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UKAEA-CCFE-PR(22)092022
Experiments in ASDEX Upgrade (AUG) and JET with the ITER-like wall (JET-ILW) are performed to separate the pedestal and core contributions to confinement in H-modes with different main ion masses. A strong isotope mass dependence in the pedestal is found which is enhanced at high gas puffing. This is because the ELM type changes when going fro…
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UKAEA-CCFE-PR(25)2742021
Efficient plasma core fuelling is a key issue for achieving steady-state scenarios in large magnetic confinement fusion devices. At present, the most promising technique to achieve this goal is the injection of cryogenic pellets. In this paper, the injection of nominal pellets into standard plasma scenarios in the tokamak ITER and the ste…
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UKAEA-CCFE-PR(24)2372021
Control of the detachment front between the target and the X-point is necessary for minimizing the effect of detachment on the core plasma (core radiation and loss of confinement) and maximizing the divertor functions (reduction of target heat load and sputtering, He pumping). However, such control has been difficult in experiments. The SOLPS-IT…
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UKAEA-CCFE-CP(23)392021
A key aim of the 2021 JET deuterium-tritium (D-T) experiments was to demonstrate steady high fusion power (10-15MW) with the ITER-like Be/W first wall. Plasmas were developed using D, repeated with T to investigate and mitigate isotope effects, and run with D-T to maximise fusion power. Compared with high current (q95~3) ‘baseline’ plasmas, …
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UKAEA-STEP-CP(23)032021
The application of dc magnetic field to a 2G high temperature superconducting (HTS) tape can reduce the critical current Ic of the tape, without driving the material normal. This property can be used in the development of HTS switching elements through so-called Jc(B) switching. The design of a dc magnetic field switch is reported, in both singl…
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UKAEA-CCFE-PR(23)1032021
This paper provides an overview of the status of the laser diagnostics to be implemented on ITER. This includes descriptions of the Thomson scattering in the Core, Edge and Divertor regions, polarimetry and interferometry diagnostics used for measuring plasma density and also measurements of Helium density in the divertor using Laser Induced Flo…
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UKAEA-CCFE-CP(23)312021
Alfvén eigenmode (AE) instabilities driven by α-particles have been observed in D-3He fusion experiments on the Joint European Torus (JET) with the ITER-like wall [Kiptily et al, submitted to Phys. Rev. Letters, 2020]. The impact of these type instabilities on a burning plasma is of crucial relevance for the perfor…
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UKAEA-CCFE-PR(23)1002021
The properties of tungsten make it ideal for use as a plasma facing surface in the divertor of large plasma machines such as JET and ITER. However, the intense heat and particle fluxes that fall on the divertor surfaces lead to its release from these surfaces into the plasma and it is necessary to model its transport from the divertor and plasma…
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UKAEA-CCFE-CP(23)302021
Many of the essential data analysis procedures for a tokamak experiment rely on the knowledge of the magnetic field structure obtained from MHD force balance. On JET, the code that is responsible for computing the magnetic equilibrium is called EFIT++. Interpretation of JET data has been challenging due to inconsistencies between diagnostic meas…
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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…
Showing 71 - 80 of 266 UKAEA Paper Results