Enhanced plasma performance in C-2W advanced beam-driven field-reversed configuration experiments

Autor: H. Gota, A. Smirnov, M.W. Binderbauer, T. Tajima, S. Putvinski, J.B. Titus, M. Nations, T. Roche, E. Trask, T. DeHaas, S.A. Dettrick, E.M. Granstedt, D.K. Gupta, S. Gupta, A.A. Ivanov, S. Korepanov, R.M. Magee, T. Matsumoto, J.A. Romero, P. Yushmanov, K. Zhai, L. Schmitz, Z. Lin, S. Krasheninnikov, E.A. Baltz, J.C. Platt, E.V. Belova, T. Asai, A.I. Smolyakov, S. Abdollahi, S. Abramov, A. Alexander, I. Allfrey, R. Andow, D.C. Barnes, B. Barnett, J. Barrett, M. Beall, N.G. Bolte, E. Bomgardner, A. Bondarenko, F. Brighenti, J. Buttery, S. Caton, F. Ceccherini, Y. Choi, R. Clary, A. Cooper, C. Deng, A. de Vera, J. Drobny, A. Dunaevsky, C. Exton, A. Fareed, P. Feng, C. Finucane, D. Fluegge, A. Fontanilla, Y. Fujiwara, L. Galeotti, S. Galkin, R. Groenewald, T. Hsyu, K. Hubbard, R. Jaber, L. Jian, N. Kafle, S. Kamio, S. Karbashewski, J.S. Kinley, A. Korepanov, G. Koumarianou, S. Krause, P. Kudrin, C.K. Lau, H. Leinweber, J. Leuenberger, D. Lieurance, M. Litton, R. Luna, R. Luong, J. MacFarlane, D. Madura, J. Margo, D. Marshall, V. Matvienko, M. Meekins, W. Melian, R. Mendoza, R. Michel, M. Morehouse, Y. Musthafa, S. Nazarenko, A. Necas, B.S. Nicks, N. Nwoke, S. Ohshima, M. Onofri, R. Page, J. Park, E. Parke, S. Patel, L. Pennings, K. Phung, G. Player, L. Rios, I. Sato, J.H. Schroeder, Y. Shimabukuro, M. Showers, A. Sibley, M. Signorelli, M. Slepchenkov, R.J. Smith, G. Snitchler, V. Sokolov, D. Solyakov, Y. Song, B. Sporer, L.C. Steinhauer, C. Stonier, A. Stratta, J. Sweeney, M. Tobin, M. Tuszewski, J. Ufnal, T. Valentine, S. Vargas, A.D. Van Drie, V. Vekselman, A. Veksler, C. Weixel, C. White, M. Wollenberg, J. Wood, Y. Zhou, S. Ziaei, the TAE Team

Publikováno v: Nuclear Fusion, Vol 64, Iss 11, p 112014 (2024)

TAE Technologies’ fifth-generation fusion device, C-2W (also called ‘Norman’), is the world’s largest compact-toroid device and has made significant progress in field-reversed configuration (FRC) plasma performance. C-2W produces record break

Externí odkaz: https://doaj.org/article/256b81cac41043c1a97676b160e67300

Toroidal field ripple loss of alphas below the critical energy in ITER

Autor: L.M. Hively, J.A. Rome

Publikováno v: Nuclear Fusion. 30:1129-1135

The toroidal field (TF) ripple loss of alphas below the critical energy (including axisymmetric neoclassical loss) is calculated for a non-circular ITER plasma. For 14 TF coils, the particle loss was found to be about 6%. About 0.6% of the initial al

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::1ee5df8133594a7fe8c377604dea36be
https://doi.org/10.1088/0029-5515/30/6/014

The Plasma Physics of Intense Neutral-Beam Heating in Tokamaks: Report on the IAEA Technical Committee Meeting and Workshop, Oak Ridge, Tennessee, United States of America 25 April–2 May 1979

Autor: J.D. Callen, J.A. Rome

Publikováno v: Nuclear Fusion. 20:501-505

Since neutral-beam heating of tokamaks has reached the new and interesting stage where it significantly exceeds the Ohmic power input, an IAEA-sponsored workshop on this subject was held at the American Museum of Science and Energy in Oak Ridge, Tenn

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::59e63d8d6dcde426f574a5d3b1d99b99
https://doi.org/10.1088/0029-5515/20/4/013

Oak Ridge TNS program: low density ignition scenarios using injection heating

Autor: J.A. Holmes, Y.K.M. Peng, J.A. Rome, S.J. Lynch, Wayne A Houlberg

Plasma heating and ignition by neutral injection have been studied using a Monte Carlo neutral injection computer code coupled to a single fluid, one-dimensional (1-D) transport code and a two-dimensional (2-D) flux conserving equilibrium code. It is

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::87cd150afd2eec30857a364bb393d52d
https://doi.org/10.2172/5770171

Effects of toroidal field ripple on injected deuterons in the FED device

Autor: J.A. Rome, R.H. Fowler

A Monte Carlo beam deposition and thermalization code is used to assess the effects of toroidal field (TF) ripple on injected fast deuterons in the Fusion Engineering Device (FED). The code uses realistic geometry for the beam, plasma equilibrium, TF

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::7c320b6a9bfb473b60e6967e562d522e
https://doi.org/10.2172/6179722