Zobrazeno 1 - 10
of 1 607
pro vyhledávání: '"Spherical tokamak"'
Autor:
CHEN Junhong, WU Yi, WANG Yingqiao, LI Weibin, CHEN Yuhong, WANG Yali, ZHANG Xiaopeng, ZHENG Xue, ZHANG Chunguang, XUAN Weimin, YAO Lieying, TAN Hao, LUO Wenwu, ZHOU Peihai, SONG Xianming, LIU Shaoxuan, SUN Zequn, CONG Zijian, YANG Enwu, GE Xingxin, GAO Xiang
Publikováno v:
He jishu, Vol 47, Iss 5, Pp 050013-050013 (2024)
BackgroundENN Science and Technology Development Co., Ltd. (ENN Fusion Technology R&D Center) is upgrading its compact fusion research facility EXL-50 to EXL-50U. Both devices are the conventional conductor tokamak, on which the magnet power supply s
Externí odkaz:
https://doaj.org/article/8eeb66772555436e90de4dd624ddcbaf
Publikováno v:
Nuclear Materials and Energy, Vol 35, Iss , Pp 101410- (2023)
A key aspect in the design of a spherical tokamak reactor is the optimisation of the plasma equilibrium, together with a compatible divertor configuration, and the corresponding poloidal field system. This is a complex multi-disciplinary problem, int
Externí odkaz:
https://doaj.org/article/cadc4a89bb96497d95183b52ef640eea
Publikováno v:
Nuclear Fusion, Vol 64, Iss 12, p 126071 (2024)
The SMall Aspect Ratio Tokamak (SMART) is currently being commissioned at the University of Seville and will be able to compare the performance of positive and negative triangularity plasmas at low aspect ratio. Predictive simulations have been perfo
Externí odkaz:
https://doaj.org/article/c11cf2c0d73d459fa4faa057281d480c
Autor:
Simon Freethy, Lorenzo Figini, Steven Craig, Mark Henderson, Ridhima Sharma, Thomas Wilson, the STEP team
Publikováno v:
Nuclear Fusion, Vol 64, Iss 12, p 126035 (2024)
A fusion reactor based on the spherical tokamak is very likely to be completely non-inductive for the majority of the plasma ramp-up and steady-state phases, due to the limitations imposed on the central coil assemblies by the compact design. Efficie
Externí odkaz:
https://doaj.org/article/6fe3674ea6fc4b7cbc1865cb7251463c
Autor:
J.W. Berkery, P.O. Adebayo-Ige, H. Al Khawaldeh, G. Avdeeva, S-G. Baek, S. Banerjee, K. Barada, D.J. Battaglia, R.E. Bell, E. Belli, E.V. Belova, N. Bertelli, N. Bisai, P.T. Bonoli, M.D. Boyer, J. Butt, J. Candy, C.S. Chang, C.F. Clauser, L.D. Corona Rivera, M. Curie, P.C. de Vries, R. Diab, A. Diallo, J. Dominski, V.N. Duarte, E.D. Emdee, N.M. Ferraro, R. Fitzpatrick, E.L. Foley, E. Fredrickson, M.E. Galante, K.F. Gan, S. Gerhardt, R. Goldston, W. Guttenfelder, R. Hager, M.O. Hanson, S.C. Jardin, T.G. Jenkins, S.M. Kaye, A. Khodak, J. Kinsey, A. Kleiner, E. Kolemen, S. Ku, M. Lampert, B. Leard, B.P. LeBlanc, J.B. Lestz, F.M. Levinton, C. Liu, T. Looby, R. Lunsford, T. Macwan, R. Maingi, J. McClenaghan, J.E. Menard, S. Munaretto, M. Ono, A. Pajares, J. Parisi, J-K. Park, M.S. Parsons, B.S. Patel, Y.V. Petrov, M. Podestà, F. Poli, M. Porcelli, T. Rafiq, S.A. Sabbagh, Á. Sánchez Villar, E. Schuster, J. Schwartz, A. Sharma, S. Shiraiwa, P. Sinha, D. Smith, S. Smith, V.A. Soukhanovskii, G. Staebler, E. Startsev, B. Stratton, K.E. Thome, W. Tierens, M. Tobin, I.U. Uzun-Kaymak, B. Van Compernolle, J. Wai, W. Wang, W. Wehner, A. Welander, J. Yang, V. Zamkovska, X. Zhang, X.L. Zhu, S. Zweben
Publikováno v:
Nuclear Fusion, Vol 64, Iss 11, p 112004 (2024)
The objectives of NSTX-U research are to reinforce the advantages of STs while addressing the challenges. To extend confinement physics of low- A , high beta plasmas to lower collisionality levels, understanding of the transport mechanisms that set c
Externí odkaz:
https://doaj.org/article/5d5d1d28caf641a6ac735feb61c884d0
Publikováno v:
Nuclear Fusion, Vol 64, Iss 6, p 066037 (2024)
A more complete non-perturbative magnetohydrodynamic (MHD)-kinetic hybrid formulation is developed by including the perturbed electrostatic potential δφ in the particle Lagrangian. The fluid-like counter-parts of the hybrid equations, in the Chew-G
Externí odkaz:
https://doaj.org/article/f347cfe7711742cebb77742a535db911
Autor:
K. Imada, T.H. Osborne, S. Saarelma, J.G. Clark, A. Kirk, M. Knolker, R. Scannell, P.B. Snyder, C. Vincent, H.R. Wilson, the MAST Upgrade Team
Publikováno v:
Nuclear Fusion, Vol 64, Iss 8, p 086002 (2024)
The first pedestal stability and structure analysis on the new MAST Upgrade (MAST-U) spherical tokamak H-mode plasmas is presented. Our results indicate that MAST-U pedestals are close to the low toroidal mode number ( n ) peeling branch of the peeli
Externí odkaz:
https://doaj.org/article/ed85e13882364f9f8c63ffb934d1febe
Publikováno v:
Nuclear Fusion, Vol 64, Iss 8, p 086020 (2024)
High-power ion heating of merging spherical tokamak (ST) plasma has been investigated using TS-3U, TS-4, and UTST at the University of Tokyo for future direct access to burning high-beta ST plasma without using any additional heating. We developed a
Externí odkaz:
https://doaj.org/article/ada0ed83bb5346b68a979074b959e8c3
Publikováno v:
Nuclear Fusion, Vol 64, Iss 10, p 106008 (2024)
Here we report the ion heating/transport characteristics of the merging startup scenario in the TS-6 spherical tokamak. In addition to the previously investigated impulsive heating process during magnetic reconnection, here we also focus on a longer
Externí odkaz:
https://doaj.org/article/d8c22d83f3db4f49b41a32c478464bad
Autor:
N. Tsujii, A. Ejiri, Y. Ko, Y. Peng, K. Iwasaki, Y. Lin, K. Shinohara, O. Watanabe, S. Jang, T. Hidano, Y. Shirasawa, Y. Tian, F. Adachi, C.P. Moeller
Publikováno v:
Nuclear Fusion, Vol 64, Iss 8, p 086017 (2024)
Establishment of an efficient central solenoid (CS) free tokamak plasma start-up method may lead to an economical fusion reactor. CS-free start-up using lower hybrid (LH) waves has been studied on the TST-2 spherical tokamak. Plasma current of about
Externí odkaz:
https://doaj.org/article/76c8a253dcac4a72b39bb3331b5d3906