Effect of magnetic reconnection on CT penetration into magnetized plasmas

Suzuki, Yoshio; Hayashi, T.; Kishimoto, Y.

doi:10.1186/bf03353268

Cited by 3 publications

(1 citation statement)

References 12 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Hwang et al [24] delved into an examination of how the shape and compressibility of a CT impact its propagation into a low-beta plasma using the CS model. In parallel, Suzuki et al introduced an alternative model, termed the nonslipping (NS) model, which incorporates considerations of magnetic pressure and the magnetic field force associated with the target magnetic field [25,26]. The utilization of numerical simulations employing MHD equations has indicated that the CT's behavior falls within the range of predictions generated by both the CS and NS models.…”

Section: Introductionmentioning

confidence: 99%

Effects of vacuum magnetic field region on the compact torus trajectory in a tokamak plasma

DONG 董,

ZHANG 张,

LAN 兰

et al. 2024

Plasma Sci. Technol.

View full text Add to dashboard Cite

The trajectory of the compact torus (CT) within a tokamak discharge is crucial to fueling. In this study, we developed a penetration model with a vacuum magnetic field region to accurately determine CT trajectories in tokamak discharges. This model was used to calculate the trajectory and penetration parameters of CT injections by applying both perpendicular and tangential injection schemes in both HL-2A and ITER tokamaks. For perpendicular injection along the tokamak's major radius direction from the outboard, CTs with the same injection parameters exhibited an 0.08 reduction in relative penetration depth when injected into HL-2A and a 0.13 reduction when injected into ITER geometry when considering the vacuum magnetic field region compared with cases where this region was not considered. In addition, we proposed an optimization method for determining the CT's initial injection velocity to accurately calculate the initial injection velocity of CTs for central fueling in tokamaks. Furthermore, this paper discusses schemes for the tangential injection of CT into tokamak discharges. The optimal injection angle and CT magnetic moment direction for injection into both HL-2A and ITER were determined through numerical simulations. Finally, the kinetic energy loss occurring when the CT penetrated the vacuum magnetic field region in ITER was reduced by ΔEk=975.08J by optimizing the injection angle for the CT injected into ITER. These results provided valuable insights for optimizing injection angles in fusion experiments. Our model closely represents actual experimental scenarios and can assist the design of CT parameters.

show abstract

Section: Introductionmentioning

confidence: 99%

Effects of vacuum magnetic field region on the compact torus trajectory in a tokamak plasma

DONG 董,

ZHANG 张,

LAN 兰

et al. 2024

Plasma Sci. Technol.

View full text Add to dashboard Cite

show abstract

Scaling arguments for a plasma experiment relevant to an interplanetary coronal mass ejection

Young

Kuranz

2020

Physics of Plasmas

View full text Add to dashboard Cite

We present the design of a plasma experiment scaled to be relevant to an interplanetary coronal mass ejection (ICME) traveling from the Sun to the Earth. The experiment would launch a compact torus of plasma (the scaled analog of the coronal mass ejected by the Sun) into a magnetized background plasma (the scaled analog of the interplanetary medium, the diffuse magnetized plasma that fills the Solar System). We present the complete process of scaling the ICME system to a laboratory experiment: beginning with the ICME features that we aim to replicate with a laboratory experiment, explaining how these desired features are translated into specific design constraints, and presenting a set of experimental parameters that meet those constraints. We find that the experiment would be possible with plasma conditions typically achieved in large-scale facilities such as the Big Red Ball at the University of Wisconsin or the LArge Plasma Device at the University of California, Los Angeles.

show abstract

Development of a compact toroid fuelling system for ITER

Olynyk¹,

Morelli

2008

Nucl. Fusion

View full text Add to dashboard Cite

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.

show abstract

Effect of magnetic reconnection on CT penetration into magnetized plasmas

Cited by 3 publications

References 12 publications

Effects of vacuum magnetic field region on the compact torus trajectory in a tokamak plasma

Effects of vacuum magnetic field region on the compact torus trajectory in a tokamak plasma

Scaling arguments for a plasma experiment relevant to an interplanetary coronal mass ejection

Development of a compact toroid fuelling system for ITER

Contact Info

Product

Resources

About