Results 51 to 60 of about 1,463,568 (229)

First SOLPS‐ITER Simulation Study of Japanese DEMO on Leakage of Seeded Ar Impurity

Contributions to Plasma Physics, EarlyView.
ABSTRACT For JA DEMO, one of the grand challenges is efficiently handling the extreme power loads onto plasma‐facing components, particularly the divertor targets. Impurity seeding is an essential strategy for increasing the radiation losses and thereby reducing the heat load on the targets.
Hang Si, Gakushi Kawamura, Nobuyuki Asakura, Kazuo Hoshino, Haruki Seto, Yoshiteru Sakamoto, Masatoshi Yagi   +6 more
wiley   +1 more source

Implementation of a High-Speed Multichannel Data Acquisition System for Magnetic Diagnostics and Plasma Centroid Position Control in ISTTOK

IEEE Access, 2023
In tokamak and other fusion devices, magnetic control is the main tool that allows to regulate the plasma current, position and shape; it is in charge of actuating the desired plasma current waveform, steering the plasma position to a given set point and
Domenica Corona, Adriano Mele, Nuno Cruz, Hugo Alves, Bernardo B. Carvalho, Humberto Figueiredo, Horacio Fernandes   +6 more
doaj   +1 more source

Tokamak Fusion Test Reactor Annual Report

, 1988
This report discusses the following topics: principal parameters achieved in experimental devices (FY88); tokamak fusion test reactor; Princeton beta Experiment-Modification; S-1 Spheromak; current drive experiment; x-ray laser studies; spacecraft glow ...
Phillips, C. A.
core   +1 more source

Electrostatic analysis of the tokamak edge plasma [PDF]

, 1981
The intrusion of an equipotential poloidal limiter into the edge plasma of a circular tokamak discharge distorts the axisymmetry in two ways: (1) it (partially) shorts out the top-to-bottom Pfirsch-Schlueter driving potentials, and (2) it creates zones ...
R.W. Motley, Motley, R. W.
core   +1 more source

Towards a Mean‐Field Braginskii Model for Stellarators

Contributions to Plasma Physics, EarlyView.
ABSTRACT Experiments in the stellarator Wendelstein 7‐X indicate that particle drifts have a significant impact on the plasma in the scrape‐off layer. However, drift effects have been absent in the mean‐field transport codes such as EMC3‐Eirene. For this reason, we present the first steps towards a mean‐field model that incorporates drifts. The code is
T. Tork, F. Reimold, D. Bold, B. Shanahan, B. Dudson, A. Stegmeir, P. Manz, The W7‐X Team   +7 more
wiley   +1 more source

Overview of recent results from the ST40 compact high-field spherical tokamak

Nuclear Fusion
ST40 is a compact, high-field ( $B_{\mathrm{T0}}\unicode{x2A7D} 2.1\,\,\,\textrm{T}$ ) spherical tokamak (ST) with a mission to expand the physics and technology basis for the ST route to commercial fusion.
S.A.M. McNamara, A. Alieva, M.S. Anastopoulos Tzanis, O. Asunta, J. Bland, H. Bohlin, P.F. Buxton, C. Colgan, A. Dnestrovskii, E. du Toit, M. Fontana, M. Gemmell, M.P. Gryaznevich, J. Hakosalo, M.R. Hardman, D. Harryman, D. Hoffman, M. Iliasova, S. Janhunen, F. Janky, J.B. Lister, H.F. Lowe, E. Maartensson, C. Marsden, S.Y. Medvedev, S.R. Mirfayzi, M. Moscheni, G. Naylor, V. Nemytov, J. Njau, T. O’Gorman, D. Osin, T. Pyragius, A. Rengle, M. Romanelli, C. Romero, M. Sertoli, V. Shevchenko, J. Sinha, A. Sladkomedova, S. Sridhar, J. Stirling, Y. Takase, P.R. Thomas, J. Varje, E. Vekshina, B. Vincent, H.V. Willett, J. Wood, E. Wooldridge, D. Zakhar, X. Zhang, D. Battaglia, N. Bertelli, P.J. Bonofiglo, L.F. Delgado-Aparicio, V.N. Duarte, N.N. Gorelenkov, M. de Haas, S.M. Kaye, R. Maingi, D. Mueller, M. Ono, M. Podesta, Y. Ren, S. Trieu, E. Delabie, T.K. Gray, B. Lomanowski, E.A. Unterberg, O. Marchuk, the ST40 Team   +71 more
doaj   +1 more source

Development of a Set of Synthetic Diagnostics for the Confrontation between 2D Transport Simulations and WEST Tokamak Experimental Data

Applied Sciences, 2022
Transport codes are frequently used for describing fusion plasmas with the aim to prepare tokamak operations. Considering novel codes, such as SolEdge3X-HDG, synthetic diagnostics are a common technique used to validate new models and confront them with ...
Ivan Kudashev, Anna Medvedeva, Manuel Scotto d’Abusco, Nicolas Fedorszak, Stefano Di Genova, Vladislav Neverov, Eric Serre   +6 more
doaj   +1 more source

On a nonlocal problem for a confined plasma in a Tokamak [PDF]

Applications of Mathematics, 2013
This article studies a class of nonlocal problems of the following form \[ \begin{cases} -\Delta u=f(x,u) \quad \text{in } \{u>0\},\\ -\Delta u=0 \quad \text{in } \{u\leq 0\},\\ u=\gamma \quad \text{(a constant to be determined) on } \partial \Omega ,\\ -\int_{\partial \Omega } \partial u / \partial \eta = I \text{ (a given constant)}, \end{cases}\tag ...
Zou, Weilin, Li, Fengquan, Lv, Boqiang
openaire   +2 more sources

Positive sheath generation in front of fish-scaled divertor plates

Nuclear Fusion
Fish-scale divertor plates are becoming popular in the design of next-generation magnetic fusion reactors to make the edge of one divertor tile sits safely behind the shadowed profile of the preceding tile, hence to protect the leading edge from extreme ...
C.S. Chang, S. Ku, X. Zhang, T. Brewer, N.A. Lopez, C. Marsden, the ST40 Team   +6 more
doaj   +1 more source

Plasma diagnostics for the compact ignition tokamak

, 1988
The primary mission of the Compact Ignition Tokamak (CIT) is to study the physics of alpha-particle heating in an ignited D-T plasma. A burn time of about 10 /tau//sub E/ is projected in a divertor configuration with baseline machine design parameters of
K.M. Young, Young, K. M., S.S. Medley, Medley, S. S.   +3 more
core   +1 more source