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151. The role of the source versus the collisionality in predicting a reactor density profile as observed on ASDEX Upgrade discharges.

Author

E. Fable, C. Angioni, V. Bobkov, J. Stober, R. Bilato, G.D. Conway, T. Goerler, R.M. McDermott, T. Puetterich, M. Siccinio, W. Suttrop, M. Teschke, H. Zohm, and Team, the ASDEX Upgrade

Subjects
*FUSION reactors, *PLASMA density, *DENSITY, *HEAT flux, *POWER density, *PHYSICS
Abstract

The design and optimization of a future tokamak fusion reactor, from the point of view of the plasma performance and output fusion power, requires the understanding of the underlying physics and the validation on present experiments of the theory-based tools used for the predictions. Present experimental efforts are devoted to approach reactor-relevant parameters (collisionality, , normalized heat fluxes and sources, temperatures ratio) as much as possible. In this work a series of discharges performed on ASDEX Upgrade are presented, where plasma density and auxiliary power levels are scanned to cover a parameter space that moves towards reactor relevant parameters. On this dedicated discharge dataset, a first-principle-based model is then applied for validation. The degree of agreement between code results and experimental measurements is shown and discussed. In cases where discrepancy is found, possible causes are identified. It is shown that the employed modeling tool can predict the overall trend, consistent with more fundamental theoretical considerations, although quantitative extrapolation still has to be performed with care. Key results of this work show that the density peaking is mainly sustained by turbulence, with a minor role for the fueling source, and how this experimental demonstration is important to predict future reactor density profiles. Moreover, the role of electromagnetic effects is also pointed out. [ABSTRACT FROM AUTHOR]

Published
2019
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152. Perturbative transport modeling of cold-pulse dynamics in Alcator C-Mod Ohmic plasmas.

Author

P. Rodriguez-Fernandez, A.E. White, N.T. Howard, B.A. Grierson, X. Yuan, G.M. Staebler, J.E. Rice, C. Angioni, N.M. Cao, A.J. Creely, E. Fable, M.J. Greenwald, A.E. Hubbard, J.W. Hughes, J.H. Irby, and F. Sciortino

Subjects
PLASMA confinement, PLASMA density, PLASMA currents, PLASMA boundary layers, ELECTRON temperature, ION temperature
Abstract

Perturbative transport experiments in magnetically confined plasmas have shown, for more than 20 years, that the injection of cold pulses at the plasma edge can trigger the increase of core temperature. Predictive heat transport simulations with the trapped gyro Landau fluid (TGLF) quasilinear transport model demonstrate that the increase of core temperature in some regimes, and lack thereof in other regimes, can be explained by a change in dominant linear micro-instability in Alcator C-Mod. The effect of density and plasma current on the cold pulse are well captured by TGLF, including the relative change in position of the temperature flex point as current density changes. Linear stability analysis of simulated density and current scans reveals a competition between trapped electron and ion temperature gradient modes as the main driver of the core transient response. These results further demonstrate that cold-pulse propagation and associated phenomenology in the cases studied are well explained within the local transport paradigm, without resorting to non-local effects. [ABSTRACT FROM AUTHOR]

Published
2019
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153. Determination of the tolerable impurity concentrations in a fusion reactor using a consistent set of cooling factors.

Author

T. Pütterich, E. Fable, R. Dux, M. O’Mullane, R. Neu, and M. Siccinio

Subjects
*FUSION reactors, *INDUSTRIAL contamination, *NUCLEAR reactor design & construction, *NUCLEAR charge, *SOFT X rays, *PLASMA pressure
Abstract

In the present work, the tolerable impurity level and composition for a reactor plasma using several sets of model assumptions are evaluated. Special care was taken to evaluate a comprehensive and consistent set of atomic data for 35 different elements, such that the impurity level for various elements may be studied as a function of their nuclear charge. The data set may not only be useful for the presented work or for system codes which design fusion reactors, but also for interpretation of bolometric measurements. Additionally, the predictions of the spectral distribution of the radiated power is of high quality such that soft x-ray broadband measurements may be interpreted. In the present work the data is used for predicting the radiated power in a reactor plasma, using a 0D, several variants of a 0.5D model and a realistic 1D ASTRA modelling of a DEMO plasma, i.e. the EU DEMO1 2015 design. The maximal or appropriate impurity content of a reactor plasma for all models can be determined, such that the predictions from a simplistic 0D model can be compared to less simplistic models and a proper reactor simulation. These comparisons suggest that with the simplistic models the impurity content may be estimated within a factor of about 1.5, independent of the realization of the reactor plasma. At the same time this study underlines the sensitivity of the reactor performance on the impurity mixture and especially of the He content of the plasma. Additionally, an extended 0.5D model is presented which is able to predict variations of the fusion yield Q and the He concentration, when both is known for a reference scenario. These predictions prove to be of high accuracy when compared to the 1D ASTRA modelling and thus, allow the net impact of an increased dilution and a simlutaneous temperature rise at constant plasma pressure to be evaluated. Furthermore, the parameter space is scanned with more than 105 model reactor plasmas demonstrating that the use of a low-Z impurity diminishes the possibility of an economical feasible reactor plasma. The main results of the parameter scan are made available via scaling formulae. [ABSTRACT FROM AUTHOR]

Published
2019
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154. Theoretical studies and simulations of mode structure symmetry breaking in tokamak plasmas in the presence of energetic particles.

Author

Z X Lu, X Wang, Ph Lauber, E Fable, A Bottino, W Hornsby, T Hayward-Schneider, F Zonca, and C Angioni

Subjects
FUSION reactors, SYMMETRY, PARTICLES, CHOICE of transportation, TURBULENCE
Abstract

The mode structure symmetry breaking is important for the understanding of the momentum transport induced by micro turbulence and the experimental observation of Alfvénic mode structures driven by energetic particles (EPs) as well as the burning plasma behavior. In this work, the theoretical approach for the analyzes of the global mode structure in the presence of EPs is introduced with various applications. As a brief review of our previous work, the calculation of strongly coupled poloidal harmonics, with a complex ‘tilting angle’ applied, and the calculation of weakly coupled poloidal harmonics, with EPs’ non-perturbative effects taken into account, are introduced. By making use of the theoretical approach, several applications related to the mode structure symmetry breaking are demonstrated. The anisotropic EP impact on the zonal flow residual is calculated. The mode structure symmetry breaking of the EP induced geodesic acoustic mode is studied. The momentum transport related to the mode structure symmetry breaking is estimated. The particle and energy transport is also analyzed and its comparison with the turbulence induced transport is discussed. [ABSTRACT FROM AUTHOR]

Published
2019
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155. Flux-driven integrated modelling of main ion pressure and trace tungsten transport in ASDEX Upgrade.

Author

O. Linder, J. Citrin, G.M.D. Hogeweij, C. Angioni, C. Bourdelle, F.J. Casson, E. Fable, A. Ho, F. Koechl, M. Sertoli, Team, the EUROfusion MST1, and Team, the ASDEX Upgrade

Subjects
TUNGSTEN, TOKAMAKS, PLASMA confinement, ELECTRON temperature, ION temperature, GAUSSIAN processes, MAGNETOHYDRODYNAMICS, PLASMA turbulence
Abstract

Neoclassical and turbulent heavy impurity transport in tokamak core plasmas are determined by main ion temperature, density and toroidal rotation profiles. Thus, in order to understand and prevent experimental behaviour of W accumulation, flux-driven integrated modelling of main ion heat and particle transport over multiple confinement times is a vital prerequisite. For the first time, the quasilinear gyrokinetic code QuaLiKiz is applied for successful predictions of core kinetic profiles in an ASDEX Upgrade H-mode discharge in the turbulence dominated region within the integrated modelling suite JETTO. Neoclassical contributions are calculated by NCLASS; auxiliary heat and particle deposition profiles due to NBI and ECRH are prescribed from previous analysis with TRANSP. Turbulent and neoclassical contributions are insufficient in explaining main ion heat and particle transport inside the q  =  1 surface, necessitating the prescription of further transport coefficients to mimic the impact of MHD activity on central transport. The ion to electron temperature ratio at the simulation boundary at stabilizes ion scale modes while destabilizing ETG modes when significantly exceeding unity. Careful analysis of experimental measurements using Gaussian process regression techniques is carried out to explore reasonable uncertainties. In following trace W impurity transport simulations performed with additionally NEO, neoclassical transport under consideration of poloidal asymmetries alone is found to be insufficient to establish hollow central W density profiles. Reproduction of these conditions measured experimentally is found possible only when assuming the direct impact of a saturated MHD mode on heavy impurity transport. [ABSTRACT FROM AUTHOR]

Published
2019
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156. Recent electron cyclotron emission results on TCV

Author

Ch. Schlatter, Timothy Goodman, B. P. Duval, Victor Udintsev, P. Blanchard, A. Gudozhnik, Ph. Marmillod, Francesca Turco, M. A. Henderson, Olivier Sauter, L. Porte, E. Asp, H. Weisen, I. Klimanov, H. Shidara, M. Goniche, G. Turri, A. Mueck, X. Llobet, P. F. Isoz, G. Giruzzi, Stefano Coda, and E. Fable

Subjects
Physics, Nuclear and High Energy Physics, 020209 energy, Mechanical Engineering, Cyclotron, Magnetic confinement fusion, 02 engineering and technology, Electron, Tore Supra, 01 natural sciences, 010305 fluids & plasmas, law.invention, Nuclear Energy and Engineering, Physics::Plasma Physics, law, 0103 physical sciences, 0202 electrical engineering, electronic engineering, information engineering, Electron temperature, General Materials Science, Microturbulence, Tokamak à configuration variable, Atomic physics, Magnetohydrodynamics, Civil and Structural Engineering
Abstract

Electron cyclotron emission (ECE) diagnostics on Tokamak a Configuration Variable (TCV) allow study of the electron temperature evolution in time with good spatial and temporal resolution at the high field side and low field side at various lines of sight. That is why ECE is being widely used to obtain both qualitative and quantitative information on heat transport, magnetohydrodynamics (MHD) phenomena, and fast electron dynamics. In this paper, a new regime on TCV with regular oscillations of the electron temperature in electron cyclotron current drive (ECCD) driven fully noninductive discharges and in discharges with a combination of ohmic/ECCD driven current is discussed These oscillations are reminiscent of the oscillations of the central electron temperature (O-regime) seen on Tore Supra in fully noninductive lower hybrid current drive plasmas. A link between evolutions of the electron temperature, the MHD modes, and the current density profile on TCV is considered In order to yield information on the properties of microturbulence of electrostatic and magnetic origin on TCV, a correlation ECE radiometer is currently under development. A technical description of the diagnostic is presented in this paper.

157. MHD as trigger of electron temperature oscillations in ECCD discharges in TCV

Author

E. Fable, Timothy Goodman, Victor Udintsev, Olivier Sauter, and G. Turri

Subjects
Nuclear physics, Physics, Nuclear Energy and Engineering, Web of science, Electron temperature, Magnetohydrodynamics, Condensed Matter Physics
Abstract

Reference CRPP-ARTICLE-2009-048doi:10.1088/0741-3335/50/6/065010View record in Web of Science Record created on 2009-01-28, modified on 2017-05-12

158. Application of the singular value decomposition method for inversion of interferometer measurements in fusion plasmas

Author

C. Angioni, E. Fable, C. Carey, H. Weisen, Ivo Furno, and R. Behn

Subjects
Physics, business.industry, Thomson scattering, Basis function, Orthogonal basis, Overdetermined system, Interferometry, Optics, Physics::Plasma Physics, Singular value decomposition, Astronomical interferometer, Plasma diagnostics, business, Instrumentation
Abstract

We present applications of a recently developed method, the singular value decomposition inversion (SVD-I), for inverting line integrated multichannel interferometer measurements in fusion devices. The method expands the local electron density profiles into a limited series of orthogonal basis functions formed from the singular value decomposition of Thomson scattering measurements, which are obtained at much lower frequencies than the interferometer data. Because these basis functions are formed from a local measurement of the electron densities in the same plasmas, they are well adapted to the class of density profiles to be reconstructed. Using this expansion, the inversion of the interferometer data are reduced to solving an overdetermined set of equations. SVD-I is significantly faster than regularization methods and more accurate for reconstructing hollow profiles. This method, which combines the high bandwidth of interferometer systems with the spatial accuracy of Thomson scattering, is applied to invert data from a 14-chord interferometer on the TCV tokamak. (C) 2004 American Institute of Physics.

159. Transport of tungsten in the H-mode edge transport barrier of ITER

Author

R. Dux, A.S. Kukushkin, A. Loarte, E. Fable, and ASDEX Upgrade Team

Subjects
Convection, Materials science, Physics::Instrumentation and Detectors, Divertor, chemistry.chemical_element, Plasma, Tungsten, Condensed Matter Physics, 7. Clean energy, Pedestal, Nuclear Energy and Engineering, chemistry, Physics::Plasma Physics, Sputtering, Atomic physics, Scaling, Helium
Abstract

The neoclassical transport of tungsten in the H-mode edge transport barrier (ETB) of ITER is investigated and scaling relations for the transport coefficients are evaluated. The major finding is that the radial convection velocity of tungsten is outward directed for a large proportion of the tested pedestal profiles. This is due to a combination of the high pedestal temperatures and the high separatrix densities making the outward directed temperature screening term the predominant contribution of the collisional convection. The high densities at the separatrix are needed to control the power exhaust and the tungsten sputtering in the divertor and the high pedestal temperatures are expected to be achieved in ITER to meet its fusion performance objectives. The density and temperature profiles, which deliver simultaneously optimum fusion performance, power exhaust and tungsten sputtering control in ITER, also ensure optimum collisional radial transport of tungsten leading to hollow tungsten density profiles in the ETB. In helium H-mode plasmas, which are considered for the initial ITER non-active operation, this very favourable neoclassical transport effect is reduced and only about half of the considered edge plasma profiles yield an outward directed drift.

160. Linear stability analysis of microinstabilities in electron internal transport barrier non-inductive discharges

Author

Alberto Bottino, Olivier Sauter, E. Fable, and Yann Camenen

Subjects
Physics, Shear (sheet metal), Nuclear Energy and Engineering, Physics::Plasma Physics, Magnetic confinement fusion, Electron temperature, Electron, Tokamak à configuration variable, Atomic physics, Magnetohydrodynamics, Condensed Matter Physics, Fluid transport, Bootstrap current
Abstract

The role of the current profile and ion and electron temperature ratio in Tokamak A Configuration Variable (TCV) electron internal transport barrier (eITB) noninductive discharges is inspected by means of the linear gyrokinetic global code LORB5 (Bottino et al 2004 Phys. Plasmas 11 198) and the Gyro-Landau fluid transport model GLF23 (Waltz et al 1997 Phys. Plasmas 4 2482). In this work we have compared two different MHD equilibria for a TCV discharge with an eITB, corresponding to a monotonic and a reversed safety factor profile. The latter has been obtained using the calculated electron-cyclotron driven density profile, the bootstrap current and the experimental pressure. Global simulations show that the most unstable electrostatic instabilities in the spectrum are trapped electron modes (TEM) for both equilibria. In the vicinity of the reverse shear region, where the magnetic shear s is positive and small (s << 1), modes tend to preserve the ballooning structure but their mixing length estimate for the thermal diffusion coefficient is significantly reduced as compared with the monotonic q equilibrium. This effect is further increased in the reverse shear region. Simulations performed with GLF23 show that the inclusion of the Shafranov shift in the model has an important stabilizing effect in all the plasma core and, in particular, in the barrier region. However, the Shafranov shift and reverse shear stabilization are not the only mechanisms through which the q profile affects the stability of the system. The local value of q in the barrier region also contributes to the stabilization. Global gyrokinetic and local Gyro-Landau fluid results suggest that the current profile modification alone, with the consequent negative shear and Shafranov shift stabilization on TEM modes, can explain the presence of the ITB in these TCV discharges.

161. Current density evolution in electron internal transport barrier discharges in TCV

Author

E. Asp, Stefano Coda, Olivier Sauter, E. Fable, M. A. Henderson, Timothy Goodman, and C. Zucca

Subjects
Materials science, Tokamak, Physics, Plasma, Electron, Cyclotron Current Drive, Condensed Matter Physics, Electron transport chain, law.invention, Shear (sheet metal), Nuclear Energy and Engineering, law, Plasmas, Atomic physics, Current (fluid), Tokamak à configuration variable, Equilibria, Current density, Operation
Abstract

Simulations of the plasma current density evolution in electron internal transport barrier discharges on the Tokamak a Configuration Variable (TCV) have been performed, in order to determine the relationship between the safety-factor profile and the electron transport improvement. The results show that the formation of the transport barrier is correlated with the shear reversal in all cases studied, regardless of the different heating and current drive schemes. No indications were found of discrete effects related to low-order rational q surfaces. On the contrary, the increase in confinement along with the negative shear is gradual, but constant, indicating that the transition is smooth, although it can be very fast.

162. A scoping study of the application of neutral beam heating on the TCV tokamak

Author

E. Fable, A. N. Karpushov, B. P. Duval, J.-M. Mayor, René Chavan, H. Weisen, and Olivier Sauter

Subjects
Materials science, Tokamak, Mechanical Engineering, Nuclear engineering, Cyclotron, Electron, Plasma, Neutral beam injection, TCV tokamak, Ion, law.invention, Nuclear Energy and Engineering, law, General Materials Science, Neutral beam heating, Atomic physics, Magnetohydrodynamics, Beam (structure), Civil and Structural Engineering
Abstract

The TCV tokamak contributes to the physics understanding of fusion plasmas, broadening the parameter range of reactor relevant regimes, by investigations based on an extensive use of the existing main experimental tools: flexible shaping and high power real time-controllable electron cyclotron heating (ECH) and current drive (ECCD) systems. A proposed implementation of direct ion heating on the TCV by the installation of a 20–35 keV neutral beam injection (NBI) with a total power of 1–3 MW would permit an extension of the accessible range of ion to electron temperatures (Ti/Te ~ 0.1–0.8) to well beyond unity, depending on the NBI/ECH mix and the plasma density. A NBI system would provide TCV with a tool for plasma study at reactor relevant Ti/Te ratios ~ 1 and in investigating fast ion and MHD physics together with the effects of plasma rotation and high plasma β scenarios. The feasibility studies for a NBI heating on TCV presented in this paper were undertaken to construct a specification for the neutral beam injectors together with an experimental geometry for possible operational scenarios.

163. Overview of JET results for optimising ITER operation

Author

J. Mailloux, N. Abid, K. Abraham, P. Abreu, O. Adabonyan, P. Adrich, V. Afanasev, M. Afzal, T. Ahlgren, L. Aho-Mantila, N. Aiba, M. Airila, M. Akhtar, R. Albanese, M. Alderson-Martin, D. Alegre, S. Aleiferis, A. Aleksa, A.G. Alekseev, E. Alessi, P. Aleynikov, J. Algualcil, M. Ali, M. Allinson, B. Alper, E. Alves, G. Ambrosino, R. Ambrosino, V. Amosov, E.Andersson Sundén, P. Andrew, B.M. Angelini, C. Angioni, I. Antoniou, L.C. Appel, C. Appelbee, S. Aria, M. Ariola, G. Artaserse, W. Arter, V. Artigues, N. Asakura, A. Ash, N. Ashikawa, V. Aslanyan, M. Astrain, O. Asztalos, D. Auld, F. Auriemma, Y. Austin, L. Avotina, E. Aymerich, A. Baciero, F. Bairaktaris, J. Balbin, L. Balbinot, I. Balboa, M. Balden, C. Balshaw, N. Balshaw, V.K. Bandaru, J. Banks, Yu.F. Baranov, C. Barcellona, A. Barnard, M. Barnard, R. Barnsley, A. Barth, M. Baruzzo, S. Barwell, M. Bassan, A. Batista, P. Batistoni, L. Baumane, B. Bauvir, L. Baylor, P.S. Beaumont, D. Beckett, A. Begolli, M. Beidler, N. Bekris, M. Beldishevski, E. Belli, F. Belli, É. Belonohy, M. Ben Yaala, J. Benayas, J. Bentley, H. Bergsåker, J. Bernardo, M. Bernert, M. Berry, L. Bertalot, H. Betar, M. Beurskens, S. Bickerton, B. Bieg, J. Bielecki, A. Bierwage, T. Biewer, R. Bilato, P. Bílková, G. Birkenmeier, H. Bishop, J.P.S. Bizarro, J. Blackburn, P. Blanchard, P. Blatchford, V. Bobkov, A. Boboc, P. Bohm, T. Bohm, I. Bolshakova, T. Bolzonella, N. Bonanomi, D. Bonfiglio, X. Bonnin, P. Bonofiglo, S. Boocock, A. Booth, J. Booth, D. Borba, D. Borodin, I. Borodkina, C. Boulbe, C. Bourdelle, M. Bowden, K. Boyd, I.Božičević Mihalić, S.C. Bradnam, V. Braic, L. Brandt, R. Bravanec, B. Breizman, A. Brett, S. Brezinsek, M. Brix, K. Bromley, B. Brown, D. Brunetti, R. Buckingham, M. Buckley, R. Budny, J. Buermans, H. Bufferand, P. Buratti, A. Burgess, A. Buscarino, A. Busse, D. Butcher, E.de la Cal, G. Calabrò, L. Calacci, R. Calado, Y. Camenen, G. Canal, B. Cannas, M. Cappelli, S. Carcangiu, P. Card, A. Cardinali, P. Carman, D. Carnevale, M. Carr, D. Carralero, L. Carraro, I.S. Carvalho, P. Carvalho, I. Casiraghi, F.J. Casson, C. Castaldo, J.P. Catalan, N. Catarino, F. Causa, M. Cavedon, M. Cecconello, C.D. Challis, B. Chamberlain, C.S. Chang, A. Chankin, B. Chapman, M. Chernyshova, A. Chiariello, P. Chmielewski, A. Chomiczewska, L. Chone, G. Ciraolo, D. Ciric, J. Citrin, Ł. Ciupinski, M. Clark, R. Clarkson, C. Clements, M. Cleverly, J.P. Coad, P. Coates, A. Cobalt, V. Coccorese, R. Coelho, J.W. Coenen, I.H. Coffey, A. Colangeli, L. Colas, C. Collins, J. Collins, S. Collins, D. Conka, S. Conroy, B. Conway, N.J. Conway, D. Coombs, P. Cooper, S. Cooper, C. Corradino, G. Corrigan, D. Coster, P. Cox, T. Craciunescu, S. Cramp, C. Crapper, D. Craven, R. Craven, M.Crialesi Esposito, G. Croci, D. Croft, A. Croitoru, K. Crombé, T. Cronin, N. Cruz, C. Crystal, G. Cseh, A. Cufar, A. Cullen, M. Curuia, T. Czarski, H. Dabirikhah, A.Dal Molin, E. Dale, P. Dalgliesh, S. Dalley, J. Dankowski, P. David, A. Davies, S. Davies, G. Davis, K. Dawson, S. Dawson, I.E. Day, M. De Bock, G. De Temmerman, G. De Tommasi, K. Deakin, J. Deane, R. Dejarnac, D. Del Sarto, E. Delabie, D. Del-Castillo-Negrete, A. Dempsey, R.O. Dendy, P. Devynck, A. Di Siena, C. Di Troia, T. Dickson, P. Dinca, T. Dittmar, J. Dobrashian, R.P. Doerner, A.J.H. Donné, S. Dorling, S. Dormido-Canto, D. Douai, S. Dowson, R. Doyle, M. Dreval, P. Drewelow, P. Drews, G. Drummond, Ph. Duckworth, H. Dudding, R. Dumont, P. Dumortier, D. Dunai, T. Dunatov, M. Dunne, I. Ďuran, F. Durodié, R. Dux, A. Dvornova, R. Eastham, J. Edwards, Th. Eich, A. Eichorn, N. Eidietis, A. Eksaeva, H. El Haroun, G. Ellwood, C. Elsmore, O. Embreus, S. Emery, G. Ericsson, B. Eriksson, F. Eriksson, J. Eriksson, L.G. Eriksson, S. Ertmer, S. Esquembri, A.L. Esquisabel, T. Estrada, G. Evans, S. Evans, E. Fable, D. Fagan, M. Faitsch, M. Falessi, A. Fanni, A. Farahani, I. Farquhar, A. Fasoli, B. Faugeras, S. Fazinić, F. Felici, R. Felton, A. Fernandes, H. Fernandes, J. Ferrand, D.R. Ferreira, J. Ferreira, G. Ferrò, J. Fessey, O. Ficker, A.R. Field, A. Figueiredo, J. Figueiredo, A. Fil, N. Fil, P. Finburg, D. Fiorucci, U. Fischer, G. Fishpool, L. Fittill, M. Fitzgerald, D. Flammini, J. Flanagan, K. Flinders, S. Foley, N. Fonnesu, M. Fontana, J.M. Fontdecaba, S. Forbes, A. Formisano, T. Fornal, L. Fortuna, E. Fortuna-Zalesna, M. Fortune, C. Fowler, E. Fransson, L. Frassinetti, M. Freisinger, R. Fresa, R. Fridström, D. Frigione, T. Fülöp, M. Furseman, V. Fusco, S. Futatani, D. Gadariya, K. Gál, D. Galassi, K. Gałązka, S. Galeani, D. Gallart, R. Galvão, Y. Gao, J. Garcia, M. García-Muñoz, M. Gardener, L. Garzotti, J. Gaspar, R. Gatto, P. Gaudio, D. Gear, T. Gebhart, S. Gee, M. Gelfusa, R. George, S.N. Gerasimov, G. Gervasini, M. Gethins, Z. Ghani, M. Gherendi, F. Ghezzi, J.C. Giacalone, L. Giacomelli, G. Giacometti, C. Gibson, K.J. Gibson, L. Gil, A. Gillgren, D. Gin, E. Giovannozzi, C. Giroud, R. Glen, S. Glöggler, J. Goff, P. Gohil, V. Goloborodko, R. Gomes, B. Gonçalves, M. Goniche, A. Goodyear, S. Gore, G. Gorini, T. Görler, N. Gotts, R. Goulding, E. Gow, B. Graham, J.P. Graves, H. Greuner, B. Grierson, J. Griffiths, S. Griph, D. Grist, W. Gromelski, M. Groth, R. Grove, M. Gruca, D. Guard, N. Gupta, C. Gurl, A. Gusarov, L. Hackett, S. Hacquin, R. Hager, L. Hägg, A. Hakola, M. Halitovs, S. Hall, S.A. Hall, S. Hallworth-Cook, C.J. Ham, D. Hamaguchi, M. Hamed, C. Hamlyn-Harris, K. Hammond, E. Harford, J.R. Harrison, D. Harting, Y. Hatano, D.R. Hatch, T. Haupt, J. Hawes, N.C. Hawkes, J. Hawkins, T. Hayashi, S. Hazael, S. Hazel, P. Heesterman, B. Heidbrink, W. Helou, O. Hemming, S.S. Henderson, R.B. Henriques, D. Hepple, J. Herfindal, G. Hermon, J. Hill, J.C. Hillesheim, K. Hizanidis, A. Hjalmarsson, A. Ho, J. Hobirk, O. Hoenen, C. Hogben, A. Hollingsworth, S. Hollis, E. Hollmann, M. Hölzl, B. Homan, M. Hook, D. Hopley, J. Horáček, D. Horsley, N. Horsten, A. Horton, L.D. Horton, L. Horvath, S. Hotchin, R. Howell, Z. Hu, A. Huber, V. Huber, T. Huddleston, G.T.A. Huijsmans, P. Huynh, A. Hynes, M. Iliasova, D. Imrie, M. Imríšek, J. Ingleby, P. Innocente, K. Insulander Björk, N. Isernia, I. Ivanova-Stanik, E. Ivings, S. Jablonski, S. Jachmich, T. Jackson, P. Jacquet, H. Järleblad, F. Jaulmes, J.Jenaro Rodriguez, I. Jepu, E. Joffrin, R. Johnson, T. Johnson, J. Johnston, C. Jones, G. Jones, L. Jones, N. Jones, T. Jones, A. Joyce, R. Juarez, M. Juvonen, P. Kalniņa, T. Kaltiaisenaho, J. Kaniewski, A. Kantor, A. Kappatou, J. Karhunen, D. Karkinsky, Yu Kashchuk, M. Kaufman, G. Kaveney, Ye.O. Kazakov, V. Kazantzidis, D.L. Keeling, R. Kelly, M. Kempenaars, C. Kennedy, D. Kennedy, J. Kent, K. Khan, E. Khilkevich, C. Kiefer, J. Kilpeläinen, C. Kim, Hyun-Tae Kim, S.H. Kim, D.B. King, R. King, D. Kinna, V.G. Kiptily, A. Kirjasuo, K.K. Kirov, A. Kirschner, T. kiviniemi, G. Kizane, M. Klas, C. Klepper, A. Klix, G. Kneale, M. Knight, P. Knight, R. Knights, S. Knipe, M. Knolker, S. Knott, M. Kocan, F. Köchl, I. Kodeli, Y. Kolesnichenko, Y. Kominis, M. Kong, V. Korovin, B. Kos, D. Kos, H.R. Koslowski, M. Kotschenreuther, M. Koubiti, E. Kowalska-Strzęciwilk, K. Koziol, A. Krasilnikov, V. Krasilnikov, M. Kresina, K. Krieger, N. Krishnan, A. Krivska, U. Kruezi, I. Książek, A.B. Kukushkin, H. Kumpulainen, T. Kurki-Suonio, H. Kurotaki, S. Kwak, O.J. Kwon, L. Laguardia, E. Lagzdina, A. Lahtinen, A. Laing, N. Lam, H.T. Lambertz, B. Lane, C. Lane, E.Lascas Neto, E. Łaszyńska, K.D. Lawson, A. Lazaros, E. Lazzaro, G. Learoyd, Chanyoung Lee, S.E. Lee, S. Leerink, T. Leeson, X. Lefebvre, H.J. Leggate, J. Lehmann, M. Lehnen, D. Leichtle, F. Leipold, I. Lengar, M. Lennholm, E. Leon Gutierrez, B. Lepiavko, J. Leppänen, E. Lerche, A. Lescinskis, J. Lewis, W. Leysen, L. Li, Y. Li, J. Likonen, Ch. Linsmeier, B. Lipschultz, X. Litaudon, E. Litherland-Smith, F. Liu, T. Loarer, A. Loarte, R. Lobel, B. Lomanowski, P.J. Lomas, J.M. López, R. Lorenzini, S. Loreti, U. Losada, V.P. Loschiavo, M. Loughlin, Z. Louka, J. Lovell, T. 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Zocco, A. Zohar, V. Zoita, S. Zoletnik, V.K. Zotta, I. Zoulias, W. Zwingmann, I. Zychor, VTT Technical Research Centre of Finland, Culham Science Centre, Princeton Plasma Physics Laboratory, Department of Applied Physics, Uppsala University, European Commission, Forschungszentrum Jülich, Universidade Lisboa, Fusion and Plasma Physics, University of Milan - Bicocca, General Atomics, ITER, University of Toyama, CEA, Oak Ridge National Laboratory, Technical University of Madrid, Swiss Federal Institute of Technology Lausanne, Dutch Institute for Fundamental Energy Research, Royal Military Academy, Seoul National University, Chalmers University of Technology, Max-Planck-Institut für Plasmaphysik, KTH Royal Institute of Technology, Aalto-yliopisto, Aalto University, JET Contributor, Mailloux, Joelle, Chiariello, Andrea, Martone, Raffaele, Formisano, Alessandro, Mattei, Massimiliano, Faculdade de Engenharia, Universitat Politècnica de Catalunya. 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Subjects
Technology, TOKAMAKS, PLASMAS, overview, CONFINEMENT, plasma facing components (PFC), ILW, tritium operations, d-t preparation, deuterium, D–T preparation, nuclear technology, JET with ITER-like wall, isotope, Física::Física de fluids::Física de plasmes [Àrees temàtiques de la UPC], Settore FIS/01, GAS HANDLING-SYSTEM, JET, Overview, ITER-like wall (ILW), D-T preparation, energetic particles, scenario development, Shattered Pellet Injection (SPI), plasma-wall interactions (PWI), tritium, Physics, Settore ING-IND/18 - Fisica dei Reattori Nucleari, shutdown dose-rate, gas handling-system, Condensed Matter Physics, simulation, Fusion, Plasma and Space Physics, ilw, confinement, Physical Sciences, SIMULATION, JET with ITER-like wallisotope, ddc:620, performance, plasma facing components (pfc), Nuclear and High Energy Physics, DEUTERIUM, jet with iter-like wall, Fusion, plasma och rymdfysik, Physics, Fluids & Plasmas, BERYLLIUM, divertor, TRITIUM, Science & Technology, Reactors de fusió, tritium operation, Nuclear energy, PERFORMANCE, beryllium, SHUTDOWN DOSE-RATE, Fusion reactors, Physics and Astronomy, JET programme, Energia nuclear, DIVERTOR, ddc:600
Abstract

The JET 2019–2020 scientific and technological programme exploited the results of years of concerted scientific and engineering work, including the ITER-like wall (ILW: Be wall and W divertor) installed in 2010, improved diagnostic capabilities now fully available, a major neutral beam injection upgrade providing record power in 2019–2020, and tested the technical and procedural preparation for safe operation with tritium. Research along three complementary axes yielded a wealth of new results. Firstly, the JET plasma programme delivered scenarios suitable for high fusion power and alpha particle (a) physics in the coming D–T campaign (DTE2), with record sustained neutron rates, as well as plasmas for clarifying the impact of isotope mass on plasma core, edge and plasma-wall interactions, and for ITER pre-fusion power operation. The efficacy of the newly installed shattered pellet injector for mitigating disruption forces and runaway electrons was demonstrated. Secondly, research on the consequences of long-term exposure to JET-ILW plasma was completed, with emphasis on wall damage and fuel retention, and with analyses of wall materials and dust particles that will help validate assumptions and codes for design and operation of ITER and DEMO. Thirdly, the nuclear technology programme aiming to deliver maximum technological return from operations in D, T and D–T benefited from the highest D–D neutron yield in years, securing results for validating radiation transport and activation codes, and nuclear data for ITER. This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 and 2019–2020 under Grant Agreement No. 633053. Peer Reviewed Article signat per 1223 autors/autores: J. Mailloux1, N. Abid1, K. Abraham1, P. Abreu2, O. Adabonyan1, P. Adrich3, V. Afanasev4, M. Afzal1, T. Ahlgren5, L. Aho-Mantila6, N. Aiba7, M. Airila6, M. Akhtar1, R. Albanese8, M. Alderson-Martin1, D. Alegre9, S. Aleiferis10, A. Aleksa1, A.G. Alekseev11, E. Alessi12, P. Aleynikov13, J. Algualcil14, M. Ali1, M. Allinson1, B. Alper1, E. Alves2, G. Ambrosino8, R. Ambrosino8, V. Amosov15, E.Andersson Sunden16, P. Andrew13, B.M. Angelini17, C. Angioni18, I. Antoniou1, L.C. Appel1, C. Appelbee1, S. Aria1, M. Ariola8, G. Artaserse17, W. Arter1, V. Artigues18, N. Asakura7, A. Ash1, N. Ashikawa19, V. Aslanyan20, M. Astrain21, O. Asztalos22, D. Auld1, F. Auriemma23, Y. Austin1, L. Avotina24, E. Aymerich25, A. Baciero9, F. Bairaktaris26, J. Balbin27, L. Balbinot23, I. Balboa1, M. Balden18, C. Balshaw1, N. Balshaw1, V.K. Bandaru18, J. Banks1, Yu.F. Baranov1, C. Barcellona28, A. Barnard1, M. Barnard1, R. Barnsley13, A. Barth1, M. Baruzzo17, S. Barwell1, M. Bassan13, A. Batista2, P. Batistoni17, L. Baumane24, B. Bauvir13, L. Baylor29, P.S. Beaumont1, D. Beckett1, A. Begolli1, M. Beidler29, N. Bekris30,31, M. Beldishevski1, E. Belli32, F. Belli17, É. Belonohy1, M. Ben Yaala33, J. Benayas1, J. Bentley1, H. Bergsåker34, J. Bernardo2, M. Bernert18, M. Berry1, L. Bertalot13, H. Betar35, M. Beurskens36, S. Bickerton1, B. Bieg37, J. Bielecki38, A. Bierwage7, T. Biewer29, R. Bilato18, P. Bílková39, G. Birkenmeier18, H. Bishop1, J.P.S. Bizarro2, J. Blackburn1, P. Blanchard40, P. Blatchford1, V. Bobkov18, A. Boboc1, P. Bohm39, T. Bohm41, I. Bolshakova42, T. Bolzonella23, N. Bonanomi18, D. Bonfiglio23, X. Bonnin13, P. Bonofiglo43, S. Boocock1, A. Booth1, J. Booth1, D. Borba2,30, D. Borodin44, I. Borodkina39,44, C. Boulbe45, C. Bourdelle27, M. Bowden1, K. Boyd1, I.Bozicevic Mihalic46, S.C. Bradnam1, V. Braic47, L. Brandt48, R. Bravanec49, B. Breizman50, A. Brett1, S. Brezinsek44, M. Brix1, K. Bromley1, B. Brown1, D. Brunetti1,12, R. Buckingham1, M. Buckley1, R. Budny, J. Buermans51, H. Bufferand27, P. Buratti17, A. Burgess1, A. Buscarino28, A. Busse1, D. Butcher1, E.de la Cal9, G. Calabrò52, L. Calacci53, R. Calado2, Y. Camenen54, G. Canal55, B. Cannas25, M. Cappelli17, S. Carcangiu25, P. Card1, A. Cardinali17, P. Carman1, D. Carnevale53, M. Carr1, D. Carralero9, L. Carraro23, I.S. Carvalho2, P. Carvalho2, I. Casiraghi56, F.J. Casson1, C. Castaldo17, J.P. Catalan14, N. Catarino2, F. Causa12, M. Cavedon18, M. Cecconello16, C.D. Challis1, B. Chamberlain1, C.S. Chang43, A. Chankin18, B. Chapman1,57, M. Chernyshova58, A. Chiariello8, P. Chmielewski58, A. Chomiczewska58, L. Chone59, G. Ciraolo27, D. Ciric1, J. Citrin60, Ł. Ciupinski61, M. Clark1, R. Clarkson1, C. Clements1, M. Cleverly1, J.P. Coad1, P. Coates1, A. Cobalt1, V. Coccorese8, R. Coelho2, J.W. Coenen44, I.H. Coffey62, A. Colangeli17, L. Colas27, C. Collins29, J. Collins1, S. Collins1, D. Conka24, S. Conroy16, B. Conway1, N.J. Conway1, D. Coombs1, P. Cooper1, S. Cooper1, C. Corradino28, G. Corrigan1, D. Coster18, P. Cox1, T. Craciunescu63, S. Cramp1, C. Crapper1, D. Craven1, R. Craven1, M.Crialesi Esposito48, G. Croci56, D. Croft1, A. Croitoru63, K. Crombe51,64, T. Cronin1, N. Cruz2, C. Crystal32, G. Cseh22, A. Cufar65, A. Cullen1, M. Curuia66, T. Czarski58, H. Dabirikhah1, A.Dal Molin56, E. Dale1, P. Dalgliesh1, S. Dalley1, J. Dankowski38, P. David18, A. Davies1, S. Davies1, G. Davis1, K. Dawson1, S. Dawson1, I.E. Day1, M. De Bock13, G. De Temmerman13, G. De Tommasi8, K. Deakin1, J. Deane1, R. Dejarnac39, D. Del Sarto35, E. Delabie29, D. Del-Castillo-Negrete29, A. Dempsey67, R.O. Dendy1,57, P. Devynck27, A. Di Siena18, C. Di Troia17, T. Dickson1, P. Dinca63, T. Dittmar44, J. Dobrashian1, R.P. Doerner68, A.J.H. Donne´69, S. Dorling1, S. Dormido-Canto70, D. Douai27, S. Dowson1, R. Doyle67, M. Dreval71, P. Drewelow36, P. Drews44, G. Drummond1, Ph. Duckworth13, H. Dudding1,72, R. Dumont27, P. Dumortier51, D. Dunai22, T. Dunatov46, M. Dunne18, I. Duran39, F. Durodie51, R. Dux18, A. Dvornova27, R. Eastham1, J. Edwards1, Th. Eich18, A. Eichorn1, N. Eidietis32, A. Eksaeva44, H. El Haroun1, G. Ellwood13, C. Elsmore1, O. Embreus73, S. Emery1, G. Ericsson16, B. Eriksson16, F. Eriksson74, J. Eriksson16, L.G. Eriksson75, S. Ertmer44, S. Esquembri21, A.L. Esquisabel76, T. Estrada9, G. Evans1, S. Evans1, E. Fable18, D. Fagan1, M. Faitsch18, M. Falessi17, A. Fanni25, A. Farahani1, I. Farquhar1, A. Fasoli40, B. Faugeras45, S. Fazinic46, F. Felici40, R. Felton1, A. Fernandes2, H. Fernandes2, J. Ferrand1, D.R. Ferreira2, J. Ferreira2, G. Ferrò53, J. Fessey1, O. Ficker39, A.R. Field1, A. Figueiredo2, J. Figueiredo2,30, A. Fil1, N. Fil1,20, P. Finburg1, D. Fiorucci23, U. Fischer31, G. Fishpool1, L. Fittill1, M. Fitzgerald1, D. Flammini17, J. Flanagan1, K. Flinders1, S. Foley1, N. Fonnesu17, M. Fontana40, J.M. Fontdecaba9, S. Forbes1, A. Formisano8, T. Fornal58, L. Fortuna28, E. Fortuna-Zalesna61, M. Fortune1, C. Fowler1, E. Fransson74, L. Frassinetti34, M. Freisinger44, R. Fresa8, R. Fridström34, D. Frigione53, T. Fülöp73, M. Furseman1, V. Fusco24, S. Futatani17, D. Gadariya77, K. Gál69, D. Galassi40, K. Gałazka58, S. 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Zychor3 // 1 United Kingdom Atomic Energy Authority, Culham Science Centre, Abingdon, Oxon, OX14 3DB, United Kingdom of Great Britain and Northern Ireland 2 Instituto de Plasmas e Fusao Nuclear, Instituto Superior Técnico, Universidade de Lisboa, 1049-001 Lisboa, Portugal 3 National Centre for Nuclear Research (NCBJ), 05-400 Otwock-Swierk, Poland 4 Ioffe Physico-Technical Institute, 26 Politekhnicheskaya, St Petersburg 194021, Russia 5 University of Helsinki, PO Box 43, FI-00014 University of Helsinki, Finland 6 VTT Technical Research Centre of Finland, PO Box 1000, FIN-02044 VTT, Finland 7 National Institutes for Quantum and Radiological Science and Technology, Naka, Ibaraki 311-0193, Japan 8 Consorzio CREATE, Via Claudio 21, 80125 Napoli, Italy 9 Laboratorio Nacional de Fusión, CIEMAT, Madrid, Spain 10 NCSR ‘Demokritos’ 153 10, Agia Paraskevi Attikis, Greece 11 NRC Kurchatov Institute, 1 Kurchatov Square, Moscow 123182, Russia 12 Institute for Plasma Science and Technology, CNR, via R. Cozzi 53, 20125 Milano, Italy 13 ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 Saint Paul Lez Durance Cedex, France 14 Universidad Nacional de Educacion a Distancia, Dept Ingn Energet, Calle Juan del Rosal 12, E-28040 Madrid, Spain 15 Troitsk Insitute of Innovating and Thermonuclear Research (TRINITI), Troitsk 142190, Moscow Region, Russia 16 Department of Physics and Astronomy, Uppsala University, SE-75120 Uppsala, Sweden 17 Dip.to Fusione e Tecnologie per la Sicurezza Nucleare, ENEA C. R. Frascati, via E. Fermi 45, 00044 Frascati (Roma), Italy 18 Max-Planck-Institut für Plasmaphysik, D-85748 Garching, Germany 19 National Institute for Fusion Science, Oroshi, Toki, Gifu 509-5292, Japan 20 MIT Plasma Science and Fusion Center, Cambridge, MA 02139, United States of America 21 Universidad Politécnica de Madrid, Grupo I2A2, Madrid, Spain 22 Centre for Energy Research, POB 49, H-1525 Budapest, Hungary 23 Consorzio RFX, Corso Stati Uniti 4, 35127 Padova, Italy 24 University of Latvia, 19 Raina Blvd., Riga, LV 1586, Latvia 25 Department of Electrical and Electronic Engineering, University of Cagliari, Piazza d’Armi 09123 Cagliari, Italy 26 National Technical University of Athens, Iroon Politechniou 9, 157 73 Zografou, Athens, Greece 27 CEA, IRFM, F-13108 Saint Paul Lez Durance, France 28 Dipartimento di Ingegneria Elettrica Elettronica e Informatica, Università degli Studi di Catania, 95125 Catania, Italy 29 Oak Ridge National Laboratory, Oak Ridge, TN 37831, TN, United States of America 30 EUROfusion Programme Management Unit, Culham Science Centre, Culham, OX14 3DB, United Kingdom of Great Britain and Northern Ireland 31 Karlsruhe Institute of Technology, PO Box 3640, D-76021 Karlsruhe, Germany 32 General Atomics, PO Box 85608, San Diego, CA 92186-5608, United States of America 33 Department of Physics, University of Basel, Switzerland 34 Fusion Plasma Physics, EECS, KTH Royal Institute of Technology, SE-10044 Stockholm, Sweden 35 Institut Jean Lamour, UMR 7198, CNRS-Université de Lorraine, 54500 Vandoeuvre-lès-Nancy, France 36 Max-Planck-Institut für Plasmaphysik, Teilinsitut Greifswald, D-17491 Greifswald, Germany 37 Maritime University of Szczecin Faculty of Marine Engineering, Waly Chrobrego 1-2, 70-500 Szczecin, Poland 38 Institute of Nuclear Physics, Radzikowskiego 152, 31-342 Kraków, Poland 39 Institute of Plasma Physics of the CAS, Za Slovankou 1782/3, 182 00 Praha 8, Czech Republic 40 Ecole Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC), CH-1015 Lausanne, Switzerland 41 University of Wisconsin-Madison, Madison, WI 53706, United States of America 42 Magnetic Sensor Laboratory, Lviv Polytechnic National University, Lviv, Ukraine 43 Princeton Plasma Physics Laboratory, James Forrestal Campus, Princeton, NJ 08543, NJ, United States of America 44 Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung, Plasmaphysik, 52425 Jülich, Germany 45 Université Cote d’Azur, CNRS, Inria, LJAD, Parc Valrose, 06108 Nice Cedex 02, France 46 Ruder Boskovic Institute, Bijenicka 54, 10000 Zagreb, Croatia 47 The National Institute for Optoelectronics, Magurele-Bucharest, Romania 48 Mechanics, SCI, KTH SE-100 44 Stockholm, Sweden 49 Fourth State Research, 503 Lockhart Dr, Austin, TX, United States of America 50 University of Texas at Austin, Institute for Fusion Studies, Austin, TX 78712, United States of America 51 Laboratory for Plasma Physics LPP-ERM/KMS, B-1000 Brussels, Belgium 52 University of Tuscia, DEIM, Via del Paradiso 47, 01100 Viterbo, Italy 53 Università di Roma Tor Vergata, Via del Politecnico 1, Roma, Italy 54 Aix-Marseille University, CNRS, PIIM, UMR 7345, 13013 Marseille, France 55 Instituto de Física, Universidade de Sao Paulo, Rua do Mat˜ao Travessa R Nr.187, CEP 05508-090 Cidade Universitária, Sao Paulo, Brasil 56 University of Milano-Bicocca, Piazza della Scienza 3, 20126 Milano, Italy 57 Centre for Fusion, Space and Astrophysics, University of Warwick, Coventry, CV4 7AL, United Kingdom of Great Britain and Northern Ireland 58 Institute of Plasma Physics and Laser Microfusion, Hery 23, 01-497 Warsaw, Poland 59 Aalto University, PO Box 14100, FIN-00076 Aalto, Finland 60 FOM Institute DIFFER, Eindhoven, The Netherlands 61 Warsaw University of Technology, 02-507 Warsaw, Poland 62 Astrophysics Research Centre, School of Mathematics and Physics, Queen’s University, Belfast, BT7 1NN, United Kingdom of Great Britain and Northern Ireland 63 The National Institute for Laser, Plasma and Radiation Physics, Magurele-Bucharest, Romania 64 Department of Applied Physics, Ghent University, 9000 Ghent, Belgium 65 Slovenian Fusion Association (SFA), Jozef Stefan Institute, Jamova 39, SI-1000 Ljubljana, Slovenia 66 The National Institute for Cryogenics and Isotopic Technology, Ramnicu Valcea, Romania 67 Dublin City University (DCU), Dublin, Ireland 68 University of California at San Diego, La Jolla, CA 92093, United States of America 69 EUROfusion Programme Management Unit, Boltzmannstr. 2, 85748 Garching, Germany 70 UNED, Dpto. Informática y Automática, Madrid, Spain 71 National Science Center ‘Kharkov Institute of Physics and Technology’, Akademichna 1, Kharkiv 61108, Ukraine 72 York Plasma Institute, Department of Physics, University of York, York, YO10 5DD, United Kingdom of Great Britain and Northern Ireland 73 Department of Physics, Chalmers University of Technology, SE-41296 Gothenburg, Sweden 74 Department of Space, Earth and Environment, Chalmers University of Technology, SE-41296 Gothenburg, Sweden 75 European Commission, B-1049 Brussels, Belgium 76 University of Tennessee, Knoxville, TN 37996, TN, United States of America 77 Universitat Politècnica de Catalunya, Barcelona, Spain 78 Barcelona Supercomputing Center, Barcelona, Spain 79 Universidad de Sevilla, Sevilla, Spain 80 Aix-Marseille University, CNRS, IUSTI, UMR 7343, 13013 Marseille, France 81 Dipartimento di Ingegneria Astronautica, Elettrica ed Energetica, SAPIENZA Università di Roma, Via Eudossiana 18, 00184 Roma, Italy 82 Institute for Nuclear Research, Prospekt Nauky 47, Kyiv 03680, Ukraine 83 Studiecentrum voor Kernenergie—Centre d’Etude de l’Energie Nucléaire, Boeretang 200, 2400 Mol, Belgium 84 University of Toyama, Toyama, 930-8555, Japan 85 University of California, Irvine, Irvine, California 92697, United States of America 86 Department of Physics, Technical University of Denmark, Bldg 309, DK-2800 Kgs Lyngby, Denmark 87 Institution ‘Project Center ITER’, Moscow, 123182, Russia 88 Faculty of Mathematics, Department of Experimental Physics, Physics and Informatics Comenius University Mlynska dolina F2, 84248 Bratislava, Slovakia 89 University College Cork (UCC), Cork, Ireland 90 Institute of Physics, Opole University, Oleska 48, 45-052 Opole, Poland 91 Daegu University, Jillyang, Gyeongsan, Gyeongbuk 712-174, Republic of Korea 92 Department of Nuclear Engineering, Seoul National University, Seoul, Republic of Korea 93 Fusion for Energy Joint Undertaking, Josep Pl. 2, Torres Diagonal Litoral B3, 08019, Barcelona, Spain 94 PELIN LLC, 27a, Gzhatskaya Ulitsa, Saint Petersburg, 195220, Russia 95 Arizona State University, Tempe, AZ, United States of America 96 Politecnico di Torino, Corso Duca degli Abruzzi 24, I-10129 Torino, Italy 97 ICREA and Barcelona Supercomputing Center, Barcelona, Spain 98 Universidad Complutense de Madrid, Madrid, Spain 99 Istituto dei Sistemi Complessi—CNR and Dipartimento di Energia—Politecnico di Torino, C.so Duca degli Abruzzi 24, 10129 Torino, Italy 100 Eindhoven University of Technology, The Netherlands 101 Purdue University, 610 Purdue Mall, West Lafayette, IN 47907, United States of America 102 Department of Material Science, Shimane University, 1060 Nishikawatsu, Matsue, 690-8504, Japan 103 Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, Brehová 78/7, 115 19 Praha 1, Czech Republic 104 College of William and Mary, Williamsburg, VA 23185, United States of America 105 University of California, 1111 Franklin St., Oakland, CA 94607, United States of America 106 University of Strathclyde, Glasgow, G4 0NG, United Kingdom of Great Britain and Northern Ireland 107 Kindai University, Higashi-Osaka, 577-8502, Japan 108 Shizuoka University, Shizuoka, 422-8529, Japan 109 Rudolf Peierls Centre for Theoretical Physics, University of Oxford, Oxford OX1 3PU, United Kingdom of Great Britain and Northern Ireland 110 Columbia University, New York, NY 10027, United States of America 111 Dipartimento di Fisica ‘G. Galilei’, Universita’ degli Studi di Padova, Padova, Italy 112 Space and Plasma Physics, EECS, KTH SE-100 44 Stockholm, Sweden 113 University of Ioannina, Panepistimioupoli Ioanninon, PO Box 1186, 45110 Ioannina, Greece 114 Universidade do Porto, Faculdade de Engenharia, 4200-465 Porto, Portugal 115 The University of Tokyo, Kashiwa, Chiba, 277-0882, Japan 116 Lithuanian Energy Institute, Breslaujos g. 3, LT-44403, Kaunas, Lithuania 117 HRS Fusion, West Orange, NJ, United States of America 118 Ibaraki University Graduate School of Science and Engineering, Mito, Ibaraki 310-8512, Japan 119 Technische Universität Wien, Fusion@ÖAW Österreichische Akademie der Wissenschaften (ÖAW), Austria

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164. Driven reconnection about a magnetic X point in weakly collisional plasmas

Author

Francesco Porcelli, G. L. Delzanno, and E. Fable

Subjects
Physics, Coupling (physics), Condensed matter physics, Field (physics), Magnetic reconnection, Plasma, Electron, Condensed Matter Physics, Plasma oscillation, Current density, Magnetic field
Abstract

The effect of the Hall term in the process of forced magnetic reconnection for an X point magnetic field configuration, both in the collisionless limit and in the case of weak resistive dissipation, is investigated in this paper. In the case of no guide field, a two-fluid (four fields) linearized model is derived and solved as a forced initial-value problem, resulting in an unexpected insensitivity of the reconnective rates (either asymptotic or peaked) upon the ion skin depth di which characterizes the Hall term. This result is obtained by imposing the axial current density and magnetic field perturbations to vanish at the boundary of the system. In the collisionless limit, the influence of the Hall term resides in the spatial configuration of the fields, which presents an interesting phase-mixing dynamics with three nested layers of width of the order of de2/di, de, and di, with de being the electron skin depth. The first scale length arises due to the coupling between axial and perpendicular motion and...

165. Gyrokinetic calculations of steady-state particle transport in electron internal transport barriers

Author

Olivier Sauter, C. Angioni, and E. Fable

Subjects
Physics, Shear (sheet metal), Steady state, Nuclear Energy and Engineering, Density gradient, Physics::Plasma Physics, Turbulence, Impurity, Pinch, Electron, Atomic physics, Condensed Matter Physics, Linear stability
Abstract

The appearance of an internal particle transport barrier, correlated with a heat transport barrier, during strongly electron heated discharges in reversed magnetic shear scenario is well-established experimental evidence. Turbulent transport is believed to be responsible for the observed inward pinch. The mechanisms for the sustainment of such peaked density profiles in the absence of core particle sources are analysed in the framework of collisionless linear gyrokinetic turbulence theory. In particular, it is elucidated how the thermodiffusive pinch can become the dominant contribution to the total inward pinch. In stationary conditions, the pinch is shown to be carried mostly by trapped electrons, while passing electrons give a smaller contribution. The pinch is maximized when two different microinstabilities, namely the ion temperature gradient mode and the trapped electron mode are believed to coexist at similar linear growth rates. To reach this state at high values of the normalized density gradient, it is necessary to reduce the trapped electron mode activity via different stabilizing mechanisms. The role of impurities is also briefly discussed. A comprehensive analytical–numerical study of the linear stability properties of the modes allows the understanding of the physical mechanism in detail and the clarification of the possible drive of the observed pinch.

166. Non-adiabatic passing electron response and outward impurity convection in gyrokinetic calculations of impurity transport in ASDEX upgrade plasmas

Author

A. G. Peeters, R. Dux, E. Fable, C. Angioni, and ASDEX Upgrade Team

Subjects
Convection, Physics, Simulations, Tokamak, Field line, Equilibrium, Plasma, Electron, Condensed Matter Physics, Heat, law.invention, Turbulence, Nuclear Energy and Engineering, ASDEX Upgrade, law, Impurity, Physics::Plasma Physics, Pinch, Density Peaking, Atomic physics, Stability, Confinement
Abstract

Gyrokinetic calculations with the GS2 code of impurity transport in ASDEX Upgrade H-mode plasmas are presented. A method to separate the diagonal and off-diagonal terms in the quasi-linear flux computed by the gyrokinetic code for a trace impurity is introduced and applied. It is shown that in the experimental conditions of strong central electron cyclotron heating, unstable modes rotating in the electron diamagnetic direction are excited in the central region of the plasma. These are generated by the non-adiabatic response of passing electrons and feature extremely elongated eigenfunctions along the field line. The related fluctuations in the electrostatic potential generate an outward convection of the impurities. These theoretical findings are in agreement with the outward convection of laser ablated Si measured in these experimental conditions. In contrast, in the outer region of the plasma, as well as everywhere in the case of discharges without central electron heating, ion temperature gradient modes produce an impurity pinch directed inwards, which is also in agreement with the experimental observations.

167. Non-Linear Gyrokinetic Simulations of Microturbulence in TCV Electron Internal Transport Barriers

Author

Frank Jenko, E. Fable, Tobias Görler, F. Merz, Stephan Brunner, Olivier Sauter, Laurent Villard, and X. Lapillonne

Subjects
Physics, Tokamak, Plasma, Electron, Condensed Matter Physics, 01 natural sciences, Spectral line, 010305 fluids & plasmas, Computational physics, law.invention, Shear (sheet metal), Wavelength, Nuclear Energy and Engineering, Heat flux, law, Physics::Plasma Physics, 0103 physical sciences, Microturbulence, Atomic physics, 010306 general physics
Abstract

Using the local (flux-tube) version of the Eulerian code GENE (Jenko et al 2000 Phys. Plasmas 7 1904), gyrokinetic simulations of microturbulence were carried out considering parameters relevant to electron-internal transport barriers (e-ITBs) in the TCV tokamak (Sauter et al 2005 Phys. Rev. Lett. 94 105002), generated under conditions of low or negative shear. For typical density and temperature gradients measured in such barriers, the corresponding simulated fluctuation spectra appears to simultaneously contain longer wavelength trapped electron modes (TEMs, for typically k⊥ρi < 0.5, k⊥ being the characteristic perpendicular wavenumber and ρi the ion Larmor radius) and shorter wavelength ion temperature gradient modes (ITG, k⊥ρi > 0.5). The contributions to the electron particle flux from these two types of modes are, respectively, outward/inward and may cancel each other for experimentally realistic gradients. This mechanism may partly explain the feasibility of e-ITBs. The non-linear simulation results confirm the predictions of a previously developed quasi-linear model (Fable et al 2010 Plasma Phys. Control. Fusion 52 015007), namely that the stationary condition of zero particle flux is obtained through the competitive contributions of ITG and TEM. A quantitative comparison of the electron heat flux with experimental estimates is presented as well.

168. The role of ion and electron electrostatic turbulence in characterizing stationary particle transport in the core of tokamak plasmas

Author

Olivier Sauter, E. Fable, and C. Angioni

Subjects
Convection, Physics, Density gradient, K-epsilon turbulence model, Turbulence, Electron, Condensed Matter Physics, Instability, Ion, Computational physics, Physics::Fluid Dynamics, Nuclear Energy and Engineering, particle transport, Diffusion (business), Atomic physics, Fusion, theory
Abstract

A general feature of particle transport in the core of tokamak plasmas is that when core particle sources are small, a stationary peaked density profile is provided by a balance of outward diffusion and inward convection, driven by either neoclassical or turbulent mechanisms. The turbulent contribution to the off-diagonal elements of the transport matrix is very sensitive to the type of dominant instability of the background turbulence. We present here a detailed quasi-linear gyrokinetic analysis of stationary turbulent particle transport by means of analytical and numerical calculations to show how the actual parametric dependence of the stationary normalized density gradient can strongly vary between an ion temperature gradient (ITG) dominated turbulence and a trapped electron mode dominated turbulence regime. It is also shown how the maximal achievable normalized density gradient is reached when the turbulence regime is in a mixed state. This result is interpreted as the interplay of different physical mechanisms arising from (linear) wave–particle resonances. The results presented here are addressed to interpret some of the still unresolved issues in interpreting known experimental results.

169. Integrated simulations of H-mode operation in ITER including core fuelling, divertor detachment and ELM control.

Author

A.r. Polevoi, A. Loarte, R. Dux, T. Eich, E. Fable, D. Coster, S. Maruyama, S.yu. Medvedev, F. Köchl, and V.e. Zhogolev

Subjects
TUNGSTEN, PLASMA devices, PEDESTALS, DIVERTERS (Electronics), FLUX (Energy)
Abstract

ELM mitigation to avoid melting of the tungsten (W) divertor is one of the main factors affecting plasma fuelling and detachment control at full current for high Q operation in ITER. Here we derive the ITER operational space, where ELM mitigation to avoid melting of the W divertor monoblocks top surface is not required and appropriate control of W sources and radiation in the main plasma can be ensured through ELM control by pellet pacing. We apply the experimental scaling that relates the maximum ELM energy density deposited at the divertor with the pedestal parameters and this eliminates the uncertainty related with the ELM wetted area for energy deposition at the divertor and enables the definition of the ITER operating space through global plasma parameters. Our evaluation is thus based on this empirical scaling for ELM power loads together with the scaling for the pedestal pressure limit based on predictions from stability codes. In particular, our analysis has revealed that for the pedestal pressure predicted by the EPED1  +  SOLPS scaling, ELM mitigation to avoid melting of the W divertor monoblocks top surface may not be required for 2.65 T H-modes with normalized pedestal densities (to the Greenwald limit) larger than 0.5 to a level of current of 6.5–7.5 MA, which depends on assumptions on the divertor power flux during ELMs and between ELMs that expand the range of experimental uncertainties. The pellet and gas fuelling requirements compatible with control of plasma detachment, core plasma tungsten accumulation and H-mode operation (including post-ELM W transient radiation) have been assessed by 1.5D transport simulations for a range of assumptions regarding W re-deposition at the divertor including the most conservative assumption of zero prompt re-deposition. With such conservative assumptions, the post-ELM W transient radiation imposes a very stringent limit on ELM energy losses and the associated minimum required ELM frequency. Depending on W transport assumptions during the ELM, a maximum ELM frequency is also identified above which core tungsten accumulation takes place. [ABSTRACT FROM AUTHOR]

Published
2018
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170. Global gyrokinetic simulations of intrinsic rotation in ASDEX Upgrade Ohmic L-mode plasmas.

Author

W.a. Hornsby, C. Angioni, Z.x. Lu, E. Fable, I. Erofeev, R. Mcdermott, A. Medvedeva, A. Lebschy, A.g. Peeters, and Team, The Asdex Upgrade

Subjects
TURBULENCE, PLASMA devices, RESIDUAL stresses, FLUX (Energy), TOKAMAKS, KINETIC energy
Abstract

Non-linear, radially global, turbulence simulations of ASDEX Upgrade (AUG) plasmas are performed and the nonlinear generated intrinsic flow shows agreement with the intrinsic flow gradients measured in the core of Ohmic L-mode plasmas at nominal parameters. Simulations utilising the kinetic electron model show hollow intrinsic flow profiles as seen in a predominant number of experiments performed at similar plasma parameters. In addition, significantly larger flow gradients are seen than in a previous flux-tube analysis (Hornsby et al 2017 Nucl. Fusion57 046008). Adiabatic electron model simulations can show a flow profile with opposing sign in the gradient with respect to a kinetic electron simulation, implying a reversal in the sign of the residual stress due to kinetic electrons. The shaping of the intrinsic flow is strongly determined by the density gradient profile. The sensitivity of the residual stress to variations in density profile curvature is calculated and seen to be significantly stronger than to neoclassical flows (Hornsby et al 2017 Nucl. Fusion57 046008). This variation is strong enough on its own to explain the large variations in the intrinsic flow gradients seen in some AUG experiments. Analysis of the symmetry breaking properties of the turbulence shows that profile shearing is the dominant mechanism in producing a finite parallel wave-number, with turbulence gradient effects contributing a smaller portion of the parallel wave-vector. [ABSTRACT FROM AUTHOR]

Published
2018
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171. Ion heat transport dynamics during edge localized mode cycles at ASDEX Upgrade.

Author

E. Viezzer, M. Cavedon, E. Fable, F.m. Laggner, R.m. Mcdermott, J. Galdon-Quiroga, M.g. Dunne, A. Kappatou, C. Angioni, P. Cano-Megias, D.j. Cruz-Zabala, R. Dux, T. Pütterich, F. Ryter, E. Wolfrum, Team, The Asdex Upgrade, and Team, The Eurofusion Mst1

Subjects
HEAT transfer, FUSION reactor divertors, HYDROGEN plasmas, IONS, DEUTERIUM plasma
Abstract

The edge ion heat transport is analyzed in ASDEX Upgrade (AUG) by combining a comprehensive set of pedestal measurements with both interpretive and predictive modelling. The experimentally determined ion heat diffusivities, , are compared with neoclassical theory and the impact of edge localized modes (ELMs) on the edge ion heat transport level is studied in detail. Pedestal matching experiments in deuterium and hydrogen plasmas show that the inter-ELM pedestal remains close to the neoclassical value. The additional power needed in hydrogen to get similar pedestal temperatures as in deuterium plasmas mostly affects the electron heat channel, i.e. the electron heat diffusivity increases while the ion heat diffusivity stays at the same level within the uncertainties. Sub-ms measurements of the edge ion temperature allows us to extend the analysis to the entire ELM cycle. During the ELM crash, the ion heat transport is increased by an order of magnitude. The perturbed heat flux increases first at the separatrix, i.e. first the separatrix ion temperature increases, leading to a flatter ion temperature gradient, followed by a decrease of the whole pedestal profile. The ion heat transport returns to its pre-ELM neoclassical level 3–4 ms after the ELM crash. [ABSTRACT FROM AUTHOR]

Published
2018
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172. Impact of an integrated core/SOL description on the R and B T optimization of tokamak fusion reactors.

Author

M. Siccinio, E. Fable, C. Angioni, S. Saarelma, A. Scarabosio, and H. Zohm

Subjects
*MATHEMATICAL optimization, *TOKAMAKS, *FUSION reactors, *MAGNETIC fields, *PLASMA confinement
Abstract

An updated and improved version of the 0D divertor and scrape-off layer (SOL) model published in Siccinio et al (2016 Plasma Phys. Control. Fusion58 125011) was coupled with the 1.5D transport code ASTRA (Pereverzev 1991 IPP Report 5/42, Pereverzev and Yushmanov 2002 IPP Report 5/98 and Fable et al 2013 Plasma Phys. Control. Fusion55 124028). The resulting numerical tool was employed for various scans in the major radius R and in the toroidal magnetic field BT—for different safety factors q, allowable loop voltages Vloop and H factors—in order to identify the most convenient choices for an electricity producing tokamak. Such a scenario analysis was carried out evaluating self-consistently, and simultaneously, the core profile and transport effects, which significantly impact on the fusion power outcome, and the divertor heat loads, which represent one of the most critical issues in view of the realization of fusion power plants (Zohm et al 2013 Nucl. Fusion53 073019 and Wenninger et al 2017 Nucl. Fusion57 046002). The main result is that, when divertor limits are enforced, the curves at constant electrical power output are closed on themselves in the plane, and a maximum achievable power exists—i.e. no benefits would be obtained from a further increase in R and BT once the optimum is reached. This result appears as an intrinsic physical limit for all those devices where a radiative SOL is needed to deal with the power exhaust, and where a lower limit on the power crossing the separatrix (e.g. because of the L–H transition) is present. [ABSTRACT FROM AUTHOR]

Published
2018
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173. Theory-based modeling of LOC–SOC transitions in ASDEX Upgrade.

Author

I. Erofeev, E. Fable, C. Angioni, R.M. McDermott, and Team, The ASDEX Upgrade

Subjects
*FUSION reactor divertors, *PLASMA confinement, *PLASMA flow, *ELECTRON temperature, *ELECTRON density, *EQUIPARTITION theorem
Abstract

Modeling of the linear-to-saturated ohmic confinement transitions is performed on the ohmic discharges database collected at ASDEX Upgrade. Ion and electron temperatures and densities are predicted using the TGLF turbulence transport model. Self-consistent classical energy equipartition is retained, as well as the impact of low-Z impurities, the core concentration of which is largest at the lowest plasma densities and decreases with increasing electron density. The simulation results are then compared to the experimentally estimated confinement time behavior, and locally to the energy diffusivities behavior across the density ramps. Both density and plasma current are scanned. The key result, which somewhat confirms previous studies, is that the ion energy transport channel is dominated by the ITG instability, which becomes stronger at higher densities due to the reduction in impurity content (as such, reduction in dilution), as well as a moderate increase in ion temperature normalized gradient. A direct impact of the transition between electron modes (TEM) and ITG on the LOC–SOC is not observed. However, this is necessary to explain the behavior of the density profile. The linear phase of the confinement is simply attributed to the decrease of electron heat transport as the electron and ion temperatures become more coupled. [ABSTRACT FROM AUTHOR]

Published
2017
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174. Non-inductive improved H-mode operation at ASDEX Upgrade.

Author

A. Bock, E. Fable, R. Fischer, M. Reich, D. Rittich, J. Stober, M. Bernert, A. Burckhart, H. Doerk, M. Dunne, B. Geiger, L. Giannone, V. Igochine, A. Kappatou, R. McDermott, A. Mlynek, T. Odstrčil, G. Tardini, H. Zohm, and Team, The ASDEX Upgrade

Subjects
*FUSION reactor divertors, *PLASMA confinement, *TOKAMAKS, *PLASMA currents, *ION temperature, *ELECTROMAGNETISM
Abstract

Recent improvements to the heating and diagnostic systems on the ASDEX Upgrade tokamak allow renewed investigations into non-inductive operation scenarios with improved confinement in a full-metal device. Motivated by this, a scenario with , and a high non-inductive current fraction has been developed. The scenario offers good confinement with and normalised ion temperature gradients . Moreover, it is robust against resistive magnetohydrodynamic (MHD) instabilities, but does suffer from ideal MHD instability when . To verify the understanding of the plasma transport processes, the heat transport was modelled using TGLF. This revealed that electromagnetic effects at high β and/or from fast ions appear to be missing from TGLF’s physics model. As accurate reconstruction of the plasma equilibrium is crucial for studies of advanced scenarios, this publication also documents the presence of polarised background light that can contaminate motional stark effect measurements and thus interfere with equilibrium reconstruction. [ABSTRACT FROM AUTHOR]

Published
2017
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175. Validation of the Fenix ASDEX Upgrade flight simulator

Author

F. Janky, E. Fable, M. Englberger, W. Treutterer, and ASDEX Upgrade Team, Max Planck Institute for Plasma Physics, Max Planck Society

Subjects
Physics, Tokamak, Mechanical Engineering, Nuclear engineering, Cyclotron, ASTRA, 01 natural sciences, 7. Clean energy, Flight simulator, Neutral beam injection, 010305 fluids & plasmas, law.invention, Nuclear Energy and Engineering, ASDEX Upgrade, law, Control system, 0103 physical sciences, General Materials Science, 010306 general physics, MATLAB, computer, Civil and Structural Engineering, computer.programming_language
Abstract

Fenix [1] , [2] is the ASDEX Upgrade (AUG) flight simulator based on the 1-D transport code ASTRA coupled with the 2-D equilibrium solver [ 3 ] SPIDER and Simulink (simulation platform integrated with MATLAB). Fenix is designed to simulate the entire discharge from the ramp up of the poloidal field (PF) coils, through the plasma phase, finishing with the ramp down of the PF coils. Currently, controllers for position, shape, fuelling and heating are implemented according to the AUG control system setup. Also, a model of the poloidal field coils and the models of their corresponding power supplies are provided, as well as basic models of heating actuators such as electron cyclotron resonant heating (ECRH), neutral beam injection (NBI) and fuelling using either pellets or gas. As a next step, the Fenix simulations have to be validated against an already existing database of the discharges. This article compares the behaviour of Fenix simulations against various AUG AUGAUGAUG discharge measurements. It shows that it succeeds in its goal as a comprehensive tokamak discharge simulator.

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176. Deep neural networks for plasma tomography with applications to JET and COMPASS

Author

J. Denis, M. Tardocchi, Kiptily, M. Koubiti, M. Ghate, R. Michling, G. De Masi, T. Tala, M. Bassan, R. McAdams, S. Dowson, Antoine Merle, Seppo Koivuranta, O. J. Kwon, S. Mahesan, P. Sparapani, A. Malaquias, M. Tsalas, Gennady V. Miloshevsky, M. Vecsei, Michal Stano, E. Lerche, Štefan Matejčík, Piergiorgio Sonato, S. D. Pinches, A. Dal Molin, O. McCormack, B. Colling, F. Mink, Ph. Mertens, P. Drewelow, Nuno Cruz, D. Iglesias, Alessandro Zocco, K. Rathod, S. Collins, F. Koechl, James Buchanan, Andrew West, Francesco Maviglia, E. Stefanikova, David Taylor, B. Graham, T. Lunt, S. Meshchaninov, Arturo Buscarino, G. L. Ravera, Maide Bucolo, J. P. Thomas, S. Foley, B. Wakeling, N. Ashikawa, D. W. Robson, N. J. Conway, V. P. Lo Schiavo, Stefan Buller, Sergey Popovichev, M. Saleem, Jorge Luis Rodriguez, M. Wheatley, Gabriele Croci, Hugo Bufferand, J.F. Artaud, R. C. Felton, O. Kovanda, D. Hepple, K. Dylst, Gabor Szepesi, M. Oberkofler, G.J. van Rooij, N. Teplova, Istvan Cziegler, K. K. Kirov, S. Vartanian, Y. Xue, D. Nina, J. Bernardo, Lorenzo Figini, Guglielmo Rubinacci, Peter Lang, R. Scannell, N. C. Hawkes, P. Denner, Istvan Pusztai, D. D. Carvalho, Salvatore Ventre, A. Lescinskis, Afanasev, C. Hamlyn-Harris, Panagiotis Tolias, R. Vale, T. O'Gorman, S. Lesnoj, I.E. Day, Karol Malinowski, D. Carralero, N. Balshaw, Massimo Angelone, Michaele Freisinger, I. Monakhov, Jesús Vega, Jonathan Citrin, Antti Hakola, H. Patten, P. A. Simmons, Y. Austin, Sehyun Kwak, J. Regana, Rohde, T. Eich, A. Alkseev, R. Lawless, C. G. Elsmore, Fusco, S. Hacquin, S. A. Silburn, A. Fernades, Luigi Fortuna, P. Bunting, R. Sartori, Yuji Hatano, D. Borodin, L. Colas, Daniele Marocco, M. Lennholm, Carlo Sozzi, J. J. Rasmussen, P. McCullen, Tommy Ahlgren, A. Kirschner, Thomas Johnson, M. Rack, Göran Ericsson, Hans Nordman, Jakub Bielecki, P. Merriman, M. Cavedon, G. Hermon, Geert Verdoolaege, K. J. Gibson, Daisuke Nishijima, R. Clarkson, Fuchs, M. Tomes, R. Zagórski, Gerald Pintsuk, W. Higginson, Daniel F. Valcarcel, R. Mooney, K. Dawson, A. Tallargio, T.H. Osborne, P. J. Carvalho, M. Gethins, R. Dux, Pierre Dumortier, G. Urbanczyk, Inessa Bolshakova, R. King, B. Tal, Daniel Tegnered, J. W. Coenen, Leena Aho-Mantila, Eva Belonohy, S. Schmuck, Kai Nordlund, Grégoire Hornung, G. Tvalashvili, M. De Bock, Y. Baranov, G. De Tommasi, A. Urban, L. Forsythe, I. Zychor, J. Dobrashian, E. Clark, Paolo Arena, Alessia Santucci, Ivan Lupelli, S. Nowak, M. Curuia, Jonathan Graves, J. C. Hillesheim, Claudio Verona, Zoita, S. Moon, C. Castaldo, A.V. Stephen, Karl Schmid, A. Sahlberg, C. Di Troia, R. Woodley, L. Garzotti, D. Sandiford, Matthew M. Knight, Juho Leppänen, S. Emery, O. G. Pompilian, M. Goniche, C. Luna, M. Mayer, M. Baruzzo, A. Weckmann, M. Kempenaars, S. Hazel, Fabio Pisano, Claudia Corradino, A. G. Meigs, P. Leichauer, S. Potzel, Stéphane Devaux, C. Piron, G. Saibene, David A Rasmussen, Bruce Lipschultz, A. Di Siena, E. Lazzaro, J. Deane, C. Meadowcroft, C. J. Rapson, K.-D. Zastrow, Ph. Duckworth, Tom Wauters, F. Nabais, T. Goerler, D. Brunetti, R. Ellis, David Moulton, L. Jones, E. Delabie, Anna Salmi, Luciano Bertalot, G. Burroughes, B. Kos, Laurent Marot, Daniel Primetzhofer, I Miron, N. Lam, F. Napoli, S. Rowe, E. Pajuste, Choong-Seock Chang, R.P. Doerner, D. Silvagni, C. Guillemaut, S. Warder, A.J. Thornton, Matthew Carr, A. Dempsey, Jorge Morales, Pramit Dutta, J. L. Herfindal, S. Maruyama, P. Camp, X. Lefebvre, Ye. O. Kazakov, Andrea G. Chiariello, Gabriele Manduchi, Andre Neto, T. Powell, J. Griffiths, José Vicente, C. Barcellona, J. Hobirk, F. Clairet, L. Xiang, Dirk Reiser, H. Bergsåker, I. Duran, G. Giacometti, M. Kalsey, David Tskhakaya, A. Martin de Aguilera, T. Dittmar, Edmund Highcock, I. Uytdenhouwen, S. Soare, Giuseppe Prestopino, L. Chôné, W. Davis, G. De Temmerman, Basiuk, G. Learoyd, C. Guerard, A. Klix, M. Incelli, B. Viola, R. J. Robins, A. Burckhart, W. Leysen, Jochen Linke, M. Oberparleiter, A. Murari, M. Sertoli, S. D. Scott, A. Lazaros, R. Dejarnac, P. Buratti, H.R. Strauss, G. T. A. Huijsmans, Hajime Urano, Justine M. Kent, A. Kallenbach, D. Fagan, D. S. Darrow, Benedikt Geiger, A. Wynn, X. Sáez, B. Beckett, Horacio Fernandes, G. Ferro, B. Alper, George Wilkie, A. Uccello, T.C. Luce, S. Zoletnik, Petrzilka, Fulvio Auriemma, D. Guard, A. Ho, R. Henriques, I. T. Chapman, D. Butcher, Ph. Maquet, C. Crapper, S. Murphy, C. Ham, D. Brennan, S. Knott, Krasilnikov, D. Kogut, Cédric Pardanaud, K. Galazka, Nicolò Marconato, Daniele Bonfiglio, M. Sos, E. Militello-Asp, Nesenevich, Sean Conroy, S. Hall, L. F. Ruchko, L. Laguardia, O. Marchuk, F.P. Orsitto, I. S. Nedzelskiy, Eva Macusova, E. Andersson Sundén, C. Ayres, R. Prakash, C. Giroud, M. Parsons, R. Rodionov, M. Marin, A. P. Vadgama, A. Reed, Jacob Eriksson, P. Macheta, R. Neu, J. Orszagh, L. Gil, Riccardo Maggiora, M. Peterka, P. Devynck, M. Price, J. Likonen, Andrew M. Edwards, P. Dalgliesh, I. Vinyar, Andrea Malizia, A. Brett, Jane Johnston, A. Kappatou, P. Blatchford, B. Lloyd, P. Vincenzi, A. Mauriya, A. Garcia-Carrasco, Z. Stancar, D. B. Gin, Gediminas Stankunas, J. Edwards, Giuseppe Ambrosino, A. Goodyear, M. Lungaroni, M. Gardener, R.A. Pitts, Svetlana V. Ratynskaia, E. Ivings, Marek Rubel, L. Calacci, Ivo S. Carvalho, M. Afzal, M. Gherendi, D. Schworer, C. Watts, A. M. Messiaen, E. Safi, P. David, A. Petre, J. Uljanovs, U. von Toussaint, H. Greuner, D. Del Sarto, A.C.A. Figueiredo, D. Gallart, R. Bilato, M. Enachescu, P. Monaghan, M. S. J. Rainford, A. Boboc, M. Reinhart, Hiroyasu Utoh, B. P. Duval, L. Hackett, M. Halitovs, G. De Dominici, B. Lomanowski, P. Cahyna, Aslanyan, T. May-Smith, M. Richiusa, A. Goussarov, M. Okabayashi, R. Howell, T. Tadic, M. E. Manso, J. F. Rivero-Rodriguez, Wayne Arter, Ivan Calvo, U. Losada, H. Weisen, A. Teplukhina, Marica Rebai, R. Andrews, C. H. A. Hogben, M. Klas, A. E. Shevelev, J. McKehon, F. Reimold, Enrico Zilli, R. Maingi, M.F. Stamp, A. Rakha, H. T. Kim, D. Ciric, Eric Nardon, A. Somers, I. Igaune, E. Laszynska, S. Saarelma, A. Cullen, Mǎdǎlina Vlad, D. Nodwell, S. Griph, T. Donne, T. Boyce, M. Tyshchenko, Paulo Carvalho, Elena Bruno, Ion E. Stamatelatos, A. Patel, E. de la Luna, F. Causa, Robin Barnsley, Michael Lehnen, F. Belli, N. Jones, B. Bauvir, M. Tokitani, I. Turner, Y. Zhou, J. Simpson, A. Vitins, D. Rendell, Alberto Milocco, Benjamin P. Brown, F.G. Rimini, C. Lamb, V. Thompson, E. Alessi, S. Arshad, J. Rzadkiewicz, P. Prior, J. Moran, S. D. A. Reyes Cortes, Igor Bykov, M. Weiszflog, Annette M. Hynes, Gennady Sergienko, J. Lönnroth, T. C. Hender, M.-L. Mayoral, Mattia Frasca, R. Coelho, J-J Honore, A. Jackson, A. Sirinelli, M. D. Axton, Hyun-Tae Kim, F. P. Keenan, H. J. Boyer, Elisabeth Rachlew, T. Szabolics, J. Ongena, Braic, Sandra C. Chapman, Anders Nielsen, John E. Marsh, J. Jansons, S. Gloeggler, Nengchao Wang, Naulin, M. Porton, D. Falie, P. Welch, G. T. Jones, N. Fil, M. Vincent, U. Kruezi, R. Pereira, L. Horvath, M. F. F. Nave, Lorella Carraro, N. Fonnesu, Davide Flammini, P. V. Edappala, G. M. D. Hogeweij, K. Krieger, P. Card, G. Poulipoulis, W. Studholme, Didier Mazon, T. Odupitan, D. Young, F. J. Casson, N. Muthusonai, I. Jepu, Olivier Sauter, Dimitri Voltolina, Sara Carcangiu, C. Reux, Irena Ivanova-Stanik, D. Tskhakaya Jun, O. Bogar, E. Viezzer, Shane Cooper, Fabio Villone, Florin Spineanu, H. Doerk, E. Cecil, J. Goff, F. Nespoli, F. Schluck, G. Ciraolo, Jennifer M. Lehmann, Jan Mlynar, H. J. C. Oliver, M. Marinucci, N. Krawczyk, J. Buch, M. Dreval, G. Possnert, C. Angioni, C. P. Lungu, Marco Ariola, S. Breton, Christopher N. Bowman, A. Kundu, J. Mailloux, I. Stepanov, D. Sprada, J. Zacks, G. Ramogida, E. Wolfrum, N.W. Eidietis, A. Pires dos Reis, Barbara Cannas, Robert E. Grove, A. Huber, Giuliana Sias, A. Baron Wiechec, Markus Airila, M. Berry, P. Huynh, R. Kovaldins, R. Bastow, Darren Price, S. Abduallev, P. Tsavalas, N. Aiba, Plyusnin, Ion Tiseanu, James Williams, M. Beckers, M. Weiland, S.N. Gerasimov, Alessandra Fanni, L. D. Horton, T. Xu, L. Joita, N. Reid, D. Zarzoso Fernandez, D. I. Refy, Jerry Hughes, Clarisse Bourdelle, J. E. Boom, G. Hancu, K. M. Aggarwal, F. Crisanti, M. Poradziński, A. Loarte, P. Vallejos Olivares, T. Mrowetz, Teddy Craciunescu, R. Guirlet, M. Valentinuzzi, J. Stephens, J. Stober, Michael Barnes, Isabel L. Nunes, Mario Pillon, P. Batistoni, G. Verona Rinati, Fabio Moro, R. Lucock, R. Olney, Jari Varje, B. Butler, A. Mariani, M. Hamed, Skvara, C. Terry, Larisa Baumane, T. Alarcon, Mike Kotschenreuther, T. M. Biewer, O. Hemming, N. Marcenko, Z. Kollo, B. Slade, J. Garcia, T. R. Blackman, Simone Peruzzo, N. den Harder, S. Ng, P. Siren, K. G. McClements, Rita Lorenzini, Y. Yakovenko, Lorenzo Frassinetti, J. Hawes, A. Kirk, C. Noble, Nicola Bonanomi, Y. Martynova, A.E. Shumack, F. Di Maio, H. R. Koslowski, N. Pomaro, G. Nemtsev, M. I. K. Santala, Richard George, E. Giovannozzi, T. Giegerich, C. Woodley, G. Pucella, D. Hopley, P.J. Knight, Michela Gelfusa, Francesca Poli, G. Petravich, G. Kocsis, S. Lanthaler, J. A. Wilson, D. Coombs, F. Köchl, G. Stables, Silvia Spagnolo, D. Rigamonti, W. Van Renterghem, Mike Dunne, H. Betar, W. Pires de Sa, Stjepko Fazinić, M. Nocente, G. Birkenmeier, L. Avotina, A. Horton, P. Heesterman, Larry R. Baylor, C. Stavrou, L. Appel, Amosov, J. Fessey, J. Flanagan, C. Paz Soldan, G. Kaveney, R. Young, Shimpei Futatani, U. Samm, R. Naish, P. Strand, E. Lascas Neto, S. Wheeler, Daisuke Shiraki, S. P. Hotchin, D. M. Witts, A. Cobalt, C. Waldon, Davide Galassi, I. Jenkins, S. Panja, C. Gurl, A. Lukin, R. Albanese, Andrea Pavone, A. Davies, J. Hawkins, N. Vianello, C. Besiliu, F. Domptail, Bruno Santos, Y. Li, T. Kaltiaisenaho, O. N. Kent, X. Litaudon, B. Lescinskis, M. Faitsch, Otto Asunta, F. Eriksson, Pericoli, M. Beldishevski, G.A. Rattá, C. D. Challis, Z. Ghani, M. Juvonen, A. C. C. Sips, João M. C. Sousa, Boris Breizman, P. Finburg, Henrik Sjöstrand, Slawomir Jednorog, Ewa Kowalska-Strzęciwilk, A. Martin, R. O. Dendy, B. Lepiavko, D. Croft, Goloborod'ko, A. V. Krasilnikov, M. Wischmeier, K. Gal, R. Ragona, Petter Ström, N. Parsons, G. Calabrò, Jean-Stéphane Joly, A. Capat, Linwei Li, T. Nakano, Paulo Rodrigues, L. Moser, João P. S. Bizarro, L. Piron, K. Pepperell, P. Aleynikov, Ambrogio Fasoli, S.-P. Pehkonen, Giuseppe Gorini, C. Taliercio, M. E. Puiatti, J. Svensson, H. R. Wilson, John Wright, S. Wiesen, O. Asztalos, R.V. Budny, A. Withycombe, P. Piovesan, Jonathan Gaspar, B. D. Stevens, P. Trimble, Vinodh Bandaru, F. S. Zaitsev, H. Sheikh, G. F. Matthews, Daniele Carnevale, K. Schoepf, L. McNamee, A. Czarnecka, P. Blanchard, Erik Fransson, J.P. Coad, Daniel Dunai, Carolina Björkas, A. Manzanares, M. Reich, A. Lahtinen, L. Giacomelli, Mirko Salewski, E. de la Cal, T. D. V. Haupt, T.T.C. Jones, M. Anghel, Kyriakos Hizanidis, J. M. Fontdecaba, Huber, A. Shaw, A. Cufar, A. Muraro, M. Clark, A. Meakins, Roland Sabot, A. Owen, K. Valerii, A. L. Esquisabel, Petr Vondracek, Maria Teresa Porfiri, Walid Helou, S. E. Sharapov, D. Terranova, M. Skiba, Konstantina Mergia, Frank Leipold, Francisco L. Tabarés, M. Zerbini, Ken W Bell, Marco Marinelli, Marco Riva, R. Martone, Bobkov, B. Magesh, A. Ash, Parail, M. Hook, Amanda Hubbard, Silvio Ceccuzzi, Ulrich Fischer, G. Liu, Nick Walkden, R. Otin, P. Santa, P. Abreu, Demerdzhiev, Roberto Zanino, T. Spelzini, António J.N. Batista, P. G. Smith, L. Meneses, S. S. Medley, M. J. Mantsinen, K. Vasava, G. Gervasini, Surya K. Pathak, Kristel Crombé, G. Ellwood, P. Raj, Robert Hager, Ch. Linsmeier, C. Stokes, Petra Bilkova, M. Groth, G. Pautasso, C. R. Nobs, S. Sridhar, P. Chmielewski, David Hatch, Luca Boncagni, I. Balboa, C. Stan-Sion, Nobuyuki Asakura, R. McKean, L. Pigatto, João Figueiredo, Roberto Cavazzana, Juri Romazanov, M. Beurskens, C. Christopher Klepper, Maryna Chernyshova, O. Biletskyi, D. Karkinsky, A. Eksaeva, S. Dalley, Pasquale Gaudio, J. Benayas, J. Dankowski, S. Korolczuk, R. Buckingham, F. Parra Diaz, E. Wang, A. Cardinali, J. Naish, R. O. Pavlichenko, Kalle Heinola, Hiroshi Tojo, Miles M. Turner, Brett Chapman, A. Lyssoivan, F. Militello, E. Matveeva, T. Kobuchi, I. Ksiazek, P. Bohm, Cody Jones, W. Yanling, T. Jackson, P. Gohil, D. Alegre, Tim D. Bohm, F. Jaulmes, L. Zakharov, Peter J. Pool, C.G. Lowry, M. Passeri, D. Testa, Igor Lengar, A. Formisano, C. M. Roach, A. Hjalmarsson, A. Drenik, S. Meiter, William Tang, Carlos B. da Silva, Diogo R. Ferreira, P. J. Lomas, M. McHardy, Gunta Kizane, Angela Busse, S. Jachmich, Corneliu Porosnicu, Stanislas Pamela, Yavorskij, Eduardo Alves, Saskia Mordijck, Boniface Nkonga, J. Morris, Dean A. J. Whittaker, S. Ertmer, A. Hollingsworth, T. Barnard, R. Tatali, S. Reynolds, S. Mistry, Sergio Galeani, Torbjörn Hellsten, V.S. Neverov, David Dickinson, T. M. Huddleston, D. Baiao, F. Salzedas, D. Willoughby, M. Tripsky, Emmanuele Peluso, J. R. Harrison, C. Mazzotta, R. Zarins, M. Maslov, X. Bonnin, T. E. Gebhart, S. Fietz, K. Flinders, C. Hidalgo, Yann Corre, Aqsa Shabbir, A. B. Kukushkin, A. Shepherd, M.L. Walker, R. Clay, T. Vasilopoulou, Paolo Innocente, I. H. Coffey, P. Lalousis, Italo Predebon, R. Bravanec, P. Papp, D. Sytnykov, Ewa Pawelec, M. Bernert, G. Corrigan, Lutsenko, M. Romanelli, Gergely Papp, S. Romanelli, R. Salmon, J. Risner, M. T. Ogawa, A. M. Whitehead, E. Fable, H. Dabirikhah, Juan Manuel López, M. Turnyanskiy, A. Baciero, S. Meigh, M. Garcia-Munoz, Massimiliano Mattei, J.-M. Noterdaeme, N. Hamilton, S. Minucci, I Wilson, A. Muir, A. V. Chankin, C. Clements, Matthias Hoelzl, Francesco Romanelli, S. Gee, R. J. E. Smith, P. de Vries, L. Fittill, S. Menmuir, K. Cave-Ayland, P. Curson, Richard Fridström, D. Grist, S. A. Robinson, Rodney Walker, Michael Loughlin, S. Aleiferis, W. Broeckx, Clayton E. Myers, S. F. Smith, D. Harting, W. Zwingmann, F. Binda, Mark R. Gilbert, Rajnikant Makwana, Richard Goulding, D. Van Eester, I. Voitsekhovitch, M. Bowden, I. Kodeli, Tomasz Czarski, Peter Hawkins, S. S. Henderson, M. Koeppen, D. Ricci, Ondrej Ficker, Carl Hellesen, D. Yadikin, Fabio Subba, Luka Snoj, Anthony Laing, E. R. Solano, M. Stephen, P. Staniec, C. Appelbee, M. Newman, Susan Leerink, M. Nicassio, P. P. Pereira Puglia, M. Brombin, Wouter Tierens, C. Perez von Thun, Cédric Boulbe, Ya. I. Kolesnichenko, Taina Kurki-Suonio, S. Hallworth-Cook, R. P. Johnson, B. B. Carvalho, Anna Widdowson, Alessandro Pau, R. Price, B. Gonçalves, D. L. Keeling, Kazantzidis, Michael Fitzgerald, M. Hughes, K. D. Lawson, M. Brix, Raffaele Fresa, Juha Karhunen, S. Esquembri, K. Purahoo, Matthew Reinke, Gerd Meisl, M. Valovic, J. Horacek, D. King, H. Maier, Philipps, Kenji Tanaka, M. Kresina, M. Valisa, L. Omoregie, Gábor Cseh, Seppo Sipilä, Scott W. Mosher, Filippo Sartori, J. Kaniewski, Jan Weiland, Giuseppe Chitarin, Coccorese, A. R. Field, P. Beaumont, Robert Skilton, D. C. Campling, Mitul Abhangi, S. Villari, Roberta Lima Gomes, G. D. Ewart, S. Wray, A. Broslawski, A. Sinha, Roberto Paccagnella, S. Hollis, R. D. Wood, Albert Gutierrez-Milla, E. Jonasson, L.-G. Eriksson, R. Leach, L. W. Packer, M. Vuksic, H. J. Sun, C. Marchetto, Giuseppe Telesca, Dieter Leichtle, S. Cramp, Blaise Faugeras, M. Allinson, Yannis Kominis, R. Normanton, H. J. Leggate, Francesco Ghezzi, T. Schlummer, Tommaso Bolzonella, Jorge Ferreira, M. J. Walsh, C. Day, Philipp Drews, Steven J. Meitner, M. D. J. Bright, Per Petersson, D. L. Hillis, M. Webb, P. Wright, C. F. Maggi, B. Sieglin, A. Farahani, J. Strachan, M. Muraglia, M. Cecconello, F. Durodié, D. Callaghan, J. Waterhouse, R. J. Dumont, Sara Moradi, Patrick J. McCarthy, S. Feng, M. Balden, M. Kaufman, R. Warren, Brian Grierson, Harry M. Meyer, S.C. Bradnam, D. Kinna, A. Krivska, M. Lungu, E. Suchkov, A. Kantor, D. Conka, C. Penot, A. Zarins, Pierre Manas, D. F. Gear, J. Callaghan, L. Barrera Orte, Tomas Markovic, Yu Gao, A. Lunniss, Z. Vizvary, E. Khilkevich, Th. Puetterich, Dmitry Matveev, E. Perelli Cippo, T. Owen, N. Imazawa, A. Silva, H. P. Summers, Norberto Catarino, Roberto Pasqualotto, P. Muscat, K. Keogh, Ricardo Magnus Osorio Galvao, P. Carman, M. Leyland, E. Veshchev, A. de Castro, M. Gruca, D. C. McDonald, L. Moreira, J. W. Banks, Sanjeev Ranjan, N. Sutton, Iris D. Young, Martin Imrisek, W. Zhang, J. K. Blackburn, Moiseenko, A. Parsloe, T. Loarer, D. N. Borba, S.J. Wukitch, D. P. Coster, J. Penzo, Jose Ramon Martin-Solis, P. Mantica, N. Bekris, M. G. O'Mullane, S. E. Dorling, Yunfeng Liang, S. Gulati, Roberto Ambrosino, J. Schweinzer, Cocilovo, D. Douai, M. A. Henderson, T. Suzuki, Gianluca Rubino, A. Peackoc, Yann Camenen, Y. Miyoshi, Ph. Jacquet, H. T. Lambertz, E. Tholerus, C. Sommariva, Prajapati, Yannick Marandet, F. Hasenbeck, Faa Federico Felici, M. Buckley, Kenneth Hammond, Daniele Milanesio, Cristian Ruset, Katsumichi Hoshino, D. Frigione, D. Chandra, I. Borodkina, P. Dinca, S. Brezinsek, J. Stallard, H. G. Esser, Matthew Sibbald, S. Knipe, Jorge Estrela da Silva, Kensaku Kamiya, P. A. Coates, J. C. Giacalone, Alfredo Pironti, Carvalho, D. D., Ferreira, D. R., Carvalho, P. J., Imrisek, M., Mlynar, J., Fernandes, H., and Formisano, A.

Subjects
Computer science, Feature extraction, Image processing, Computerized Tomography (CT) and Computed Radiography (CR), Plasma diagnostics - interferometry, spectroscopy and imaging, 01 natural sciences, Convolutional neural network, 030218 nuclear medicine & medical imaging, 03 medical and health sciences, 0302 clinical medicine, Compass, Plasma diagnostics-interferometry, spectroscopy and imaging, 0103 physical sciences, Computer vision, Instrumentation, Mathematical Physics, Jet (fluid), Contextual image classification, 010308 nuclear & particles physics, business.industry, Cognitive neuroscience of visual object recognition, Plasma diagnostics - interferometry spectroscopy and imaging, Tomography, Artificial intelligence, business, plasma diagnostics - interferometry, spectroscopy and imaging
Abstract

Convolutional neural networks (CNNs) have found applications in many image processing tasks, such as feature extraction, image classification, and object recognition. It has also been shown that the inverse of CNNs, so- called deconvolutional neural networks, can be used for inverse problems such as plasma tomography. In essence, plasma tomography consists in reconstructing the 2D plasma profile on a poloidal cross-section of a fusion device, based on line-integrated measurements from multiple radiation detectors. Since the reconstruction process is computationally intensive, a deconvolutional neural network trained to produce the same results will yield a significant computational speedup, at the expense of a small error which can be assessed using different metrics. In this work, we discuss the design principles behind such networks, including the use of multiple layers, how they can be stacked, and how their dimensions can be tuned according to the number of detectors and the desired tomographic resolution for a given fusion device. We describe the application of such networks at JET and COMPASS, where at JET we use the bolometer system, and at COMPASS we use the soft X-ray diagnostic based on photodiode arrays.

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177. DEMO divertor limitations during and in between ELMs

Author

G. Strohmayer, M. Wischmeier, A. Loarte, A. Kallenbach, Ronald Wenninger, D. C. McDonald, R. Neu, B. Sieglin, T. Eich, P. A. Schneider, Th. Pütterich, G. Federici, M. Bernert, C.G. Lowry, E. Fable, and F. Reimold

Subjects
Physics, Nuclear and High Energy Physics, Energy loss, Divertor, Nuclear engineering, Condensed Matter Physics, 7. Clean energy, Energy density, Maximum size, Boundary value problem, Atomic physics, Overheating (electricity), Order of magnitude, Power density
Abstract

Operation of DEMO in comparison to ITER will be significantly more demanding, as various additional limitations of physical and technical nature have to be respected. In particular a set of extremely restrictive boundary conditions on divertor operation during and in between ELMs will have to be respected. It is of high importance to describe these limitations in order to consider them as early as possible in the ongoing development of the DEMO concept design. This paper extrapolates the existing physics basis on power and particle exhaust to DEMO.In phases between ELMs or with mitigated ELMs surface overheating and W sputtering pose challenging boundary conditions. For attached divertor conditions at 90% total radiation fraction a peak power density of about 15 MW m−2 convected or radiated to the outer divertor is estimated. As this clearly exceeds the tolerable limit, some degree of divertor detachment is regarded as essential for the operation of DEMO. A loss of detachment with a peak power density of more than 30 MW m−2 cannot be tolerated for more than a second before the divertor would suffer from a destructive event. The combination of the limitations on the peak power flux density and W sputtering rate necessitates divertor temperatures less than 4 eV.For uncontrolled ELMs sizes in the order of 100 MJ are estimated. Results on ELM broadening from JET suggest that in DEMO an energy density limit of 0.5 MJ m−2 per ELM is exceeded by a factor of about 8 for a large range of relative ELM sizes. This highlights the necessity of a reactor-relevant ELM control technique for DEMO, which is capable of reducing the maximum size of the energy loss per ELM to the divertor by more than an order of magnitude without a strong reduction of confinement.

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178. Investigation of inter-ELM ion heat transport in the H-mode pedestal of ASDEX Upgrade plasmas

Author

M. Bernert, Th. Pütterich, M. Willensdorfer, F. Ryter, E. Fable, R. M. McDermott, M. Cavedon, R. Dux, Florian Laggner, C. Angioni, E. Viezzer, A. Burckhart, E. Wolfrum, Viezzer, E, Fable, E, Cavedon, M, Angioni, C, Dux, R, Laggner, F, Bernert, M, Burckhart, A, Mcdermott, R, Putterich, T, Ryter, F, Willensdorfer, M, Wolfrum, E, Universidad de Sevilla. Departamento de Física Atómica, Molecular y Nuclear, European Commission (EC), European Union (UE), ASDEX Upgrade Team, Max Planck Institute for Plasma Physics, Max Planck Society, and EUROfusion MST1 Team

Subjects
Nuclear and High Energy Physics, Tokamak, Materials science, Transport, 01 natural sciences, 7. Clean energy, Electron cyclotron resonance, 010305 fluids & plasmas, Ion, law.invention, Pedestal, ASDEX Upgrade, Physics::Plasma Physics, law, 0103 physical sciences, Neoclassical theory, 010306 general physics, tokamak, Toroid, Plasma, Condensed Matter Physics, neoclassical theory, transport, Electron temperature, Magnetic confinement and equilibrium, Atomic physics, magnetic confinement and equilibrium, Tokamaks
Abstract

The ion heat transport in the pedestal of H-mode plasmas is investigated in various H-mode discharges with different pedestal ion collisionalities. Interpretive modelling suggests that in all analyzed discharges the ion heat diffusivity coefficient, χ i , in the pedestal is close to the neoclassical prediction within the experimental uncertainties. The impact of changing the deposition location of the electron cyclotron resonance heating on the ion heat transport has been studied. The effect on the background profiles is small. The pre-ELM (edge localized modes) edge profiles as well as the behaviour of the electron temperature and density, ion temperature and impurity toroidal rotation during the ELM cycle are very similar in discharges with on- and off-axis ECRH heating. No significant deviation of χ i from neoclassics is observed when changing the ECRH deposition location to the plasma edge.

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179. Impact of plasma thermal transients on the design of the EU DEMO first wall protection

Author

F. Palermo, M. Firdaouss, C. Vorpahl, Thomas Franke, V. P. Loschiavo, Fabio Villone, M. L. Richiusa, J. Gerardin, Roberto Ambrosino, Christian Bachmann, E. Fable, Z. Vizvary, Gianfranco Federici, Francesco Maviglia, Raffaele Albanese, Massimiliano Mattei, Mattia Siccinio, Maviglia, F., Bachmann, C., Federici, G., Franke, T., Siccinio, M., Vorpahl, C., Albanese, R., Ambrosino, R., Fable, E., Firdaouss, M., Gerardin, J., Loschiavo, V. P., Mattei, M., Palermo, F., Richiusa, M. L., Villone, F., and Vizvary, Z.

Subjects
Materials science, Steady state (electronics), Nuclear engineering, Discrete limiter, Plasma transients, 01 natural sciences, 010305 fluids & plasmas, Electromagnetic simulation, 0103 physical sciences, Thermal, Limit (music), Limiter, Water cooling, General Materials Science, 010306 general physics, First wall load, DEMO, Civil and Structural Engineering, Mechanical Engineering, Plasma, Discrete limiters, Nuclear Energy and Engineering, 13. Climate action, Thermal radiation, Electromagnetic simulations, Transient (oscillation), Plasma scenario optimization
Abstract

The protection of the EU-DEMO first wall (FW) during plasma transients represents one of the main challenges of the current pre-concept design phase. While the present DEMO FW design heat load capability is of the order of ≈1−2 MW/m2 in steady state, this limit is overcome during plasma transients for both normal and off-normal events leading to a plasma-wall contact. A strategy to protect the FW is being developed, considering the inclusion of discrete limiters, designed also to maintain the integrity of their cooling system during transients. The present investigations include electromagnetic modelling and plasma simulations on a list of critical transient events. The plasma equilibria are designed to ensure that the plasma impact, in case of loss of plasma control, is located, when possible, close to maintenance ports, to allow for replacement of the limiters. Charged particles and radiation heat load calculations are performed to evaluate the surface design and the required number of limiters. Finally, simplified thermal analyses are run to verify the integrity of the limiter plasma-facing components, and propose their design.

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180. Turbulence in high-beta ASDEX upgrade advanced scenarios

Author

A. Di Siena, Frank Jenko, Tobias Görler, H. Doerk, J. Stober, E. Fable, A. Bock, and ASDEX Upgrade Team, Max Planck Institute for Plasma Physics, Max Planck Society

Subjects
Physics, Nuclear and High Energy Physics, Safety factor, Turbulence, Cyclotron, Mechanics, Plasma, Condensed Matter Physics, 01 natural sciences, 7. Clean energy, 010305 fluids & plasmas, law.invention, ASDEX Upgrade, Heat flux, Physics::Plasma Physics, law, Beta (plasma physics), 0103 physical sciences, 010306 general physics, Beam (structure)
Abstract

Recent experiments at ASDEX Upgrade achieve non-inductive operation in full tungsten wall conditions by applying electron cyclotron and neutral beam current drive. These discharges are characterised by a well-measured safety factor profile, which does not drop below one, and a good energy confinement. By reproducing the experimental heat fluxes, nonlinear gyrokinetic simulations suggest that the observed strong peaking of the ion temperature in the core is caused by the stabilising impact of a significant beam ion content, as well as strong electromagnetic effects on turbulent transport. Quasilinear transport models are not yet applicable in this interesting and reactor relevant parameter regime, but available simulation data may serve as a testbed for improvements. As the present plasma is close to the kinetic ballooning (KBM) threshold, elevating the safety factor profile under otherwise identical conditions is proposed to clarify, whether profiles are ultimately limited by KBM turbulence, or by global stability constraints.

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181. A stepladder approach to a tokamak fusion power plant

Author

Frederik Träuble, E. Fable, H. Lux, Mattia Siccinio, Wolfgang Biel, R. Kemp, Ronald Wenninger, and H. Zohm

Subjects
Nuclear and High Energy Physics, Operating point, Tokamak, Steady state, Ideal (set theory), Power station, Computer science, Nuclear engineering, Condensed Matter Physics, ASTRA, 01 natural sciences, 7. Clean energy, Stability (probability), 010305 fluids & plasmas, law.invention, law, 0103 physical sciences, Path (graph theory), ddc:620, 010306 general physics
Abstract

We present an approach to design in a consistent way a stepladder connecting ITER, DEMO and an FPP, starting from an attractive FPP and then locating DEMO such that main similarity parameters for the core scenario are constant. The approach presented suggests how to use ITER such that DEMO can be extrapolated with maximum confidence and a development path for plasma scenarios in ITER follows from our approach, moving from low β N and q typical for the present Q = 10 scenario to higher values needed for steady state. A numerical example is given, indicative of the feasibility of the approach, and it is backed up by more detailed 1.5-D calculation using the ASTRA code. We note that ideal MHD stability analysis of the DEMO operating point indicates that it is located between the no-wall and the ideal wall β-limit, which may require active stabilization. The DEMO design could also be a pulsed fallback solution should a stationary operation turn out to be impossible.

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182. Modelling of pulsed and steady-state DEMO scenarios

Author

J.F. Artaud, D.J. Ward, W. Stepniewski, Irena Ivanova-Stanik, Tommaso Bolzonella, M. Schneider, R. Zagórski, L. Garzotti, P. Vincenzi, D. B. King, G. Giruzzi, R. Kemp, M. Baruzzo, R. Stankiewicz, and E. Fable

Subjects
Nuclear and High Energy Physics, Tokamak, Steady state, Computer science, Nuclear engineering, Monte Carlo method, Fusion power, Condensed Matter Physics, 7. Clean energy, 01 natural sciences, 010305 fluids & plasmas, law.invention, law, DEMO, fusion reactor, plasma scenario, 0103 physical sciences, Ion distribution, Sensitivity (control systems), 010306 general physics
Abstract

Scenario modelling for the demonstration fusion reactor (DEMO) has been carried out using a variety of simulation codes. Two DEMO concepts have been analysed: a pulsed tokamak, characterized by rather conventional physics and technology assumptions (DEMO1) and a steady-state tokamak, with moderately advanced physics and technology assumptions (DEMO2). Sensitivity to impurity concentrations, radiation, and heat transport models has been investigated. For DEMO2, the impact of current driven non-inductively by neutral beams has been studied by full Monte Carlo simulations of the fast ion distribution. The results obtained are a part of a more extensive research and development (R&D) effort carried out in the EU in order to develop a viable option for a DEMO reactor, to be adopted after ITER for fusion energy research.

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183. Scaling laws from theory-based modeling for different regimes in the DEMO fusion reactor

Author

E. Fable, F. Palermo, H. Zohm, C. Angioni, and Mattia Siccinio

Subjects
Physics, Nuclear and High Energy Physics, Scaling law, Tokamak, Nuclear engineering, Iter tokamak, Magnetic confinement fusion, Thermal power station, Fusion power, Condensed Matter Physics, 01 natural sciences, 010305 fluids & plasmas, law.invention, Theory based, law, 0103 physical sciences, 010306 general physics, Dimensionless quantity
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184. A stepladder approach to a tokamak fusion power plant.

Author

H. Zohm, F. Träuble, W. Biel, E. Fable, R. Kemp, H. Lux, M. Siccinio, and R. Wenninger

Subjects
TOKAMAKS, POWER plants, EXTRAPOLATION, COMPUTER simulation, FEASIBILITY studies
Abstract

We present an approach to design in a consistent way a stepladder connecting ITER, DEMO and an FPP, starting from an attractive FPP and then locating DEMO such that main similarity parameters for the core scenario are constant. The approach presented suggests how to use ITER such that DEMO can be extrapolated with maximum confidence and a development path for plasma scenarios in ITER follows from our approach, moving from low βN and q typical for the present Q  =  10 scenario to higher values needed for steady state. A numerical example is given, indicative of the feasibility of the approach, and it is backed up by more detailed 1.5-D calculation using the ASTRA code. We note that ideal MHD stability analysis of the DEMO operating point indicates that it is located between the no-wall and the ideal wall β-limit, which may require active stabilization. The DEMO design could also be a pulsed fallback solution should a stationary operation turn out to be impossible. [ABSTRACT FROM AUTHOR]

Published
2017
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185. On the effect of neoclassical flows on intrinsic momentum in ASDEX Upgrade Ohmic L-mode plasmas.

Author

W.A. Hornsby, C. Angioni, E. Fable, P. Manas, R. McDermott, A.G. Peeters, M. Barnes, F. Parra, and Team, The ASDEX Upgrade

Subjects
TOKAMAKS, TRANSPORT theory, TURBULENCE, MAGNETIC flux, PLASMA dynamics
Abstract

A gyro-kinetic analysis of intrinsic rotation is presented for the ASDEX Upgrade tokamak. The gyro-kinetic turbulence code, GKW and the neoclassical transport code, NEO are coupled so that the neoclassical equilibrium distribution function is included in the background distribution function in the gyro-kinetic turbulence simulation. This implementation is benchmarked against a similar implementation in the gyro-kinetic code, GS2 (Dorland et al 2000 Phys. Rev. Lett. 85 5579) and against analytical predictions. A quasi-linear and non-linear gyro-kinetic turbulence analysis is performed on Ohmic L-mode ASDEX Upgrade plasmas showing that the symmetry breaking effects due to neoclassical background flows can produce significant toroidal momentum transport. While its magnitude is of the order of other symmetry breaking mechanisms, such as the Coriolis pinch, up–down asymmetry in the magnetic flux surfaces and flow shear, the flow gradients it can sustain are appreciably smaller than the maximum gradients measured at the mid-radius of the ASDEX Upgrade tokamak core, which can be up to an order of magnitude larger. It is found that the gradient of the diamagnetic flow, and therefore the second derivatives of the density and temperature gradients are critical to the production of residual toroidal momentum flux. A quasi-linear estimate indicated that the second derivatives required to match the experimental flow gradient are up to an order of magnitude higher than the measured second derivatives. This analysis suggests that turbulent transport driven by neoclassical flows is not sufficient to explain the maximum flow gradients observed in ASDEX Upgrade. [ABSTRACT FROM AUTHOR]

Published
2017
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186. Experimental observations and modelling of intrinsic rotation reversals in tokamaks.

Author

Y Camenen, C Angioni, A Bortolon, B P Duval, E Fable, W A Hornsby, R M McDermott, D H Na, Y-S Na, A G Peeters, and J E Rice

Subjects
TOKAMAKS, PHYSICS experiments, TURBULENT flow, MOMENTUM transfer, TOROIDAL harmonics
Abstract

The progress made in understanding spontaneous toroidal rotation reversals in tokamaks is reviewed and current ideas to solve this ten-year-old puzzle are explored. The paper includes a summarial synthesis of the experimental observations in AUG, C-Mod, KSTAR, MAST and TCV tokamaks, reasons why turbulent momentum transport is thought to be responsible for the reversals, a review of the theory of turbulent momentum transport and suggestions for future investigations. [ABSTRACT FROM AUTHOR]

Published
2017
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187. Selected transport studies of a tokamak-based DEMO fusion reactor.

Author

E. Fable, R. Wenninger, and R. Kemp

Subjects
*TOKAMAKS, *FUSION reactors, *ELECTRICITY, *PLASMA density, *FUEL cycle
Abstract

As a next-step in the tokamak-based fusion programme, the DEMO fusion reactor is foreseen to produce relevant output electricity, in the order of  ∼500 MW delivered to the network. The scenarios that are being presently investigated consist of a pulsed device, called DEMO1, and a steady-state device, called DEMO2. In this work, which is focused on the pulsed device DEMO1, scenarios are studied from the point of view of core transport, to assess plasma performance and limitations due to core microinstabilities. The role of radiated power, aspect ratio, and height of temperature pedestal are assessed as they impact both core energy and particle transport. Open issues in this framework are also discussed. [ABSTRACT FROM AUTHOR]

Published
2017
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188. Investigation of inter-ELM ion heat transport in the H-mode pedestal of ASDEX Upgrade plasmas.

Author

E. Viezzer, E. Fable, M. Cavedon, C. Angioni, R. Dux, F.M. Laggner, M. Bernert, A. Burckhart, R.M. McDermott, T. Pütterich, F. Ryter, M. Willensdorfer, E. Wolfrum, Team, the ASDEX Upgrade, and Team, the EUROfusion MST1

Subjects
*HEAT transfer, *H-mode plasma confinement, *FUSION reactor divertors, *THERMAL diffusivity, *CYCLOTRON resonance
Abstract

The ion heat transport in the pedestal of H-mode plasmas is investigated in various H-mode discharges with different pedestal ion collisionalities. Interpretive modelling suggests that in all analyzed discharges the ion heat diffusivity coefficient, , in the pedestal is close to the neoclassical prediction within the experimental uncertainties. The impact of changing the deposition location of the electron cyclotron resonance heating on the ion heat transport has been studied. The effect on the background profiles is small. The pre-ELM (edge localized modes) edge profiles as well as the behaviour of the electron temperature and density, ion temperature and impurity toroidal rotation during the ELM cycle are very similar in discharges with on- and off-axis ECRH heating. No significant deviation of from neoclassics is observed when changing the ECRH deposition location to the plasma edge. [ABSTRACT FROM AUTHOR]

Published
2017
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189. Gyrokinetic study of turbulent convection of heavy impurities in tokamak plasmas at comparable ion and electron heat fluxes.

Author

C. Angioni, R. Bilato, F.J. Casson, E. Fable, P. Mantica, T. Odstrcil, M. Valisa, Team, ASDEX Upgrade, and Contributors, JET

Subjects
TURBULENCE, CONVECTIVE flow, TOKAMAKS, HEAT flux
Abstract

In tokamaks, the role of turbulent transport of heavy impurities, relative to that of neoclassical transport, increases with increasing size of the plasma, as clarified by means of general scalings, which use the ITER standard scenario parameters as reference, and by actual results from a selection of discharges from ASDEX Upgrade and JET. This motivates the theoretical investigation of the properties of the turbulent convection of heavy impurities by nonlinear gyrokinetic simulations in the experimentally relevant conditions of comparable ion and electron heat fluxes. These conditions also correspond to an intermediate regime between dominant ion temperature gradient turbulence and trapped electron mode turbulence. At moderate plasma toroidal rotation, the turbulent convection of heavy impurities, computed with nonlinear gyrokinetic simulations, is found to be directed outward, in contrast to that obtained by quasi-linear calculations based on the most unstable linear mode, which is directed inward. In this mixed turbulence regime, with comparable electron and ion heat fluxes, the nonlinear results of the impurity transport can be explained by the coexistence of both ion temperature gradient and trapped electron modes in the turbulent state, both contributing to the turbulent convection and diffusion of the impurity. The impact of toroidal rotation on the turbulent convection is also clarified. [ABSTRACT FROM AUTHOR]

Published
2017
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190. The physics and technology basis entering European system code studies for DEMO.

Author

R. Wenninger, R. Kembleton, C. Bachmann, W. Biel, T. Bolzonella, S. Ciattaglia, F. Cismondi, M. Coleman, A.J.H. Donné, T. Eich, E. Fable, G. Federici, T. Franke, H. Lux, F. Maviglia, B. Meszaros, T. Pütterich, S. Saarelma, A. Snickers, and F. Villone

Subjects
NUCLEAR fusion, POWER plants, NUCLEAR reactions, ELECTRIC power
Abstract

A large scale program to develop a conceptual design for a demonstration fusion power plant (DEMO) has been initiated in Europe. Central elements are the baseline design points, which are developed by system codes. The assessment of the credibility of these design points is often hampered by missing information. The main physics and technology content of the central European system codes have been published (Kovari et al 2014 Fusion Eng. Des. 89 3054–69, 2016 Fusion Eng. Des. 104 9–20, Reux et al 2015 Nucl. Fusion55 073011). In addition, this publication discusses key input parameters for the pulsed and conservative design option and provides justifications for the parameter choices. In this context several DEMO physics gaps are identified, which need to be addressed in the future to reduce the uncertainty in predicting the performance of the device. Also the sensitivities of net electric power and pulse duration to variations of the input parameters are investigated. The most extreme sensitivity is found for the elongation ( corresponds to ). [ABSTRACT FROM AUTHOR]

Published
2017
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191. Impact of lithium pellets on plasma performance in the ASDEX Upgrade all-metal-wall tokamak.

Author

P.T. Lang, R. Maingi, D.K. Mansfield, R.M. McDermott, R. Neu, E. Wolfrum, R. Arredondo Parra, M. Bernert, G. Birkenmeier, A. Diallo, M. Dunne, E. Fable, R. Fischer, B. Geiger, A. Hakola, V. Nikolaeva, A. Kappatou, F. Laggner, M. Oberkofler, and B. Ploeckl

Subjects
LITHIUM, PLASMA gases, TOKAMAKS, TUNGSTEN, FUSION reactors
Abstract

The impact of lithium (Li) on plasma performance was investigated at the ASDEX Upgrade tokamak, which features a full tungsten wall. Li pellets containing 1.6  ×  1020 Li atoms were launched with a speed of 600 m s−1 to achieve deep penetration into the plasma and minimize the impact on the first wall. Homogeneous transient Li concentrations in the plasma of up to 15% were established. The Li sustainment time in the plasma decreased with an increasing heating power from 150 to 40 ms. Due to the pellet rate being restricted to 2 Hz, no Li pile-up could take place. No significant positive impact on plasma properties, as reported from other tokamak devices, could be found; the Li pellets rather caused a small reduction in plasma energy, mainly due to enhanced radiation. Due to pellet injection, a short-lived Li layer was formed on the plasma-facing components, which lasted a few discharges and led to moderately beneficial effects during plasma start-up. Most pellets were found to trigger type-I ELMs, either by their direct local perturbation or indirectly by the altered edge conditions; however, reliability was less than 100%. [ABSTRACT FROM AUTHOR]

Published
2017
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192. Disruption mitigation by injection of small quantities of noble gas in ASDEX Upgrade.

Author

G Pautasso, M Bernert, M Dibon, B Duval, R Dux, E Fable, J C Fuchs, G D Conway, L Giannone, A Gude, A Herrmann, M Hoelzl, P J McCarthy, A Mlynek, M Maraschek, E Nardon, G Papp, S Potzel, C Rapson, and B Sieglin

Subjects
NOBLE gases, NUCLEAR reactors, THERMAL analysis, PLASMA currents, ENERGY dissipation
Abstract

The most recent experiments of disruption mitigation by massive gas injection in ASDEX Upgrade have concentrated on small—relatively to the past—quantities of noble gas injected, and on the search for the minimum amount of gas necessary for the mitigation of the thermal loads on the divertor and for a significant reduction of the vertical force during the current quench. A scenario for the generation of a long-lived runaway electron beam has been established; this allows the study of runaway current dissipation by moderate quantities of argon injected. This paper presents these recent results and discusses them in the more general context of physical models and extrapolation, and of the open questions, relevant for the realization of the ITER disruption mitigation system. [ABSTRACT FROM AUTHOR]

Published
2017
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193. A 0D stationary model for the evaluation of the degree of detachment on the divertor plates.

Author

M Siccinio, E Fable, K Lackner, A Scarabosio, R P Wenninger, and H Zohm

Subjects
*PLASMA boundary layers, *FUSION reactor divertors, *STRUCTURAL plates, *HEAT convection, *HEAT conduction, *PLASMA physics
Abstract

A 0D analytical stationary model to estimate the degree of detachment on the divertor plates is derived, starting from previous works of Igitkhanov (Igitkhanov et al 1994 21st EPS (Montpellier) ECA v.18B, 1995 22th EPS (Bournemouth) ECA v.19C, Igitkhanov 2014 KIT Sci. Rep. 7661). It accounts for heat convection, conduction, impurity radiation and contains a simplified balance for the neutrals. The upstream particle flux (or, alternatively, the density upstream nup), the heat flux in the scrape-off layer (SOL) qup and the impurity concentrations are required as input, whereas the temperatures at the plate and at the separatrix are not fixed a priori. The routine has been mainly developed for system codes, or more in general for scopy studies in the framework of the preliminary design phase for the reactor DEMO, its simplicity being therefore justified by the purpose of keeping the calculation times as low as possible. A calibration against a more detailed 1D routine (Kallenbach et al 2016 Plasma Phys. Control. Fusion58 045013) has been performed, finding a reasonable agreement. Furthermore, a coupling of the model with the 1.5D transport code ASTRA (Pereverzev 1991 IPP Report 5/42, Fable et al 2013 Plasma Phys. Control. Fusion55 124028) to illustrate its possible usage is also presented. [ABSTRACT FROM AUTHOR]

Published
2016
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194. Radiation and confinement in 0D fusion systems codes.

Author

H Lux, R Kemp, E Fable, and R Wenninger

Subjects
PLASMA impurities, MAGNETIC confinement, TOKAMAKS, FUSION reactors, SCALING laws (Nuclear physics)
Abstract

In systems modelling for fusion power plants, it is essential to robustly predict the performance of a given machine design (including its respective operating scenario). One measure of machine performance is the energy confinement time that is typically predicted from experimentally derived confinement scaling laws (e.g. IPB98(y,2)). However, the conventionally used scaling laws have been derived for ITER which—unlike a fusion power plant—will not have significant radiation inside the separatrix. In the absence of a new high core radiation relevant confinement scaling, we propose an ad hoc correction to the loss power used in the ITER confinement scaling and the calculation of the stored energy by the radiation losses from the ‘core’ of the plasma . Using detailed ASTRA / TGLF simulations, we find that an appropriate definition of is given by 60% of all radiative losses inside a normalised minor radius . We consider this an improvement for current design predictions, but it is far from an ideal solution. We therefore encourage more detailed experimental and theoretical work on this issue. [ABSTRACT FROM AUTHOR]

Published
2016
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195. Transport simulations of the pre–thermal–quench phase in ASDEX Upgrade massive gas injection experiments.

Author

E. Fable, G. Pautasso, R. Dux, M. Bernert, A. Mlynek, Team, the ASDEX Upgrade, and M. Lehnen

Subjects
*GAS injection, *TOKAMAKS, *HIGH temperature plasmas, *PLASMA flow, *CARBON dioxide mitigation
Abstract

The pre–thermal–quench (PTQ) phase of the massive gas injection (MGI) scenario to terminate the tokamak plasma discharge is studied by means of one-dimensional (1D) transport simulations. This phase is characterized by the cold–front penetration in the hot plasma after the gas has been released from the valves, and before the actual thermal quench takes place, with consequent plasma disruption at lower stored energy. The comparison between the simulations and the ASDEX Upgrade (AUG) experiments allows to gain insight in the observed dependencies and time scales. Despite the genuine three-dimensional structure of the problem, it is shown that the 1D simulations are already giving experimentally relevant answers, the reason for which will be discussed in detail. Influence of unknown parameters and simplifying assumptions are also discussed. [ABSTRACT FROM AUTHOR]

Published
2016
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196. Modelling of pulsed and steady-state DEMO scenarios.

Author

G. Giruzzi, J.F. Artaud, M. Baruzzo, T. Bolzonella, E. Fable, L. Garzotti, I. Ivanova-Stanik, R. Kemp, D.B. King, M. Schneider, R. Stankiewicz, W. Stępniewski, P. Vincenzi, D. Ward, and R. Zagórski

Subjects
STEADY-state responses, NUCLEAR fusion, FUSION reactors, MONTE Carlo method, RESEARCH & development
Abstract

Scenario modelling for the demonstration fusion reactor (DEMO) has been carried out using a variety of simulation codes. Two DEMO concepts have been analysed: a pulsed tokamak, characterized by rather conventional physics and technology assumptions (DEMO1) and a steady-state tokamak, with moderately advanced physics and technology assumptions (DEMO2). Sensitivity to impurity concentrations, radiation, and heat transport models has been investigated. For DEMO2, the impact of current driven non-inductively by neutral beams has been studied by full Monte Carlo simulations of the fast ion distribution. The results obtained are a part of a more extensive research and development (R&D) effort carried out in the EU in order to develop a viable option for a DEMO reactor, to be adopted after ITER for fusion energy research. [ABSTRACT FROM AUTHOR]

Published
2015
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197. Understanding of impurity poloidal distribution in the edge pedestal by modelling.

Author

V. Rozhansky, E. Kaveeva, P. Molchanov, I. Veselova, S. Voskoboynikov, D. Coster, E. Fable, T. Puetterich, E. Viezzer, A.S. Kukushkin, A. Kirk, and Team, the ASDEX Upgrade

Subjects
POLOIDAL magnetic fields, IMPURITY centers, NEUTRON density, ION temperature, ELECTRIC fields
Abstract

Simulation of an H-mode ASDEX Upgrade shot with boron impurity was done with the B2SOLPS5.2 transport code. Simulation results were compared with the unique experimental data available for the chosen shot: radial density, electron and ion temperature profiles in the equatorial midplanes, radial electric field profile, radial profiles of the parallel velocity of impurities at the low-field side (LFS) and high-field side (HFS), radial density profiles of impurity ions at LHS and HFS. Simulation results reproduce all available experimental data simultaneously. In particular strong poloidal HFS–LFS asymmetry of B5+ ions was predicted in accordance with the experiment. The simulated HFS B5+ density inside the edge transport barrier is twice larger than that at LFS. This is consistent with the experimental observations where even larger impurity density asymmetry was observed. A similar effect was predicted in the simulation done for the MAST H-mode. Here the HFS density of He2+ is predicted to be 4 times larger than that at LHS. Such a large predicted asymmetry is connected with a larger ratio of HFS and LFS magnetic fields which is typical for spherical tokamaks. The HFS/LFS asymmetry was not measured in the experiment, however modelling qualitatively reproduces the observed change of sign of He+parallel velocity to the counter-current direction at LFS. The understanding of the asymmetry is based on neoclassical effects in plasma with strong gradients. It is demonstrated that simulation results obtained with account of sources of ionization, realistic geometry and turbulent transport are consistent with the simplified analytical approach. Difference from the standard neoclassical theory is emphasized. [ABSTRACT FROM AUTHOR]

Published
2015
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198. Advances in the physics basis for the European DEMO design.

Author

R. Wenninger, F. Arbeiter, J. Aubert, L. Aho-Mantila, R. Albanese, R. Ambrosino, C. Angioni, J.-F. Artaud, M. Bernert, E. Fable, A. Fasoli, G. Federici, J. Garcia, G. Giruzzi, F. Jenko, P. Maget, M. Mattei, F. Maviglia, E. Poli, and G. Ramogida

Subjects
FUSION reactors, MAGNETOHYDRODYNAMICS, PARTICLES (Nuclear physics), PLASMA gases, TRANSPORT theory
Abstract

In the European fusion roadmap, ITER is followed by a demonstration fusion power reactor (DEMO), for which a conceptual design is under development. This paper reports the first results of a coherent effort to develop the relevant physics knowledge for that (DEMO Physics Basis), carried out by European experts. The program currently includes investigations in the areas of scenario modeling, transport, MHD, heating & current drive, fast particles, plasma wall interaction and disruptions. [ABSTRACT FROM AUTHOR]

Published
2015
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199. Integrated core–SOL–divertor modelling for ITER including impurity: effect of tungsten on fusion performance in H-mode and hybrid scenario.

Author

R. Zagórski, I. Voitsekhovitch, I. Ivanova-Stanik, F. Köchl, P. Belo, E. Fable, J. Garcia, L. Garzotti, J. Hobirk, G.M.D. Hogeweij, E. Joffrin, X. Litaudon, A.R. Polevoi, G. Telesca, and contributors, JET

Subjects
PLASMA boundary layers, PLASMA core reactors, FUSION reactor divertors, H-mode plasma confinement, TUNGSTEN isotopes, SELF-consistent field theory, HYBRID reactors
Abstract

The compatibility of two operational constraints—operation above the L–H power threshold and at low power to divertor—is examined for ITER long pulse H-mode and hybrid scenarios in integrated core–scrape off layer (SOL)–divertor modelling including impurities (intrinsic Be, He, W and seeded Ne). The core thermal, particle and momentum transport is simulated with the GLF23 transport model tested in the self-consistent simulations of temperatures, density and toroidal rotation velocity in JET hybrid discharges and extrapolated to ITER. The beneficial effect of toroidal rotation velocity on fusion gain is shown. The sensitivity studies with respect to operational (separatrix and pedestal density, Ne gas puff) and unknown physics (W convective velocity and perpendicular diffusion in SOL as well as W prompt re-deposition) parameters are performed to determine their influence on the operational window and fusion gain. [ABSTRACT FROM AUTHOR]

Published
2015
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200. Overview of recent pedestal studies at ASDEX Upgrade.

Author

E. Wolfrum, E. Viezzer, A. Burckhart, M.G. Dunne, P.A. Schneider, M. Willensdorfer, E. Fable, R. Fischer, D. Hatch, F. Jenko, B. Kurzan, P. Manz, S.K. Rathgeber, and Team, the ASDEX Upgrade

Subjects
PEDESTALS, BALLOONING instability, TEARING instability, MAGNETOHYDRODYNAMICS, PLASMA diagnostics, PLASMA flow
Abstract

New or upgraded diagnostics of the edge transport barrier allow investigations of the dominant transport mechanisms in the pedestal. The density build-up after the L–H transition can be explained with a mainly diffusive edge transport barrier. A small inward convection term improves the agreement between modelling and experiment, but its existence cannot be confirmed due to the uncertainty in the neutral sources. Measurements of the impurity ion flow asymmetry as well as the edge current density are in agreement with neoclassical modelling. The inter-ELM pedestal recovery was traced with ideal peeling–ballooning modelling, which shows that the stability boundary moves closer to the operational point as the pedestal becomes wider. Gyrokinetic modelling of the different phases reveal that density gradient driven trapped electron modes are dominant during the early recovery, while electron temperature gradient modes or kinetic ballooning modes determine the temperature gradient in the final phase. Microtearing modes are modelled and also experimentally determined at the top of the pedestal. Non-linear coupling between modes could explain the failure of ideal linear MHD modelling. [ABSTRACT FROM AUTHOR]

Published
2015
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