Results 1 to 10 of about 311 (75)
Predictive JET current ramp-up modelling using QuaLiKiz-neural-network [PDF]
Nuclear Fusion, 2023 This work applies the coupled JINTRAC and QuaLiKiz-neural-network (QLKNN) model on the ohmic current ramp-up phase of a JET D discharge. The chosen scenario exhibits a hollow $T_\mathrm{e}$ profile attributed to core impurity accumulation, which is ...
C D Challis
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Nuclear FusionDesigning a robust termination scenario for a burning ITER plasma is a challenge that requires extensive core plasma and divertor modelling. The presented work consists of coupled core/edge/SOL/divertor simulations, performed with the JINTRAC code, to ...
E Tholerus, G Corrigan, Y Baranov
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Nuclear FusionIn the initial stages of ITER operation, ELM mitigation systems need to be commissioned. This requires controlled flat-top operation in type-I ELMy H-mode regimes.
E Tholerus, V Parail, Y Baranov
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ELM and inter-ELM tungsten erosion sources in high-power, JET ITER-like wall H-mode plasmas
Nuclear Materials and Energy, 2022 Simulations of JET ITER-like wall high-confinement mode plasmas, including type-I edge-localised modes (ELMs), using JINTRAC for the background plasmas and ERO2.0 for tungsten erosion and transport, predict virtually perfect screening of the primary W ...
M O'Mullane
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JINTRAC: A System of Codes for Integrated Simulation of Tokamak Scenarios
Plasma and Fusion Research, 2014 Operation and exploitation of present and future Tokamak reactors require advanced scenario modeling in order to optimize engineering parameters in the design phase as well as physics performance during the exploitation phase. The simulation of Tokamak scenarios involves simultaneous modeling of different regions of the reactor, characterized by ...
S Wiesen, R Ambrosino, L Garzotti
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Effect of PFC Recycling Conditions on JET Pedestal Density [PDF]
Contributions To Plasma Physics, 2016 There is experimental evidence that the pedestal dynamics in type-I ELMy H-mode discharges is significantly affected by a change in the recycling conditions at the tungsten plasma-facing components (W-PFCs) after an ELM event.
S Wiesen, S Brezinsek, D Harting
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Nuclear Fusion, 2013 Self-consistent transport simulation of ITER scenarios is a very important tool for the exploration of the operational space and for scenario optimisation.
V Parail, R Albanese, R Ambrosino
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Validation of EDGE2D-EIRENE and DIVIMP for W SOL transport in JET
Nuclear Materials and Energy, 2020 Tungsten sputtering rates and density profiles predicted using the edge plasma codes EDGE2D-EIRENE and DIVIMP are found to agree within a factor of 4 with measurements of neutral and singly-ionized W spectral line emission in the JET low-field side (LFS)
H Kumpulainen, M Groth, G Corrigan
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Global JINTRAC Simulations for ITER PFPO Scenario Development [PDF]
Nuclear Fusion, 2021 The inductive goal of ITER is to produce 500s long burning plasmas with Q = Pfus/Paux >=10[1]. This requires the development of operationally robust scenarios that span the whole plasma discharge from startup to termination not only in Deuterium Tritium (DT) but also in the Pre Fusion-Plasma Operation (PFPO) phase in Hydrogen (H) and Helium (He).
Militello Asp E +15 more
openaire +2 more sources
Assessment of the ITER divertor bolometer diagnostic performance
Nuclear Materials and Energy, 2023 The ITER bolometer diagnostic will provide measurements of the total radiation emitted from the plasma, a part of the overall energy balance. It will consist of some 550 lines of sight (LOS) of bolometer detector, bundled in multiple individual cameras ...
M. Brank +9 more
doaj +1 more source