Conveners
Session 04: Session 04
- Brian Lloyd (UKAEA)
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Stanley Kaye (PPPL)30/10/2019, 09:00oral
NSTX-U: Recent Results and Plans
S.M. Kaye
Princeton Plasma Physics Laboratory, Princeton NJ 08543After an 18-month sequence of key reviews, the NSTX-U Recovery Project was recently approved to initiate procurement and fabrication of components as a step towards completion of the Recovery and commencement of physics operations in the 2021-2022 time frame. The elements of the Recovery,...
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Dr Juan Ruiz Ruiz (1. MIT-Plasma Science and Fusion Center 2. Rudolf Peierls Centre for Theoretical Physics, University of Oxford)30/10/2019, 09:35oral
A new extensive validation study performed for a modest beta NSTX NBI-heated H-mode predicts that electron thermal transport can be entirely explained by short-wavelength electron-scale turbulence fluctuations driven by the electron temperature gradient mode (ETG), both in conditions of strong and weak ETG turbulence drive. For the first time, local, nonlinear gyrokinetic simulations carried...
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Nicola Bertelli30/10/2019, 10:10oral
In this paper we report an application of the Petra-M on NSTX-U. Petra-M, is a recent developed and open source code, which is based on the scalable MFEM C++ finite element library and allows for FEM analysis from geometry/mesh generation, FEM assembly, FEM system equation solution, and visualization in one platform [1, 2]. The first full torus 3D high harmonic fast wave (HHFW) simulations for...
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Mr A. Piccione (University College London), Mr J.W. Berkery (Columbia University), Mr S.A. Sabbagh (Columbia University)30/10/2019, 11:15oral
Machine Learning approaches to predict the ideal stability properties of spherical tokamak plasmas
A.Piccione 1, J.W. Berkery 2, S.A. Sabbagh 2, Y. Andreopoulos 1
1 Department of Electronic and Electrical Engineering, University College London, London, WC1E 7JE, UK
2 Department of Applied Physics and Applied...
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Dr Roger Raman30/10/2019, 11:35oral
Demonstration of fully solenoid-free start-up at the ~1 MA level and ramp-up to full current of low inductance plasma would be a major step for the ST program, as it would be a convincing enough step for the consideration of ST designs with a reduced size solenoid. In support of this objective, the TSC code, with the inclusion of plasma transport, has been used to study the Transient CHI...
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Dr Jonathan Menard (Princeton Plasma Physics Laboratory)30/10/2019, 11:55oral
Utilizing high-Z solid walls such as tungsten is challenging for next-step/Fusion Nuclear Science Facility (FNSF)/Pilot Plant applications due to a range of issues. These issues include Plasma-Facing Component (PFC) material damage from erosion and re-deposition and neutrons, high-Z impurity accumulation and associated core plasma radiative collapse, relatively low heat flux limits at the...
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