Abstract

The redistribution and potential loss of energetic particles due to MHD modes can limit the performance of fusion plasmas by reducing the plasma heating rate. In this work, we present validation studies of the 1.5D critical gradient model (CGM) for Alfvén eigenmode (AE) induced EP transport in NSTX and DIII-D neutral beam heated plasmas. In previous comparisons with a single DIII-D L-mode case, the CGM model was found to be responsible for 75% of measured AE induced neutron deficit []. A fully kinetic HINST is used to compute mode stability for the non-perturbative version of CGM (or nCGM). We have found that AEs show strong local instability drive up to violating assumptions of perturbative approaches used in NOVA-K code. We demonstrate that both models agree with each other and both underestimate the neutron deficit measured in DIII-D shot by approximately a factor of 2.On the other hand in NSTX the application of CGM shows good agreement for the measured flux deficit predictions. We attempt to understand these results with the help of the so-called kick model which is based on the guiding center code ORBIT. The kick model comparison gives important insight into the underlying velocity space dependence of the AE induced EP transport as well as it allows the estimate of the neutron deficit in the presence of the low frequency Alfvénic modes. Within the limitations of used models we infer that there are missing modes in the analysis which could improve the agreement with the experiments.

Highlights

  • The fast ion confinement is one of the key problems to be addressed in preparation for future burning plasma (BP) experiments [2, 3] such as ITER [4]

  • The application of critical gradient model (CGM) included the comparison of time averaged EP predicted pressure profiles over the interval comparable with the fast ion slowing down time

  • The measurements of the characteristic width of the mode is shown to be about two times narrower in simulations than in linear perturbative analysis and has similar width to the mode width obtained by the ideal MHD code [26]. This motivated us to develop the non-perturbative version of CGM where TAEs are computed by the non-perturbative code HINST (HIgh-n STability) [15, 16]

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Summary

Introduction

The fast ion (or energetic particle—EP) confinement is one of the key problems to be addressed in preparation for future burning plasma (BP) experiments [2, 3] such as ITER [4]. Earlier CGM ( called here the 1.5D model) applications [6, 9] reasonably well described such integral parameters as EP pressure profiles. This encouraged further validation against recent DIII-D experiments at elevated qmin values [1]. The application of CGM included the comparison of time averaged EP predicted pressure profiles over the interval comparable with the fast ion slowing down time. Despite such averaging, the agreement obtained between the experiments and predictions was surprisingly good.

Critical gradient models
Kick model approach
Experiment
Comparison with the kick model calculations
Findings
Summary
Full Text
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