Abstract Tokamak and inertial confinement fusion(ICF) are two kinds of devices to achieve fusion. Magnetic gravitational fields the drivers used in tokamak ICF, respectively. In other fusion like MIF, both them used. this work, different from these mentioned above, a new promising method confine plasma is proposed. Spacial distribution energy high-speed changing magnetic field simulated. This e...

A new spherical tokamak, the SMall Aspect Ratio Tokamak (SMART), is currently being designed at University of Seville. The goal machine to achieve a toroidal field 1 T, plasma current 500 kA and pulse length ms for with major radius 0.4 m minor 0.25 m. This contribution presents design coils power supplies machine. foresees central solenoid, 12 8 poloidal coils. Taking waveforms these set as st...

The US National Fusion Collaboratory (NFC) project has been exploring a variety of computer and network technologies to develop a persistent, efficient, reliable and convenient collaborative environment for magnetic fusion research. One goal is to enhance remote and collocated team collaboration by integrating collaboration software tools into control room operations as well as with data analys...

Submitted for the DPP06 Meeting of The American Physical Society Status of BOUT fluid turbulence code: improvements and verification M.V. UMANSKY, L.L. LODESTRO, X.Q. XU, LLNL — BOUT is an electromagnetic fluid turbulence code for tokamak edge plasma [1]. BOUT performs time integration of reduced Braginskii plasma fluid equations, using spatial discretization in realistic geometry and employing...

During the past few years, the ARIES team has developed advanced designs to identify the physics and technology areas of high leverage for achieving environmentally attractive and economically competitive fusion power plants. This paper documents the key neutronics parameters and identifies the nuclear issues for the most recent spherical and advanced tokamak designs. The nuclear assessment pla...

The reaction of an equilibrium tokamak plasma to a sudden localized deposition of heat is investigated by means of numerical simulations of the time-dependent equations of resistive magnetohydrodynamics (MHD) in two spatial dimensions, in order to obtain a better understanding of the structure and dynamics of the hot plasma filaments that are observed in recent tokamak experiments. Simulation r...

An extensive set of software tools for integrated plasma control has been developed, validated, and applied to the DIII–D tokamak to design controllers for plasma shape and both axisymmetric and non-axisymmetric MHD instabilities [1]. The integrated plasma control approach uses validated physics models to design controllers, and confirms their performance by operating actual machine control har...

Through compact toroid (CT) injection experiments on the TEXT-U tokamak (with BT ' 10 kG and IP ' 100 kA), it has been shown that the acceleration electrode configuration, particularly in the vicinity of the toroidal field (TF) coils of the tokamak, has a strong effect on penetration performance. In initial experiments, premature stopping of CTs within the injector was seen at anomalously low T...

Non Regression Testing (NRT) aims to check if software modifications result in undesired behaviour. Suppose the behaviour of the application previously known, this kind of test makes it possible to identify an eventual regression, a bug. Improving and tuning a parallel code can be a time-consuming and difficult task, especially whenever people from different scientific fields interact closely. ...