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Calculations of Consistent Parameters of FNS-ST Plasma Using Ion Transport Equations and Simulations of Tritium Fuel Cycle Using FC-FNS Code
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DOI：10.1080/15361055.2026.2629151.png)
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Abstract
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The results of simulating the fluxes of deuterium (D)/tritium (T) fuel particles in plasma and the fuel cycle of the FNS-ST fusion neutron source based on a spherical tokamak are presented for the 10 -W-power neutral beam injection (NBI) heating scenario. Previously, scenarios for 6-MW-power NBI heating with the injection of D beams, T beams, and D + T beams have been studied. In contrast to the simulations performed previously, in this study, ions were used instead of electrons in the transport equations when performing consistent simulations of the particle and heat fluxes using the SOLPS and ASTRA codes. This allowed for performing better estimates of the fluxes of the D/T fuel components that should be provided with the systems for gas puffing and processing.The confinement times obtained (including global ones) are comparable with those obtained when simulating the 6 -MW-power scenario. The D and T fluxes in the core and divertor plasmas of a tokamak obtained during the simulations were used to estimate the fluxes and to calculate the content of the fusion fuel components in the tokamak fuel cycle systems using the FC-FNS code. Feedback was implemented between the pumping and injection systems in the form of changes in the density and isotopic composition of the core and divertor plasmas.Simulations of the NBI heating scenarios with the injection of D and T beams with powers of up to 10 MW, performed for a fusion neutron source with a fusion power of up to 3 MW, showed that the neutron yield can be increased to 0.1 & times; 1019 s-1. When increasing the additional NBI heating power from 6 to 10 MW, the additional injector is involved, which will require processing a larger amount of gas from the NBI system. At the same time, an increase in the particle flux due to the beam injection will result in a decrease in the flux associated with the pellet injection. For the scenario with the T beam injection, the amount of tritium contained in the facility was less. It can be up to 110 g, while in the scenario with the D beam injection, the amount of tritium increased to 330 g.
Keywords:
Fusion neutron source
spherical tokamak
D-T fuel cycle
FC-FNS code
tritium inventory
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