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UKAEA-CCFE-CP(24)012022
Investigations were undertaken into the thermal treatment of beryllium and tungsten to see if these materials can be detritiated in the Material Detritiation Facility (MDF) at UKAEA, allowing for the declassification of intermediate level waste (ILW) to low level waste (LLW). When heated in oxygen, both tungsten and beryllium readily oxidise, wi…
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UKAEA-CCFE-PR(23)1882022
In 2019, the JET-ILW was equipped with a Shattered Pellet Injector (SPI) system with a wide capability to allow studies on the efficacy of shattered pellets in reducing the electro-magnetic and the thermal loads during disruptions and the avoidance/suppression of the formation of runaway electrons. The fully commissioned system became operationa…
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UKAEA-CCFE-CP(23)592022
Investigations were undertaken into the thermal treatment of beryllium and tungsten to see if these materials can be detritiated in the Material Detritiation Facility (MDF) at UKAEA, allowing for the declassification of intermediate level waste (ILW) to low level waste (LLW). When heated in oxygen, both tungsten and beryllium readily oxidise, wi…
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UKAEA-CCFE-CP(23)542022
Several Ion Cyclotron Resonance Heating (ICRH) schemes in DT plasma have been considered for the ITER reactor [1]. Most of these heating schemes are minority heating at fundamental frequency. In DT plasma, both reactants can also absorb RF power as majorities at fundamental n=1 or harmonic n=2 frequency. Understanding benefits of directly heatin…
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UKAEA-STEP-CP(23)102022
The work presented in this paper is an integrated time-dependent model, describing the power demands of the major tokamak components (magnets, cryogenics, heating and current drive, etc.), as well as the power generated. The physics are implemented in OpenModelica and make use of a Python API (Application Programming Interface) to collect inputs, r…
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UKAEA-CCFE-PR(23)1142022
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 Te profile attributed to core impurity accumulation, which is observed to worsen with the increasing fuel ion mass from D to T. A dynamic D simulation was validated, evolvi…
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UKAEA-CCFE-PR(23)1132022
The Joint European Torus (JET) is operated with the ITER-Like Wall (JET-ILW): beryllium in the main chamber and tungsten in the divertor in order to replicate materials for ITER. It was present systematic and quantitative study of tritium retention in dust and divertor tiles of ILW by means of tritium imaging plate technique to assess tritium le…
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UKAEA-CCFE-CP(23)492022
JET’s frequency-modulated continuous-wave (FMCW) reflectometers have been operating well with the current design since 2005 and density profiles are being automatically calculated intershot since then[1]. However, the calculated profiles had long suffered from several shortcomings – poor agreement to other diagnostics; sometimes inappropriat…
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UKAEA-CCFE-CP(23)482022
Recent experiments performed in JET at high level of plasma heating, in preparation of, and during the DT campaign have shown significant discrepancies between electron temperature measurements by Thomson Scattering (TS) and Electron Cyclotron Emission (ECE). In order to perform a systematic analysis of this effect, a simple model of bipolar dis…
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UKAEA-CCFE-CP(23)462022
Accurate and consistent measurements of the electron temperature (Te) profile are paramount for current fusion experiments, like JET, and future devices, such as ITER. In high performance plasmas in JET and TFTR, electron cyclotron emission (ECE) measurements for central Te>5 keV were systematically found to be up to 20%…
Showing 91 - 100 of 510 UKAEA Paper Results