. Elwasif, T. E. Ely, K. M. Eng, K. Engelhorn, D. Ennis, K. Erickson, D. R. Ernst, T. E. Evans, M. E. Fenstermacher, N. M. Ferraro, J. R. Ferron, D. F. Finkenthal, P. A. Fisher, B. Fishler, S. M. Flanagan, J. A. Fooks, L. Frassinetti, H. G. Frerichs, Y. Fu, T. Fulop, Q. Gao, F. Garcia, A. M. Garofalo, A. Gattuso, L. Giacomelli, E. M. Giraldez, C. Giroud, F. Glass, P. Gohil, X. Gong, Y. A. Gorelov, R. S. Granetz, D. L. Green, C. M. Greenfield, B. A. Grierson, R. J. Groebner, W. H. Grosnickle, M. Groth, H. J. Grunloh, H. Y. Guo, W. Guo, J. Guterl, R. C. Hager, S. Hahn, F. D. Halpern, H. Han, M. J. Hansink, J. M. Hanson, J. Harris, S. R. Haskey, D. R. Hatch, W. W. Heidbrink, J. Herfindal, D. N. Hill, M. D. Hill, E. T. Hinson, C. T. Holcomb, C. G. Holland, L. D. Holland, E. M. Hollmann, A. M. Holm, R. Hong, M. Hoppe, S. Houshmandyar, J. Howard, N. T. Howard, Q. Hu, W. Hu, H. Huang, J. Huang, Y. Huang, G. A. Hughes, J. Hughes, D. A. Humphreys, A. W. Hyatt, K. Ida, V. Igochine, Y. In, S. Inoue, A. Isayama, R. C. Isler, V. A. Izzo, M. R. Jackson, A. E. Jarvinen, Y. Jeon, H. Ji, X. Jian, R. Jimenez, C. A. Johnson, I. Joseph, D. N. Kaczala, D. H. Kaplan, J. Kates-Harbeck, A. G. Kellman, D. H. Kellman, C. E. Kessel, K. Khumthong, C. C. Kim, H. Kim, J. Kim, K. Kim, S. H. Kim, W. Kimura, J. R. King, A. Kirk, K. Kleijwegt, M. Knolker, A. Kohn, E. Kolemen, M. Kostuk, G. J. Kramer, P. Kress, D. M. Kriete, R. J. La Haye, F. M. Laggner, H. Lan, M. J. Lanctot, R. Lantsov, L. L. Lao, C. J. Lasnier, C. Lau, K. Law, D. Lawrence, J. Le, R. L. Lee, M. Lehnen, R. Leon, A. W. Leonard, M. Lesher, J. A. Leuer, G. Li, K. Li, K. T. Liao, Z. Lin, C. Liu, F. Liu, Y. Liu, Z. Liu, S. Loch, N. C. Logan, J. M. Lohr, J. Lore, T. C. Luce, N. C. Luhmann, R. Lunsford, C. Luo, Z. Luo, L. Lupin-Jimenez, A. Lvovskiy, B. C. Lyons, X. Ma, R. Maingi, M. A. Makowski, P. Mantica, M. Manuel, M. W. Margo, A. Marinoni, E. Marmar, W. C. Martin, R. L. Masline, G. K. Matsunaga, D. M. Mauzey, P. S. Mauzey, J. T. Mcclenaghan, G. R. Mckee, A. G. Mclean, H. S. Mclean, E. Meier, S. J. Meitner, J. E. Menard, O. Meneghini, G. Merlo, W. H. Meyer, D. C. Miller, W. J. Miller, C. P. Moeller, K. J. Montes, M. A. Morales, S. Mordijck, A. Moser, R. A. Moyer, S. A. Muller, S. Munaretto, M. Murakami, C. J. Murphy, C. M. Muscatello, C. E. Myers, A. Nagy, G. A. Navratil, R. M. Nazikian, A. L. Neff, T. F. Neiser, A. Nelson, P. Nguyen, R. Nguyen, J. H. Nichols, M. Nocente, R. E. Nygren, R. C. O'Neill, T. Odstrcil, S. Ohdachi, M. Okabayashi, E. Olofsson, M. Ono, D. M. Orlov, T. H. Osborne, N. A. Pablant, D. C. Pace, R. R. Paguio, A. Pajares Martinez, C. Pan, A. Pankin, J. M. Park, J. Park, Y. Park, C. T. Parker, S. E. Parker, P. B. Parks, C. J. Pawley, C. A. Paz-Soldan, W. A. Peebles, B. G. Penaflor, T. W. Petrie, C. C. Petty, Y. Peysson, A. Y. Pigarov, D. A. Piglowski, R. I. Pinsker, P. Piovesan, N. Piper, R. A. Pitts, J. D. Pizzo, M. L. Podesta, F. M. Poli, D. Ponce, M. Porkolab, G. D. Porter, R. Prater, J. Qian, O. Ra, T. Rafiq, R. Raman, C. Rand, G. C. Randall, J. M. Rauch, C. Rea, M. L. Reinke, J. Ren, Q. Ren, Y. Ren, T. L. Rhodes, J. Rice, T. D. Rognlien, J. C. Rost, W. L. Rowan, D. L. Rudakov, A. Salmi, B. S. Sammuli, C. M. Samuell, A. M. Sandorfi, C. Sang, O. J. Sauter, D. P. Schissel, L. Schmitz, O. Schmitz, E. J. Schuster, J. T. Scoville, A. Seltzman, I. Sfiligoi, M. Shafer, H. Shen, T. Shi, D. Shiraki, H. Si, D. R. Smith, S. P. Smith, J. A. Snipes, P. B. Snyder, E. R. Solano, W. M. Solomon, A. C. Sontag, V. A. Soukhanovskii, D. A. Spong, W. M. Stacey, G. M. Staebler, L. Stagner, B. Stahl, P. C. Stangeby, T. J. Stoltzfus-Dueck, D. P. Stotler, E. J. Strait, D. Su, L. E. Sugiyama, A. A. Sulyman, Y. Sun, C. Sung, W. A. Suttrop, Y. Suzuki, A. 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Subjects
Physics, Nuclear and High Energy Physics, fusion, model, Tokamak, DIII-D, Divertor, Mechanics, Plasma, Fusion power, Dissipation, Condensed Matter Physics, 01 natural sciences, 010305 fluids & plasmas, law.invention, Pedestal, Heat flux, law, Physics::Plasma Physics, 0103 physical sciences, 010306 general physics, tokamak, plasma, energy
Abstract

DIII-D research is addressing critical challenges in preparation for ITER and the next generation of fusion devices through focusing on plasma physics fundamentals that underpin key fusion goals, understanding the interaction of disparate core and boundary plasma physics, and developing integrated scenarios for achieving high performance fusion regimes. Fundamental investigations into fusion energy science find that anomalous dissipation of runaway electrons (RE) that arise following a disruption is likely due to interactions with RE-driven kinetic instabilities, some of which have been directly observed, opening a new avenue for RE energy dissipation using naturally excited waves. Dimensionless parameter scaling of intrinsic rotation and gyrokinetic simulations give a predicted ITER rotation profile with significant turbulence stabilization. Coherence imaging spectroscopy confirms near sonic flow throughout the divertor towards the target, which may account for the convection-dominated parallel heat flux. Core-boundary integration studies show that the small angle slot divertor achieves detachment at lower density and extends plasma cooling across the divertor target plate, which is essential for controlling heat flux and erosion. The Super H-mode regime has been extended to high plasma current (2.0 MA) and density to achieve very high pedestal pressures (~30 kPa) and stored energy (3.2 MJ) with H 98y2 ≈ 1.6–2.4. In scenario work, the ITER baseline Q = 10 scenario with zero injected torque is found to have a fusion gain metric independent of current between q 95 = 2.8–3.7, and a lower limit of pedestal rotation for RMP ELM suppression has been found. In the wide pedestal QH-mode regime that exhibits improved performance and no ELMs, the start-up counter torque has been eliminated so that the entire discharge uses ≈0 injected torque and the operating space is more ITER-relevant. Finally, the high- (⩽3.8) hybrid scenario has been extended to the high-density levels necessary for radiating divertor operation, achieving ~40% divertor heat flux reduction using either argon or neon with P tot up to 15 MW.

Published
2019

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