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A disruption mitigation system (DMS) is necessary for fusion-grade tokamaks like ITER in order to ensure the preservation of machine components throughout their designated operational lifespan. To address the intense heat and…

Plasma Physics · Physics 2023-12-07 Anshkumar Himanshu Patel

Shattered pellet injection (SPI) is selected for the disruption mitigation system in ITER, due to deeper penetration, expected assimilation efficiency and prompt material delivery. This article describes non-linear magnetohydrodynamic (MHD)…

The radiation response and the MHD destabilization during the thermal quench after a mixed species Shattered Pellet Injection (SPI) with impurity species neon and argon are investigated via 3D non-linear MHD simulation using the JOREK code.…

In a shattered pellet injection (SPI) system the penetration and assimilation of the injected material depends on the speed and size distribution of the SPI fragments. ASDEX Upgrade (AUG) was recently equipped with a flexible SPI to study…

Shattered pellet injection (SPI) as primary mitigation method for major disruptions in ITER has a large parameter space available for optimization including the total amount of injected material, the size of the individual pellet fragments,…

Disruptions are a major concern for future fusion reactors based on the tokamak principle. To ensure machine protection, the thermal loads and vessel forces that arise during disruptions have to be mitigated reliably. For the ITER…

First simulations of deuterium shattered pellet injection (SPI) into an ASDEX Upgrade H-Mode plasma with the JOREK MHD code are presented. Resistivity is increased by one order of magnitude in most simulations to reduce computational costs…

Plasma Physics · Physics 2020-02-14 M. Hoelzl , D. Hu , E. Nardon , G. T. A. Huijsmans

Plasma-terminating disruptions represent a critical outstanding issue for reactor-relevant tokamaks. ITER will use shattered pellet injection (SPI) as its disruption mitigation system to reduce heat loads, vessel forces, and to suppress the…

The heat flux mitigation during the Thermal Quench (TQ) by the Shattered Pellet Injection (SPI) is one of the major elements of disruption mitigation strategy for ITER. It's efficiency greatly depends on the SPI and the target plasma, and…

Plasma Physics · Physics 2024-06-10 D. Hu , F. J. Artola , E. Nardon , M. Lehnen , M. Kong , D. Bonfiglio , M. Hoelzl , G. T. A. Huijsmans , JOREK Team

The lifetime and utilization of a nuclear fusion reactor like ITER depends strongly on its capabilities to mitigate damage during disruptions. While shattered pellet injection (SPI) was chosen as the baseline mitigation method for ITER, the…

Plasma Physics · Physics 2022-09-05 Tobias Peherstorfer

Future large tokamaks will operate at high plasma currents and high stored plasma energies. To ensure machine protection in case of a sudden loss of plasma confinement (major disruption), a large fraction of the magnetic and thermal energy…

Pellet injection is an important means to fuel and control discharges and mitigate disruptions in reactor-scale fusion devices. To accurately assess the efficiency of these applications, it is necessary to account for the drift of the…

This report is in partial fulfillment of deliverable D1.1 Optimization of the SPI model and summarizes axisymmetric ITER SPI parameter scans performed by the NIMROD code for several ITER equilibria. These axisymmetric parameter scans are to…

Plasma Physics · Physics 2023-10-23 Charlson. C. Kim , B. C. Lyons , Y. Q. Liu , J. T. McClenaghan , P. B. Parks , L. L. Lao

A collisional-radiative non-equilibrium impurity treatment for JOREK 3D nonlinear magneto-hydrodynamic (MHD) simulations has been developed. The impurities are represented by super-particles flowing along the fluid velocity field lines,…

Plasma Physics · Physics 2021-11-17 D. Hu , G. T. A. Huijsmans , E. Nardon , M. Hoelzl , M. Lehnen , D. Bonfiglio , JOREK Team

In this study, NIMROD simulations are performed to investigate the effects of massive helium gas injection level on the induced disruption on EAST tokamak. It is demonstrated in simulations that two different scenarios of plasma cooling…

Plasma Physics · Physics 2021-03-16 Abdullah Zafar , Ping Zhu , Ahmad Ali , Shiyong Zeng , Haolong Li

This report is in partial fulfillment of deliverable D1.3 Code Validation (DIII-D). These simulations focus on thermal quench phase of the SPI mitigation and are not typically carried beyond it to the current spike and subsequent current…

Plasma Physics · Physics 2023-10-23 Charlson. C. Kim , T. Bechtel , J. L. Herfindal , B. C. Lyons , Y. Q. Liu , P. B. Parks , L. Lao

An effective disruption mitigation system in a tokamak reactor should limit the exposure of the wall to localized heat losses and to the impact of high current runaway electron beams, and avoid excessive forces on the structure. We evaluate…

Plasma Physics · Physics 2022-10-12 O. Vallhagen , I. Pusztai , M. Hoppe , S. L. Newton , T. Fülöp

A 3D numerical model for the ablation of pellets and shattered pellet injection (SPI) fragments in tokamaks in the plasma disruption mitigation and fueling parameter space has been developed based on the Lagrangian particle code [R.…

Plasma Physics · Physics 2021-05-26 R. Samulyak , S. Yuan , N. Naitlho , P. B. Parks

The fragment ablation rate plays significant roles in the mitigation efficiency of Shattered Pellet Injection (SPI) as a Disruption Mitigation System (DMS). Current mainstream 3D MHD codes modelling SPIs mostly assume instantaneous…

Plasma Physics · Physics 2022-06-27 Di Hu , Chang Liu

A two-temperature magnetohydrodynamic (MHD) model, which evolves the electron and ion temperatures separately, is implemented in the PSI-Tet code and used to model plasma dynamics in the HIT-SI experiment. When compared with…

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