Abstract:A compact toroid (CT) penetrating into a tokamak discharge is modelled as a conducting
solid sphere with an intrinsic magnetic moment. Equations of CT motion in tokamak discharges are derived and used to calculate the trajectory of a CT with parameters pertinent for penetrating the ITER tokamak. The advantage of tangential CT injection and the optimal direction
of the initial magnetic moment are discussed.
“…Some theoretical studies show that tangential CT injection has longer interaction time with the tokamak plasma and might cause smaller disturbance on the tokamak discharge. 10,11 In addition, tangential CT injection may transfer CT momentum to tokamak plasma to induce and sustain toroidal rotation, which has beneficial effects on stabilizing the locked mode and resistive wall mode. 12 At the University of Saskatchewan, it has been observed that tangential CT injection into the Saskatchewan Torus-Modified ͑STOR-M͒ tokamak induces H-mode discharges.…”
Compact torus injection into the Saskatchewan Torus-Modified ͓Phys. Fluids B 4, 3277 ͑1992͔͒ tokamak discharges has triggered improved confinement characterized by an increase in the electron density by more than twofold, 30% reduction in the H ␣ radiation level, significant suppression of floating potential fluctuations and mϭ2 Mirnov oscillations. In this paper, we present detailed experimental setup and results, as well as an extended theory explaining the mechanism for triggering improved confinement in a tokamak by compact torus injection.
“…Some theoretical studies show that tangential CT injection has longer interaction time with the tokamak plasma and might cause smaller disturbance on the tokamak discharge. 10,11 In addition, tangential CT injection may transfer CT momentum to tokamak plasma to induce and sustain toroidal rotation, which has beneficial effects on stabilizing the locked mode and resistive wall mode. 12 At the University of Saskatchewan, it has been observed that tangential CT injection into the Saskatchewan Torus-Modified ͑STOR-M͒ tokamak induces H-mode discharges.…”
Compact torus injection into the Saskatchewan Torus-Modified ͓Phys. Fluids B 4, 3277 ͑1992͔͒ tokamak discharges has triggered improved confinement characterized by an increase in the electron density by more than twofold, 30% reduction in the H ␣ radiation level, significant suppression of floating potential fluctuations and mϭ2 Mirnov oscillations. In this paper, we present detailed experimental setup and results, as well as an extended theory explaining the mechanism for triggering improved confinement in a tokamak by compact torus injection.
“…Benefits of CT injection are that it is able to penetrate into the core region of the tokamak plasma as it is an excellent conductor with a high velocity and is able to overcome the tokamak's toroidal field gradient. Also, via tangential injection, CT injection provides long interaction time with tokamak plasma, and transfers momentum to the tokamak plasma, causing smaller disturbances in the discharge and inducing and sustaining toroidal rotation [26,27].…”
Section: Nuclear Fusion and The Tokamak Reactormentioning
confidence: 99%
“…The wave's frequency, ω, must be larger than the plasma frequency, 27) where ω has a dispersion relation…”
Development of fueling technologies for modern and future tokamak reactors is essential for their implementation in a commercial energy production setting. Compared to the presently available fueling technologies, gas or cryogenic pellet injection, compact torus injection presents an effective and efficient method for directly fueling the central core of tokamak plasmas. Fueling of the central core of a tokamak plasma is pivotal for providing efficient energy production. The central core plasma of a reactor contains the greatest density of fusion processes. For consistent and continuous fueling of tokamak fusion reactors, compact torus injectors must be operated in a repetitive mode.The goal of this thesis was to study the feasibility of firing the University of Saskatchewan Compact Torus Injector (USCTI) in a repetitive mode. In order to enable USCTI to fire repetitively, modifications were made to its electrical system, control system and data acquisition system. These consisted primarily of the addition of new power supplies, to enable fast charging of the many capacitor banks used to form and accelerate the plasma. The maximum firing rate achieved on USCTI was 0.33 Hz, an increase from the previous maximum firing rate of 0.2 Hz achieved at UC Davis.Firing USCTI in repetitive modes has been successful. It has been shown that the CTs produced in any given repetitive series are properly formed and repeatable. This is made evident through analysis of data collected from the CTs' magnetic fields and densities as they traveled along the injector barrel. The shots from each experiment were compared to the series' mean data and were shown to be consistent over time.Calculations of their correlations show that there are only minimal deviations from shot to shot in any given series.ii
“…The CS model was developed further by Newcomb [8], who developed a more accurate model for the MHD wave drag. Xiao et al [9] refined the work of Bozhokin and used the corrected (Newcomb) drag term, and also were the first to simulate vertical (as opposed to radial) injection [10]. All these models had three degrees of freedom, considering the motion of the CT in a twodimensional plane and the rotation of its dipole about a single fixed axis.…”
Section: The Conducting Sphere (Cs) Modelmentioning
confidence: 99%
“…Several papers [5,7,9,12,13] have used ITER or ITER-like reactors as test cases for the CT trajectory models. In addition, there have been at least two [24,25] serious proposals to use horizontal CT injection as a central fuelling method for ITER.…”
A review of literature relevant to compact toroid (CT) injection is presented. A design is then developed for a repetitive-fire CT injection fuelling system for the ITER (2001) tokamak. Advantages of central over edge fuelling include plasma density control and higher deposition rates, implying lower tritium usage. The reference design offers 50 Pa m3 s−1 of 90%T/10%D fuelling. 1.29 mg CTs are injected at a rate of 50 Hz (in order to synchronize with the European power grid) and a speed of 300 km s−1. A new six-degree-of-freedom model of CT trajectory in the tokamak is developed and applied to the proposed injector design. The fueller is intended to work in parallel with the 400 Pa m3 s−1 edge gas puffing system and to replace the centrifuge pellet-injection system in the ITER (2001) reference design. Each injected CT adds only 0.68% to the plasma inventory, implying that the injection process will be non-disruptive. Power consumption will be approximately 15 MWe. The strengths of the design compared with the current pellet-injection system are highlighted.
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