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D Moreau,
M L Walker,
J R Ferron,
F Liu,
E Schuster, J F Artaud,
J E Barton,
M D Boyer,
K H Burrell,
S M Flanagan, [......],
R D Johnson,
R J La Haye,
J Lohr,
T C Luce,
R Nouailletas,
J M Park,
B G Penaflor,
W Shi,
F Turco,
W Wehner
[show abstract]
[hide abstract]
ABSTRACT: The first real-time profile control experiments integrating magnetic and kinetic variables were performed on DIII-D in view of regulating and extrapolating advanced tokamak scenarios to steady state devices and burning plasma experiments. Device-specific, control-oriented models were obtained from experimental data and these data-driven models were used to synthesize integrated magnetic and kinetic profile controllers. Closed-loop experiments were performed for the regulation of (a) the poloidal flux profile, Ψ(x), (b) the inverse of the safety factor profile, ι(x)=1/q(x), and (c) either the Ψ(x) profile or the ι(x) profile together with the normalized pressure parameter, β N . The neutral beam injection (NBI), electron cyclotron current drive (ECCD) systems and ohmic coils provided the heating and current drive (H&CD) sources. The first control actuator was the plasma surface loop voltage or current (i. e. the ohmic coil), and the available beamlines and gyrotrons were grouped to form five additional H&CD actuators: co-current on-axis NBI, co-current off-axis NBI, counter-current NBI, balanced NBI and total ECCD power from all gyrotrons (with off-axis current deposition). The control method was also applied on simulated ITER discharges using a simplified transport code (METIS).
24th IAEA Fusion Energy Conference, San Diego (USA); 10/2012
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A. A. Tuccillo,
Y. Baranov,
R. Cesario,
B. J. Ding,
M. Goniche,
G.M. Wallace,
L. Amicucci, J.F. Artaud,
S.G. Baek,
E. Barbato, [......],
K. Kirov,
J. Mailloux,
O. Meneghini,
F.C. Mirizzi,
R. Parker,
V. Pericoli-Ridolfini,
Y. Peysson,
F. Santini,
S. Shiraiwa,
B.N. Wan
[show abstract]
[hide abstract]
ABSTRACT: A multi-machine assessment started at the end of 2009 under the coordination of ITPA-IOS group aiming at understanding the complex physics underlying the phenomena that could prevent penetration of Lower Hybrid (LH) waves in reactor relevant high-density plasma. Results from Alcator C-Mod, FTU, HT-7, JET and Tore Supra are reviewed, together with preliminary indications from EAST. These experiments have relevant plasma and LH parameters that encompass those of ITER. Limiter and divertor operations are included, as well as operation with metallic and carbon walls and with plasma edge conditioned by wall boronisation or lithization. Two independent models based on ray tracing and on full wave, indicate respectively Non Resonant Collisional Absorption (NRCA) and parallel index upshift as possible explanation for the decrease of LH effects at density above ne≥1020m-3 in Alcator C-Mod. New spectral measurements suggest a possible important role of Parametric Instability (PI) in C-Mod. FTU experiments show that LH effects are recovered, at density even higher than that expected in ITER, when edge electron temperature is increased by wall lithization. Accordingly a strong reduction of PI is measured, but concurrent contribution by NRCA and Scattering from Density Fluctuations (SDF) cannot be excluded. A gradual shift to the periphery of LH power deposition is observed in JET with increasing density, till disappearing of LH effects for ne,ped > 3×1019m-3. Preliminary RF probe measurements indicate large LH spectral broadening when increased gas puffing decreases edge temperature. Reduction of LH effects correlates, in Tore Supra, with increasing edge fluctuations. LH experiments on HT-7 did not find any anomalous decrease of current drive at high density, although better performance is observed in lithized discharges. Preliminary results of LH at high density on EAST are reported. Initial results from inter- machines modelling with different code-model are also reported.
24th IAEA Fusion Energy Conference, San Diego, USA; 10/2012
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J Citrin,
J Hobirk,
M Schneider, J F Artaud,
C Bourdelle,
K Crombe,
G M D Hogeweij,
F Imbeaux,
E Joffrin,
F Koechl,
J Stober,
the ASDEX Upgrade team,
JET-EFDA contributors,
the ITM-TF ITER Scenario Modelling group
[show abstract]
[hide abstract]
ABSTRACT: Hybrid scenarios in present machines are often characterized by improved confinement compared with the IPB98(y,2) empirical scaling law expectations. This work concentrates on isolating the impact of increased s/q at outer radii (where s is the magnetic shear) on core confinement in low-triangularity JET and ASDEX Upgrade (AUG) experiments. This is carried out by predictive heat and particle transport modelling using the integrated modelling code CRONOS coupled to the GLF23 turbulent transport model. For both machines, discharge pairs were analysed displaying similar pedestal confinement yet significant differences in core confinement. From these comparisons, it is found that s/q shaping at outer radii may be responsible for up to ~50% of the relative core confinement improvement observed in these specific discharges. This relative improvement is independent of the degree of rotational shear turbulence suppression assumed in the GLF23 model. However, employing the full GLF23 rotational shear model leads to an overprediction of the ion temperatures in all discharges analysed. Additional mechanisms for core confinement improvement are discussed and estimated. Further linear threshold analysis with QuaLiKiz is carried out on both pairs of discharges. This work aims to validate recent predictions of the ITER hybrid scenario also employing CRONOS/GLF23, where a high level of confinement and resultant fusion power sensitivity to the s/q profile was found.
Plasma Physics and Controlled Fusion 05/2012; 54(6):065008. · 2.42 Impact Factor
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[show abstract]
[hide abstract]
ABSTRACT: Measurements of fast electron bremsstrahlung (FEB) using hard X‐ray (HXR) cameras provide a unique diagnostic for the fast electron dynamics, with resolution in space, time and energy. A synthetic HXR diagnostic is developed to calculate the distribution function and FEB emission, such that experimental results can be directly compared with simulations. Using this comparison, the role of fast electron radial transport in radio‐frequency current drive is investigated. For two cases studied in this paper, the HXR emission is consistent with negligible radial transport, although in one case this is in disagreement with the measured driven current.
AIP Conference Proceedings. 12/2011; 1406(1):447-450.
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[show abstract]
[hide abstract]
ABSTRACT: Methods and tools for design and modelling of tokamak operation scenarios are discussed with particular application to ITER advanced scenarios. Simulations of hybrid and steady-state scenarios performed with the integrated tokamak modelling suite of codes CRONOS are presented. The advantages of a possible steady-state scenario based on cyclic operations, alternating phases of positive and negative loop voltage, with no magnetic flux consumption on average, are discussed. For regimes in which current alignment is an issue, a general method for scenario design is presented, based on the characteristics of the poloidal current density profile.
Plasma Physics and Controlled Fusion 11/2011; 53(12):124010. · 2.42 Impact Factor
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J. Garcia,
G. Giruzzi,
X. Litaudon,
J. Mailloux, J.F. Artaud,
V. Basiuk,
J. Decker,
F. Imbeaux,
Y. Peysson,
M. Schneider,
the JET EFDA contributors
[show abstract]
[hide abstract]
ABSTRACT: The impact of the radio-frequency heating and current drive systems on JET advanced scenarios at high density is analysed by means of the CRONOS suite of codes for integrated tokamak modelling. In particular, the performance of the proposed electron cyclotron heating and current drive system for JET is evaluated. As a first step, the code is applied in the interpretative mode to analyse two high power advanced scenario discharges of JET, in order to validate both the heating and current drive computational modules and the overall simulation procedure. Then, JET advanced scenarios are studied by predictive simulations on the basis of previous results. The simulations show that lower hybrid and electron cyclotron heating and current drive systems can together provide off-axis current in order to create and sustain steady-state scenarios on JET at high density. These results give deeper insight into the future advanced scenarios in ITER, since they establish a clear way to test some key aspects of them in present day devices such as JET.
Nuclear Fusion 06/2011; 51(7):073019. · 4.09 Impact Factor
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C. Bourdelle,
T. Gerbaud,
L. Vermare,
A. Casati,
T. Aniel, J.F. Artaud,
V. Basiuk,
J. Bucalossi,
F. Clairet,
Y. Corre, [......],
G.T. Hoang,
F. Imbeaux,
L. Manenc,
P. Monier-Garbet,
P. Moreau,
R. Sabot,
J.-L. Ségui,
A. Sirinelli,
D. Villegas,
the Tore Supra Team
[show abstract]
[hide abstract]
ABSTRACT: A collisionality scaling experiment associating a confinement analysis, turbulence measurements across the whole plasma and gyrokinetic modelling is reported. In Tore Supra L-mode plasmas, mid-radius dimensionless collisionality ν* has been varied performing a four-points scan from 0.1 to 0.7. The normalized confinement time exhibits a dependence with respect to collisionality: BτE ∝ ν*−0.3±0.3 which is strongly modified when accounting for the confinement dependence on the normalized Larmor radius, ρ*, and normalized pressure, β, since one obtains BτE ∝ ν*0.0±0.7. This weak dependence is consistent with ITER L mode scaling laws and dedicated experiments elsewhere (Luce 2008 Plasma Phys. Control. Fusion 50 043001). The global analysis is confirmed by normalized effective heat transport coefficients which do not vary outside their error bars in a limited radial range of reliability. The analysis is completed by density fluctuation δne/ne measurements across the whole plasmas. For normalized radius r/a < 0.7, δne/ne does not depart from its error bars and the radial wave-vector spectra are not modified. These observations are well reproduced by non-linear gyrokinetic simulations, where, despite high ν* values, no zonal flow damping mechanism is at play. At the plasma edge (r/a > 0.7), the lowest poloidal wave-vector measured by the Doppler reflectometer exhibits a decrease in δne/ne with increasing ν*, while the other turbulence measurements remain unaffected.
Nuclear Fusion 05/2011; 51(6):063037. · 4.09 Impact Factor
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[show abstract]
[hide abstract]
ABSTRACT: The NEMO (NEutral beam MOdelling) code for simulating neutral beam ionization during neutral beam injection (NBI) in tokamak plasmas has been developed for implementation in integrated modelling frameworks and is presented. Integrated modelling of fusion plasmas is becoming increasingly important, both for preparation and analysis of experiments in large devices. Moreover, it should play a crucial role for the design of future fusion reactors. In a modern context, integrated modelling requires codes that are (i) flexible in terms of their interfaces, i.e. can be adapted for different simulation environments, (ii) machine independent; i.e. they should not contain hard coded information on a particular device to be simulated; (iii) optimized for speed of execution, (iv) verified and validated. The NEMO code has been specially designed to meet these requirements. The code is based on the physics concept outlined by Feng et al (1995 Comput. Phys. Commun. 88 161–72) and is a completely modular program: it works with any input NBI geometry and can be coupled to any external Fokker–Planck calculation for evaluating the distribution function of the injected species, i.e. it can provide source terms for both Monte Carlo codes and codes using finite difference/elements methods. The NEMO code has already been integrated with the CRONOS integrated modelling suite (Artaud et al 2010 Nucl. Fusion 50 043001) and the European Integrated Tokamak Modelling Task Force (ITM-TF)*. The basics of the code are described in this paper along with an illustration of its integration in the ITM-TF simulation platform. A crucial aspect is the verification of the code, the results of benchmarks carried out with other NBI codes for JET and ITER discharges are thereby presented.
Nuclear Fusion 05/2011; 51(6):063019. · 4.09 Impact Factor
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J. Hillairet,
S. Ceccuzzi,
J. Belo,
L. Marfisi, J.F. Artaud,
Y.S. Bae,
G. Berger-By,
J.M. Bernard,
Ph. Cara,
A. Cardinali, [......],
G. Schettini,
M. Schneider,
P.K. Sharma,
A.A. Tuccillo,
O. Tudisco,
G. Vecchi,
R. Villari,
K. Vulliez,
Y. Wu,
Q. Zeng
[show abstract]
[hide abstract]
ABSTRACT: In the frame of the EFDA task HCD-08-03-01, a 5 GHz Lower Hybrid system which should be able to deliver 20 MW CW on ITER and sustain the expected high heat fluxes has been reviewed. The design and overall dimensions of the key RF elements of the launcher and its subsystem has been updated from the 2001 design in collaboration with ITER organization. Modeling of the LH wave propagation and absorption into the plasma shows that the optimal parallel index must be chosen between 1.9 and 2.0 for the ITER steady-state scenario. The present study has been made with n|| = 2.0 but can be adapted for n|| = 1.9. Individual components have been studied separately giving confidence on the global RF design of the whole antenna.
Fusion Engineering and Design. 03/2011; 86(6-8):823-826.
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F. Mirizzi,
S. Ceccuzzi,
S. Meschino, J.F. Artaud,
J.H. Belo,
G. Berger-By,
J.M. Bernard,
A. Cardinali,
C. Castaldo,
R. Cesario, [......],
Y. Peysson,
P.K. Sharma,
G. Schettini,
M. Schneider,
A.A. Tuccillo,
O. Tudisco,
G. Vecchi,
R. Villari,
K. Vulliez,
Y.S. Bae
[show abstract]
[hide abstract]
ABSTRACT: In the frame of the EFDA Task HCD-08-03-01 (EU contribution to the ITER LHCD Development Plan) the preliminary design of the LHCD system, described in the Detailed Design Description DDD 5.4 LH (2001), has been revised to take into account progresses on technology and on knowledge. In particular a revised layout of the ITER machine and the successful development of a prototype klystron at 5 GHz with a target RF power of 500 kW CW have determined significant changes in the design of the main transmission lines and on the modularity of the launcher.
Fusion Engineering and Design 03/2011; 86(6-8):759-762. · 1.49 Impact Factor
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A. Bécoulet,
G.T. Hoang, J.F. Artaud,
Y.S. Bae,
J. Belo,
G. Berger-By,
J.M. Bernard,
Ph. Cara,
A. Cardinali,
C. Castaldo, [......],
M. Schneider,
P.K. Sharma,
A. Tuccillo,
O. Tudisco,
G. Vecchi,
R. Villari,
K. Vulliez,
Y. Wu,
H.L. Yang,
Q. Zeng
[show abstract]
[hide abstract]
ABSTRACT: Steady-state long pulse operation of tokamaks requires fully non-inductive current drive, thus an external current drive method. Lower Hybrid Current Drive is recognized as one of the most efficient technique used in the present day tokamaks. Progress of the conceptual design of the LHCD ITER relevant system is reported, as well as critical technology issues.
Fusion Engineering and Design. 02/2011; 86(6-8):490-496.
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L. Marfisi,
M. Goniche,
C. Hamlyn-Harris,
J. Hillairet, J.F. Artaud,
Y.S. Bae,
J. Belo,
G. Berger-By,
J.M. Bernard,
Ph. Cara, [......],
G. Schettini,
M. Schneider,
P.K. Sharma,
A.A. Tuccillo,
O. Tudisco,
G. Vecchi,
R. Villari,
K. Vulliez,
Y. Wu,
Q. Zeng
[show abstract]
[hide abstract]
ABSTRACT: A 20 MW Lower Hybrid Current Drive system using an antenna based on the Passive-Active Multijunction (PAM) concept is envisaged on ITER. This paper gives an overview of the mechanical analysis, modeling and design carried out on two major elements of the antenna: the grill front face, and the RF feed-through or windows. The front face will have to withstand high heat and fast neutrons fluxes directly from the plasma. It will be actively cooled and present a beryllium coating upon ITER requirement. The RF window being a critical safety importance class component (SIC) because of its tritium confinement function, two of them will be put in series on each line to achieve a double barrier. A design of a water cooled 5 GHz CW RF “pillbox” window capable of sustaining 500 kW of transmitted power is proposed. Both studies allow to move forward, and focus on critical issues, such as manufacturing processes and R&D associated programs including tests of mock-ups.
Fusion Engineering and Design 02/2011; 86(6-8):810-814. · 1.49 Impact Factor
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P.K. Sharma,
F. Kazarian,
P. Garibaldi,
T. Gassman, J.F. Artaud,
Y.S. Bae,
J. Belo,
G. Berger-By,
J.M. Bernard,
Ph. Cara, [......],
Y. Peysson,
A. Saille,
G. Schettini,
M. Schneider,
O. Tudisco,
G. Vecchi,
S.R. Villari,
K. Vulliez,
Y. Wu,
Q. Zeng
[show abstract]
[hide abstract]
ABSTRACT: In the framework of the EFDA task HCD-08-03-01, the ITER lower hybrid current drive (LHCD) system design has been reviewed. The system aims to generate 24 MW of RF power at 5 GHz, of which 20 MW would be coupled to the plasmas. The present state of the art does not allow envisaging a unitary output of the klystrons exceeding 500 kW, so the project is based on 48 klystron units, leaving some margin when the transmission lines losses are taken into account. A high voltage power supply (HVPS), required to operate the klystrons, is proposed. A single HVPS would be used to feed and operate four klystrons in parallel configuration. Based on the above considerations, it is proposed to design and develop twelve HVPS, based on pulse step modulator (PSM) technology, each rated for 90 kV/90 A. This paper describes in details, the typical electrical requirements and the conceptual design of the proposed HVPS for the ITER LHCD system.
Fusion Engineering and Design. 01/2011; 86(6-8):819-822.
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S. Meschino,
S. Ceccuzzi,
F. Mirizzi,
L. Pajewski,
G. Schettini, J.F. Artaud,
Y.S. Bae,
J.H. Belo,
G. Berger-By,
J.M. Bernard, [......],
W. Namkung,
L. Panaccione,
Y. Peysson,
P.K. Sharma,
M. Schneider,
A.A. Tuccillo,
O. Tudisco,
G. Vecchi,
R. Villari,
K. Vulliez
[show abstract]
[hide abstract]
ABSTRACT: The use of rectangular oversized waveguides in the Main Transmission Lines of the Lower Hybrid Current Drive (LHCD) system of ITER, requires to investigate the problem of bends. The principal specifications that characterize the oversized bend design concern the minimization of the reflection of the fundamental mode and the maximization of its transmission, limiting at the same time its coupling to spurious modes that could propagate at the operational frequency. In this paper, the performances of bends with different geometries are compared. They are simulated using the commercial finite element software Ansoft HFSS. An innovative modified mitre-bend solution with trapezoidal-elements is proposed and analyzed.
Fusion Engineering and Design. 01/2011; 86(6-8):746-749.
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D. Milanesio,
J. Hillairet,
L. Panaccione,
R. Maggiora, J.F. Artaud,
Y.S. Bae,
A.M.A. Barbera,
J. Belo,
G. Berger-By,
J.M. Bernard, [......],
A. Saille,
G. Schettini,
M. Schneider,
P.K. Sharma,
A.A. Tuccillo,
O. Tudisco,
R. Villari,
K. Vulliez,
Y. Wu,
Q. Zeng
[show abstract]
[hide abstract]
ABSTRACT: In order to assist the design of the future ITER Lower Hybrid launcher, coupling codes ALOHA, from CEA/IRFM, TOPLHA, from Politecnico di Torino, and GRILL3D, developed by Dr. Mikhail Irzak (A.F. Ioffe Physico-Technical Institute, St. Petersburg, Russia) and operated by ENEA Frascati, have been compared with the updated (six modules with four active waveguides per module) Passive-Active Multi-junction (PAM) Lower Hybrid antennas. Both ALOHA and GRILL3D formulate the problem in terms of rectangular waveguides modes, while TOPLHA is based on boundary-value problem with the adoption of a triangular cell-mesh to represent the relevant waveguides surfaces. Several plasma profiles, with varying edge density and density increase, have been adopted to provide a complete description of the simulated launcher in terms of reflection coefficient, computed at the beginning of each LH module, and of power spectra. Good agreement can be observed among codes for all the simulated profiles.
Fusion Engineering and Design. 01/2011; 86(6-8):827-830.
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J Decker,
Y Peysson,
J Hillairet, J -F Artaud,
V Basiuk,
A Becoulet,
A Ekedahl,
M Goniche,
G T Hoang,
F Imbeaux,
A K Ram,
M Schneider
Nuclear Fusion. 01/2011; 51(7):073025.
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S. Ceccuzzi,
S. Meschino,
F. Mirizzi, J.F. Artaud,
Y.S. Bae,
J. Belo,
G. Berger-By,
J.M. Bernard,
Ph. Cara,
A. Cardinali, [......],
G. Schettini,
M. Schneider,
P.K. Sharma,
A.A. Tuccillo,
O. Tudisco,
G. Vecchi,
R. Villari,
K. Vulliez,
Y. Wu,
Q. Zeng
[show abstract]
[hide abstract]
ABSTRACT: Oversized waveguides allow to transmit high electromagnetic power, but require components able to filter the unwanted modal content unavoidably excited along their path. In this paper mode filters based on corrugations partially filled with absorbing materials are described; they have been studied aiming at optimizing their performance and overcoming their intrinsic limitations. More precisely the dependence of the filtering performance on various geometrical parameters is derived using analytical and numerical approaches. The problems related with the power handling capability of mode filters are shortly considered too. Finally the role of degenerate modes in deteriorating the filtering performance is explained and a solution to this problem is presented.
Fusion Engineering and Design 12/2010; 86(6-8):909-912. · 1.49 Impact Factor
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[show abstract]
[hide abstract]
ABSTRACT: Hybrid scenario performance in ITER is studied with the CRONOS integrated modelling suite, using the GLF23 anomalous transport model for heat transport prediction. GLF23 predicted core confinement is optimized through tailoring the q-profile shape by a careful choice of current drive actuators, affecting the transport due to the predicted dependence of the turbulence level on the absolute q-profile values and magnetic shear. A range of various heating and current drive choices are examined, as are different assumptions on the pedestal height. The optimum q-profile shape is predicted to be one that maximizes the ratio of s/q throughout the bulk of the plasma volume. Optimizing the confinement allows a minimization of the plasma density required in order to achieve a defined target fusion power of 350 MW. A lower density then allows a lower total current (Ip) at the same Greenwald fraction (fG), thus aiding in maintaining q > 1 as desired in a hybrid scenario, and in minimizing the flux consumption. The best performance is achieved with a combination of NBI and ECCD (e.g. 33/37 MW NBI/ECCD for a scenario with a pedestal height of 4 keV). The q-profile shape and plasma confinement properties are shown to be highly sensitive to the positioning of the ECCD deposition. Comparisons with the lower performing cases where some or all of the ECCD power is replaced with LHCD or ICRH are shown (e.g. 33/20/17 MW NBI/ECCD/LHCD or NBI/ECCD/ICRH). The inclusion of LHCD reduces confinement due to deleterious shaping of the q-profile, and the inclusion of ICRH, particularly in a stiff model, does not lead to significantly increased fusion power and furthermore does not contribute to the non-inductive current fraction. For the optimum NBI/ECCD current drive mix, the predictions show that a satisfactory ITER hybrid scenario (Pfus ~ 350 MW, Q ≥ 5, qmin close to 1) may be achieved with Tped ≥ 4 keV. In addition, predicted performance sensitivity analysis was carried out for several assumed parameters, such as Zeff and density peaking.
Nuclear Fusion 10/2010; 50(11):115007. · 4.09 Impact Factor
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R. Guirlet,
A. Sirinelli,
T. Parisot,
R. Sabot, J.F. Artaud,
C. Bourdelle,
X. Garbet,
P. Hennequin,
G.T. Hoang,
F. Imbeaux,
J.L. Ségui,
D. Mazon,
D. Villegas
[show abstract]
[hide abstract]
ABSTRACT: Electron and impurity transport has been studied in sawtoothing plasmas in the Tore-Supra tokamak. High time and space resolution measurements of the electron density reveal the existence of a flat profile region encompassing the q = 1 surface, on which is superimposed a density peak building up between sawtooth relaxations. For the first time in this regime, we have determined the underlying transport of both nickel and electrons independently of the effect of sawteeth in the central part of the plasma. Electron transport is consistent with the neoclassical expectations only in the close vicinity of the magnetic axis. Further out, it exceeds the neoclassical values as calculated with the NCLASS code, although the turbulence level is very low in the whole central region region. In contrast, nickel transport is in good agreement with the neoclassical calculations in the same region. The neoclassical effect on trapped particles of a persisting mode due to incomplete reconnection of the magnetic surfaces is consistent with these observations.
Nuclear Fusion 07/2010; 50(9):095009. · 4.09 Impact Factor
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J.F. Artaud,
V. Basiuk,
F. Imbeaux,
M. Schneider,
J. Garcia,
G. Giruzzi,
P. Huynh,
T. Aniel,
F. Albajar,
J.M. Ané, [......],
F. Köchl,
J. Lister,
X. Litaudon,
P. Maget,
R. Masset,
B. Pégourié,
Y. Peysson,
P. Thomas,
E. Tsitrone,
F. Turco
[show abstract]
[hide abstract]
ABSTRACT: CRONOS is a suite of numerical codes for the predictive/interpretative simulation of a full tokamak discharge. It integrates, in a modular structure, a 1D transport solver with general 2D magnetic equilibria, several heat, particle and impurities transport models, as well as heat, particle and momentum sources. This paper gives a first comprehensive description of the CRONOS suite: overall structure of the code, main available models, details on the simulation workflow and numerical implementation. Some examples of applications to the analysis of experimental discharges and the predictions of ITER scenarios are also given.
Nuclear Fusion 03/2010; 50(4):043001. · 4.09 Impact Factor
