4.6 Article

Neutral Beam Coupling with Plasma in a Compact Fusion Neutron Source

Journal

APPLIED SCIENCES-BASEL
Volume 12, Issue 17, Pages -

Publisher

MDPI
DOI: 10.3390/app12178404

Keywords

fusion neutron source; spherical tokamak; neutral beam injection; current drive; neutron yield; lite beam model; FNS-ST; NBI; BTR; BTOR

Funding

  1. NRC Kurchatov Institute

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FNS-ST is a fusion neutron source project based on a spherical tokamak. This study focuses on the beam-plasma coupling issue and presents a method to achieve steady-state current drive and fusion controllability in beam-driven toroidal plasmas. The study demonstrates the efficient modeling of neutral beam production and the tokamak plasma response to NBI using a specialized software package.
FNS-ST is a fusion neutron source project based on a spherical tokamak (R/a = 0.5 m/0.3 m) with a steady-state neutron generation of similar to 10(18) n/s. Neutral beam injection (NBI) is supposed to maintain steady-state operation, non-inductive current drive and neutron production in FNS-ST plasma. In a low aspect ratio device, the toroidal magnetic field shape is not optimal for fast ions confinement in plasma, and the toroidal effects are more pronounced compared to the conventional tokamak design (with R/a > 2.5). The neutral beam production and the tokamak plasma response to NBI were efficiently modeled by a specialized beam-plasma software package BTR-BTOR, which allowed fast optimization of the neutral beam transport and evolution within the injector unit, as well as the parametric study of NBI induced effects in plasma. The Lite neutral beam model (LNB) implements a statistical beam description in 6-dimensional phase space (10(6)-10(10) particles), and the beam particle conversions are organized as a data flow pipeline. This parametric study of FNS-ST tokamak is focused on the beam-plasma coupling issue. The main result of the study is a method to achieve steady-state current drive and fusion controllability in beam-driven toroidal plasmas. LNB methods can be also applied to NBI design for conventional tokamaks.

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