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UKAEA-CCFE-PR(23)1182023
A new open source tool for fluid simulation of multi-component plasmas is presented, based on a flexible software design that is applicable to scientific simulations in a wide range of fields. This design enables the same code to be configured at run-time to solve systems of partial differential equations in 1D, 2D or 3D, either for transport (st…
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UKAEA-CCFE-PR(23)1092023
The influence of negative plasma triangularity on the n=1 (n is the toroidal mode number) tearing mode (TM) stability has been numerically investigated, with results compared to that of the positive triangularity counterpart. By matching the safety factor profile for a series of toroidal equilibria, several important plasma parameters, including th…
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UKAEA-CCFE-PR(23)812023
Linear and nonlinear gyrokinetic simulations are performed in experimentally relevant scenarios built from a MAST case where a microtearing mode instability dominates at ion Larmor radius scale. This collisional microtearing mode instability appears only when a vel…
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UKAEA-CCFE-PR(23)162023
Observations of enhanced fast-ion losses during edge localized modes (ELMs) have been reported in the ASDEX Upgrade tokamak, revealing losses above the injection energy. This suggests that fast ions can be accelerated and lost by the ELMs. Recent analysis delves into the analysis of the ELM-induced losses, suggesting that the fast ions are los…
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UKAEA-CCFE-PR(23)152023
Pellet injection is used for fuelling and controlling discharges in tokamaks, and it is foreseen in ITER. During pellet injection, a movement of the ablated material towards the low- field side (or outward major radius direction) occurs because of the inhomogeneity of the magnetic field. Due to the complexity of the theoretical models, computer…
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UKAEA-STEP-CP(23)012023
Cryogenics are widely used in tokamak fusion reactors in three main areas. Firstly, to provide cooling to superconducting magnets for plasma confinement. Secondly, to provide the required level of vacuum in the plasma vessel through cryogenic vacuum technology. Thirdly, as part of the fusion fuel cycle, including matter injection, typically…
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UKAEA-STEP-PR(23)012023
In this work, the MARS-F/K codes (Liu Y Q et al 2000 Phys. Plasmas 7 3681 & Liu Y Q et al 2008 Phys. Plasmas 15 112503) are utilized to model the passive and active control of the n=1 (n is the toroidal mode number) resistive wall mode (RWM) in a spherical tokamak (aspect rat…
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UKAEA-CCFE-PR(23)042023
The High Field High Density Region (HFSFD) has been experimentally observed in both divertor and limiter tokamak devices. In order to numerically reproduced the HFSHD region in the limiter tokamak device J-TEXT, we first performed SOLPS-ITER simulations on the J-TEXT limiter tokamak with the activation of drifts, which is associated with the HFSHD …
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UKAEA-CCFE-CP(25)032022
The UK Spherical Tokamak for Energy Production (STEP) program is currently progressing the conceptual engineering design of a Spherical Tokamak-based fusion reactor. The program includes a project concerned with design of the reactor breeding blanket. The objective of this work was to develop a low fidelity, integrated simulation approach to sup…
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UKAEA-STEP-CP(25)012022
A key aspect in the design of a spherical tokamak reactor is the optimisation of the plasma equilibrium, together with a compatible divertor configuration and the corresponding poloidal field system. This is a complex multi-disciplinary problem, integrating plasma physics and engineering in order to satisfy a multitude of often conflicting requi…
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