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UKAEA-CCFE-PR(24)032024
To design a safe 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, studying the Q=10 flat-top phase and exit phase of the ITER 15MA/5.3T DT scenario. The modelling uti…
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UKAEA-CCFE-PR(25)2682023
In 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. Hydrogen or helium plasma discharges are used exclusively in these stages to ensure no production of neutrons from fusion reactions. With the expected higher L-H power threshold of hy…
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UKAEA-CCFE-PR(24)2452023
2021 JET experimental campaign has produced high stationary fusion power with 50%D 50%T discharges, operated with the ITER-relevant conditions i.e. operation with the baseline or hybrid scenario in the full metallic wall. It has provided a unique opportunity to assess the DT fusion power prediction capability before ITER DT experiments. This pap…
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UKAEA-CCFE-CP(23)282021
An important part of the ITER Research Plan [1] is the Pre-Fusion Power Operation (PFPO) phase, which includes demonstration of H-mode plasma operation and the commissioning of ELM control systems. However, since hydrogen or helium are the main ion species in PFPO plasmas, the L–H power threshold PL–H is expected to be cons…
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UKAEA-CCFE-PR(21)772021
The optimum conditions for access to and sustainment of H-mode plasmas and their expected plasma parameters in the Pre-Fusion Power Operation 1 (PFPO-1) phase of the ITER Research Plan, where the additional plasma heating will be provided by 20 MW of Electron Cyclotron Heating (ECH), are assessed in order to identify key open R&D issues. The as…
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UKAEA-CCFE-PR(21)772021
The optimum conditions for access and sustainment of H-mode plasmas and their expected plasma parameters in the Pre-Fusion Operation 1 (PFPO-1) phase of the ITER Research Plan, where the additional plasma heating will be provided by 20 MW of Electron Cyclotron Heating (ECH), are assessed. The assessment is performed on the basis of empirical and…
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UKAEA-CCFE-CP(21)082021
The pedestal plays an important role in determining the confinement in tokamak H-mode plasmas. However, the steep pressure gradients in this transport barrier also lead to edge localized modes (ELMs) [1]. There is good understanding of the pedestal in type I ELM regimes [2], however, type I ELMs are known to damage plasma facing components and f…
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UKAEA-CCFE-PR(18)702018
We report results of the benchmarking of core particle transport simulations by the codes widely used in the interpretative transport analyses and predictive modelling of tokamak plasmas. Our analysis includes formulation of transport equations, difference between electron and ion particle solvers, comparison of simulations of particle sinks and so…
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2008
The Integrated tokamak modelling taskforce was set up to provide the European scientific community with simulation tools for preparing and analysing discharges of fusion experiments. We will report on recent progress made on the taskforce project on equilibrium and linear stability. A generic data structure has been devised to describe the geometry…
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