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UKAEA-CCFE-CP(19)382019
As part of the preparation for the second JET DT campaign (DTE2), a series of isotope control experiments in H/D mixtures [1] have shown that NBI fuelling species has only a weak effect on the core isotope composition, which remains determined by the edge H/D ratio and therefore by the injected gas.
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UKAEA-CCFE-PR(18)322018
Progress in understanding lower hybrid current drive (LHCD) at high density has been made through experiments and modeling, which is encouraging given the need for an efficient off-axis current profile control technique in burning plasma. By reducing the wall recycling of neutrals, the edge temperature is increased and the effect of parametric inst…
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UKAEA-CCFE-PR(18)292018
FISPACT-II is an advanced activation/transmutation and inventory code that employs the most up-to-date and sophisticated nuclear data forms, including the full TENDL-2017 library. TENDL includes residual nuclide production for incident particle energies up to 200 MeV. To address the needs of activation-transmutation simulation in incident-particle …
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UKAEA-CCFE-PR(18)162018
The processing code SPECTRA-PKA produces energy spectra of primary atomic recoil events (or primary knock-on atoms, PKAs) for any material composition exposed to an irradiation spectrum. Such evaluations are vital inputs for simulations aimed at understanding the evolution of damage in irradiated material, which is generated in cascade displacement…
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CCFE-PR(17)582017
Methods for density control are of critical importance for future long pulse tokamaks. The EMC3-EIRENE code is being used to investigate the applicability of 3D non-axisymmetric fields for density control in standard and advanced divertor configurations in spherical tokamaks. Part of this effort is understanding Scrape Off layer (SOL) transport mec…
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CCFE-PR(16)152016
Accurately quantifying the transmutation rate of tungsten (W) under neutron irradiation is a necessary requirement in the assessment of its performance as an armour material in a fusion power plant. The usual approach of calculating average responses, assuming large, homogenised material volumes, is insu?cient to capture the full complexity of the …
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CCFE-PR(16)532016
Fispact-II is a code system and library database for modelling activation-transmutation processes depletion-burn-up, time dependent inventory and radiation damage source terms caused by nuclear reactions and decays. The Fispact-II code, written in object-style Fortran, follows the evolution of material irradiated by neutrons, alphas, gammas, proto…
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2016
Demountable superconducting magnet coils would offer signi fi cant benefits to commercial nuclear fusion power plants. Whether large pressed joints or large soldered joints provide the solution for demountable fusion magnets, a critical component or building block for both will be the many, smaller-scale joints that enable the supercurrent to leave…
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CCFE-PR(15)882015
Verification is the fundamental step that any turbulence simulation code has to be submitted in order to assess the proper implementation of the underlying equations. We have carried out a cross comparison of three flux tube gyrokinetic codes, GENE [F. Jenko et al., Phys. Plasmas 7, 1904 (2000)], GKW [A. G. Peeters et al., Comput. Phys. Commun. 180…
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CCFE-PR(15)342015
A one dimensional model of the magnetic multipole volume plasma source has been developed for use in intense ion/neutral atom beam injectors. The model uses plasma transport coefficients for particle and energy flow to create a detailed description of the plasma parameters along an axis parallel to that of the extracted beam. Primarily constructed …
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