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In this paper, a novel system has been developed for plasma disruption conditions followed by downward vertical displacement. During the disruption, size and orientation of plasma decreases, which gives the halo current circulated around each contacting point in radial as well as in poloidal directions. Therefore, a new mathematical model has been developed, which gives the interaction forces of halo current, vertical, and radial plasma dynamical behavior (linear and nonlinear). This theoretical approach showed that the tokamak plasma has two connecting points in order to distinguish between the stable and unstable position. This model can particularly give the magnetic field change points and changing of flux, which are more convenient in order to discuss the static and tilting position of plasma behavior. Numerical techniques have been calculated in terms of plasma dynamical behavior, that is, Electromagnetic/plasma, Vertical Displacement Event (VDE) stages, and initial interaction between the forces under specific time interval. The objective of the research is to developed theoretical and computational model in order to investigate the dynamical behavior of plasma under disruption conditions. This is the novel method, and no work has been reported so far. Copyright © 2015 John Wiley & Sons, Ltd. [ABSTRACT FROM AUTHOR]

In this paper, research has been conducting on calculating full plasma energy and magnetic field cross sections in static as well as in tilting position for analyzing plasma vertical displacement event behavior. Consequently, the main concern of the research is to developed plasma energy and shape model. First, the developed 3D shape model allows an effective way to study the shape of plasma behavior of main plasma characteristics under controlled conditions including sensitive dependent on initial condition based on isolated points. Secondly, the developed 3D plasma energy model denotes every calculated point and analyze magnetic field of each cross section under different values of α and β according to magnetic field produced by a circular current loop. This theoretical approach showed that the individual points (( a, b) & ( r, z)) with static and tilting moments are able to develop the three-dimension coordinates system, based on R0 = 1.7 ∼ 1.8, B0 = 3.5 T and plasma current I P ≤ 1 MA. Furthermore, 195 × 12 (both states) circle current loop of magnetic field has been calculated as well. The 'sinβ cross section' for every 30° in both states (static and tilt with alpha variations) calculates the total plasma energy. Therefore, we have developed computational codes in Matlab program to calculate the values of full plasma energy in EAST. Energy from initial to final state, VDE and external force behavior, poloidal and toroidal fix degree of every cross section that depends on each current loop of magnetic field have been analyzed based on whole plasma energy data. Copyright © 2015 John Wiley & Sons, Ltd. [ABSTRACT FROM AUTHOR]

In superconducting magnetic system including with the accessorial equipment's for fusion device i.e., Tokamak, the linkage of the superconducting cable-in-conduit conductor (CICC) requires special designed structure named as superconducting cable joint. This joint connects the segmental superconducting cables electrically and in the meanwhile, coolant flow is maintained non-obstructively between two cable via the joint. For the case of “twin-box” structure joint, the boxes is sealed welded with the cable jacket. In realistic operational condition, the joint need to sustain complicated loads which can apply from various directions including the electromagnetic force and thermal stress. The action of the torque is the main factor that affects the welding seam quality between the joint and the cable jacket. In this scenario, the full penetration butt welding is the best choice. In International Thermonuclear Experimental Reactor (ITER) Feeder system, the cable jacket thickness is only 2 mm, and the allowable maximum temperature of the superconducting strands in cable should be lower than 250 °C during the whole welding stage. Therefore, special welding techniques should be developed, the welding for such thin-wall jacket limits the temperature rise of the strands and achieve the full penetration simultaneously. This paper describes the latest research and experiments in ASIPP, which aims to find a suitable method for Feeder cable jacket to joint box sealing weld. [ABSTRACT FROM AUTHOR]