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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-PR(24)022023
This work studies the influence of RF waves in ICRH range of frequency on fusion alphas during recent JET D-T campaign. Fusion alphas from D-T reactions are born with energies of about 3.5MeV and therefore have significant Doppler shift enabling synergistic interaction between them and RF waves at broad range of frequencies including the ones fo…
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UKAEA-CCFE-PR(23)1862023
In recent years, physics-informed neural networks (PINN) have been used to solve stiff-PDEs mostly in the 1D and 2D spatial domain. PINNs still experience issues solving 3D problems, especially, problems with conflicting boundary conditions at adjacent edges and corners. These problems have discontinuous solutions at edges and corners that are di…
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UKAEA-CCFE-PR(23)1702023
Neutral Beam Injection (NBI) is a flexible auxiliary heating method for tokamak plasmas, capable of being efficiently coupled to the various plasma configurations required in the Tritium and mixed DeuteriumTritium Experimental campaign (DTE2) on the JET device. High NBI power was required for high fusion yield and alpha particle studies and to …
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UKAEA-CCFE-PR(23)1212023
In the paper we present an overview of interpretive modelling of a database of JET-ILW 2021 D-T discharges using the TRANSP code. Our main aim is to assess our capability of computationally reproducing the fusion performance of various D-T plasma scenarios using different external heating and D-T mixtures, and understand the performance driving mec…
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UKAEA-STEP-CP(24)022022
The UK’s Spherical Tokamak for Energy Production (STEP) reactor design program has recently taken the decision to use exclusively microwave-based heating and current drive (HCD) actuators for its reactor concepts. This is based on a detailed assessment considering all viable HCD concepts, covering the grid to plasma efficiency (), physics applica…
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UKAEA-CCFE-PR(23)1342022
During operation, structural components made of zirconium alloys are subject to neutron irradiation, which leads to the displacement of zirconium atoms from their lattice sites, the production of self-interstitials and vacancies, and eventually dislocation loops. This process can lead to deleterious effects such as irradiation growth, creep and …
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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-CCFE-CP(23)352021
Neutral Beam Injection (NBI) is a very flexible auxiliary heating method for tokamak plasmas, capable of being efficiently coupled to the various plasma configurations required in the Tritium and Deuterium–Tritium Experimental campaign (DTE2) to be undertaken in the JET device. In particular, experiments for high fusion yield and alpha particl…
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UKAEA-CCFE-PR(21)692021
The ASCOT orbit-following code has been equipped with a model for simulating charge exchange (CX) of fast ions with background atoms in magnetically confined fusion plasmas. The model was successfully verified by comparing simulated reaction mean free paths to analytical values across a range of fusion-relevant parameters. ASCOT was used to simulat…
Showing 1 - 10 of 11 UKAEA Paper Results