Search

Your search keyword '"Colandrea, C."' showing total 26 results
Start Over Author "Colandrea, C." Search Limiters Available in Library Collection
26 results on '"Colandrea, C."'

1. Investigating the influence of divertor baffles on nitrogen-seeded detachment in TCV with SOLPS-ITER simulations and TCV experiments

Author

Sun, G., Reimerdes, H., Theiler, C., Duval, B. P., Carpita, M., Colandrea, C., Ducker, R., Fevrier, O., Gorno, S., Simons, L., and Tonello, E.

Subjects
Physics - Plasma Physics
Abstract

Plasma edge simulations with the SOLPS-ITER code are performed to study the influence of divertor baffles on nitrogen-seeded detachment in TCV single-null, L-mode discharges. Scans of nitrogen seeding rate are conducted in both baffled and unbaffled TCV divertors, where the nitrogen seeding with baffles is found to yield lower target temperatures and heat fluxes than with baffles-only and with seeding-only. The cumulative effects of baffles and seeding on target parameters are explained by the two-point model. The divertor neutral density and neutral compression increase with baffles, due to lower divertor to main chamber neutral conductance, as explained by a schematic neutral transport model with baffles. The nitrogen retention, defined as the ratio of average nitrogen nuclei density in divertor and main chamber, increases with the seeding rate if baffled, and remains constant if unbaffled. At the same outboard mid-plane separatrix plasma density, the nitrogen retention with baffles is lower than the unbaffled retention at low seeding levels and is higher at high seeding levels, which is explained by the changes of nitrogen ion and neutral transport with baffles and seeding. The baffled carbon retention is higher than the unbaffled retention due to lower divertor to main chamber carbon neutral conductance. Baffles increase the divertor radiation. The predicted trends of target parameters, the distribution of neutrals and radiations are well supported by TCV experiments, though discrepancies in the absolute values remain. The simulations yield an overall colder and denser divertor, consistent with previous SOLPS-ITER simulations of Ohmically heated L-modes in TCV. The successful comparison of simulation and experiment, together with the understanding gained from the neutral transport model, increases the confidence in the SOLPS simulations for the next TCV divertor upgrade.

Published
2023

2. Validation of SOLPS-ITER Simulations against the TCV-X21 Reference Case

Author

Wang, Y., Colandrea, C., Oliveira, D. S., Theiler, C., Reimerdes, H., Body, T., Galassi, D., Martinelli, L., Lee, K., and team, TCV

Subjects
Physics - Plasma Physics
Abstract

This paper presents a quantitative validation of SOLPS-ITER simulations against the TCV-X21 reference case and provides insights into the neutral dynamics and ionization source distribution in this scenario. TCV-X21 is a well-diagnosed diverted L-mode sheath-limited plasma scenario in both toroidal field directions, designed specifically for the validation of turbulence codes [D.S. Oliveira, T. Body, et al 2022 Nucl. Fusion 62 096001]. Despite the optimization to reduce the impact of the neutral dynamics, the absence of neutrals in previous turbulence simulations of TCV-X21 was identified as a possible explanation for the disagreements with the experimental data in the divertor region. This motivates the present study with SOLPS-ITER that includes kinetic neutral dynamics via EIRENE. Five new observables are added to the extensive, publicly available TCV-X21 dataset. These are three deuterium Balmer lines in the divertor and neutral pressure in the common and private flux regions. The quantitative agreement metric is combined with the conjugate gradient method to approach the SOLPS-ITER input parameters that return the best overall agreement with the experiment. A proof-of-principle of this method results in a modest improvement in the level-of-agreement; shortcomings of the method and how to improve it are discussed. Alternatively, a scan of the particle and heat diffusion coefficients shows an improvement of 10.4% beyond the agreement level achieved by the gradient method. The result is found for an increased transport coefficient compared to what is usually used for TCV L-mode plasmas, suggesting the need for accurate self-consistent turbulence models for predictive boundary simulations. The simulations indicate that ~65% of the total ionization occurs in the SOL, motivating the inclusion of neutrals in future turbulence simulations towards improved agreement with the experiment.

Published
2023
Full Text
View/download PDF

3. Comparison of detachment in Ohmic plasmas with positive and negative triangularity

Author

Février, O., Tsui, C. K., Durr-Legoupil-Nicoud, G., Theiler, C., Carpita, M., Coda, S., Colandrea, C., Duval, B. P., Gorno, S., Huett, E., Linehan, B., Perek, A., Porte, L., Reimerdes, H., Sauter, O., Tonello, E., Zurita, M., Bolzonella, T., Sciortino, F., Team, the TCV, and Team, the EUROfusion Tokamak Exploitation

Subjects
Physics - Plasma Physics
Abstract

In recent years, negative triangularity (NT) has emerged as a potential high-confinement L-mode reactor solution. In this work, detachment is investigated using core density ramps in lower single null Ohmic L-mode plasmas across a wide range of upper, lower, and average triangularity (the mean of upper and lower triangularity: $\delta$) in the TCV tokamak. It is universally found that detachment is more difficult to access for NT shaping. The outer divertor leg of discharges with $\delta\approx -0.3$ could not be cooled to below $5~\mathrm{eV}$ through core density ramps alone. The behavior of the upstream plasma and geometrical divertor effects (e.g. a reduced connection length with negative lower triangularity) do not fully explain the challenges in detaching NT plasmas. Langmuir probe measurements of the target heat flux widths ($\lambda_q$) were constant to within 30% across an upper triangularity scan, while the spreading factor $S$ was lower by up to 50% for NT, indicating a generally lower integral Scrape-Off Layer width, $\lambda_{int}$. The line-averaged core density was typically higher for NT discharges for a given fuelling rate, possibly linked to higher particle confinement in NT. Conversely, the divertor neutral pressure and integrated particle fluxes to the targets were typically lower for the same line-averaged density, indicating that NT configurations may be closer to the sheath-limited regime than their PT counterparts, which may explain why NT is more challenging to detach.

Published
2023

4. Parallel flows as a key component to interpret Super-X divertor experiments

Author

Carpita, M., Février, O., Reimerdes, H., Theiler, C., Duval, B. P., Colandrea, C., Durr-Legoupil-Nicoud, G., Galassi, D., Gorno, S., Huett, E., Loizu, J., Martinelli, L., Perek, A., Simons, L., Sun, G., Tonello, E., Wüthrich, C., and team, the TCV

Subjects
Physics - Plasma Physics
Abstract

The Super-X Divertor (SXD) is an alternative divertor configuration leveraging total flux expansion at the Outer Strike Point (OSP). While the extended 2-Point Model (2PM) predicts facilitated detachment access and control in the SXD configuration, these attractive features are not always retrieved experimentally. These discrepancies are at least partially explained by the effect of parallel flows which, when self-consistently included in the 2PM, reveal the role of total flux expansion on the pressure balance and weaken the total flux expansion effect on detachment access and control, compared to the original predictions. This new model can partially explain the discrepancies between the 2PM and experiments performed on tokamak \`a configuration variable (TCV), in ohmic L-mode scenarios, which are particularly apparent when scanning the OSP major radius Rt. In core density ramps in lower Single-Null (SN) configuration, the impact of Rt on the CIII emission front movement in the divertor outer leg - used as a proxy for the plasma temperature in the divertor - is substantially weaker than 2PM predictions. Furthermore, in OSP radial sweeps in lower and upper SN configurations, in ohmic L-mode scenarios with a constant core density, the peak parallel particle flux density at the OSP is almost independent of Rt, while the 2PM predicts a linear dependence. Finally, analytical and numerical modeling of parallel flows in the divertor is presented. It is shown that an increase in total flux expansion can favour supersonic flows at the OSP. Parallel flows are also shown to be relevant by analysing SOLPS-ITER simulations of TCV., Comment: This version of the paper is outdated. The most recent, and published, version of the paper can be found at the corresponding Journal / DOI reference

Published
2023
Full Text
View/download PDF

5. Performance assessment of a tightly baffled, long-legged divertor configuration in TCV with SOLPS-ITER

Author

Sun, G., Reimerdes, H., Theiler, C., Duval, B. P., Carpita, M., Colandrea, C., Février, O., and team, the TCV

Subjects
Physics - Plasma Physics
Abstract

Numerical simulations explore the possibility to test the tightly baffled, long-legged divertor (TBLLD) concept in a future upgrade of the Tokamak \`a configuration variable (TCV). The SOLPS-ITER code package is used to compare the exhaust performance of several TBLLD configurations with existing unbaffled and baffled TCV configurations. The TBLLDs feature a range of radial gaps between the separatrix and the outer leg side walls. All considered TBLLDs are predicted to lead to a denser and colder plasma in front of the targets and improve the power handling by factors of 2-3 compared to the present, baffled divertor and by up to a factor of 12 compared to the original, unbaffled configuration. The improved TBLLD performance is mainly due to a better neutral confinement with improved plasma-neutral interactions in the divertor region. Both power handling capability and neutral confinement increases when reducing the radial gap. The core compatibility of TBLLDs with nitrogen seeding is also evaluated and the detachment window with acceptable core pollution for the proposed TBLLDs is explored, showing a reduction of required upstream impurity concentration up to 18% to achieve the detachment with thinner radial gap.

Published
2023
Full Text
View/download PDF

6. Improved Heat and Particle Flux Mitigation in High Core Confinement, Baffled, Alternate Divertor Configurations in the TCV tokamak

Author

Raj, Harshita, Theiler, C., Thornton, A., Fevrier, O., Gorno, S., Bagnato, F., Blanchard, P., Colandrea, C., de Oliveira, H., Duval, B. P., Labit, B., Perek, A., Reimerdes, H., Sheikh, U., Vallar, M., and Vincent, B.

Subjects
Physics - Plasma Physics
Abstract

Nitrogen seeded detachment has been achieved in the Tokamak a Configuration Variable (TCV) in advanced divertor configurations (ADCs), namely X-divertor and X-point target, with and without baffles in H-mode plasmas with high core confinement. Both ADCs show a remarkable reduction in the inter-ELM particle and heat fluxes to the target compared to the standard divertor configuration. 95-98% of the peak heat flux to the target is mitigated as a synergetic effect of ADCs, baffling, and nitrogen seeded detachment. The effect of divertor geometry and baffles on core-divertor compatibility is investigated in detail. The power balance in these experiments is also investigated to explore the physics behind the observed reduction in heat fluxes in the ADCs.

Published
2022
Full Text
View/download PDF

7. Validation of edge turbulence codes against the TCV-X21 diverted L-mode reference case

Author

Oliveira, D. S., Body, T., Galassi, D., Theiler, C., Laribi, E., Tamain, P., Stegmeir, A., Giacomin, M., Zholobenko, W., Ricci, P., Bufferand, H., Boedo, J. A., Ciraolo, G., Colandrea, C., Coster, D., de Oliveira, H., Fourestey, G., Gorno, S., Imbeaux, F., Jenko, F., Naulin, V., Offeddu, N., Reimerdes, H., Serre, E., Tsui, C. K., Varini, N., Vianello, N., Wiesenberger, M., Wüthrich, C., and Team, the TCV

Subjects
Physics - Plasma Physics
Abstract

Self-consistent full-size turbulent-transport simulations of the divertor and SOL of existing tokamaks have recently become feasible. This enables the direct comparison of turbulence simulations against experimental measurements. In this work, we perform a series of diverted Ohmic L-mode discharges on the TCV tokamak, building a first-of-a-kind dataset for the validation of edge turbulence models. This dataset, referred to as TCV-X21, contains measurements from 5 diagnostic systems -- giving a total of 45 1- and 2-D comparison observables in two toroidal magnetic field directions. The dataset is used to validate three flux-driven 3D fluid-turbulence models: GBS, GRILLIX and TOKAM3X. With each model, we perform simulations of the TCV-X21 scenario, tuning the particle and power source rates to achieve a reasonable match of the upstream separatrix value of density and electron temperature. We find that the simulations match the experimental profiles for most observables at the OMP -- both in terms of profile shape and absolute magnitude -- while a poorer agreement is found towards the divertor targets. The match between simulation and experiment is seen to be sensitive to the value of the resistivity, the heat conductivities, the power injection rate and the choice of sheath boundary conditions. Additionally, despite targeting a sheath-limited regime, the discrepancy between simulations and experiment also suggests that the neutral dynamics should be included. The results of this validation show that turbulence models are able to perform simulations of existing devices and achieve reasonable agreement with experimental measurements. Where disagreement is found, the validation helps to identify how the models can be improved. By publicly releasing the experimental dataset, this work should help to guide and accelerate the development of predictive turbulence simulations of the edge and SOL.

Published
2021
Full Text
View/download PDF

8. Benign termination of runaway electron beams on ASDEX Upgrade and TCV

Author

Sheikh, U, Decker, J, Hoppe, M, Pedrini, M, Sieglin, B, Simons, L, Cazabonne, J, Caloud, J, Cerovsky, J, Coda, S, Colandrea, C, Dal Molin, A, Duval, B, Ficker, O, Griener, M, Papp, G, Pautasso, G, Paz-Soldan, C, Reux, C, Tomesova, E, Wijkamp, T, Sheikh U., Decker J., Hoppe M., Pedrini M., Sieglin B., Simons L., Cazabonne J., Caloud J., Cerovsky J., Coda S., Colandrea C., Dal Molin A., Duval B., Ficker O., Griener M., Papp G., Pautasso G., Paz-Soldan C., Reux C., Tomesova E., Wijkamp T., Sheikh, U, Decker, J, Hoppe, M, Pedrini, M, Sieglin, B, Simons, L, Cazabonne, J, Caloud, J, Cerovsky, J, Coda, S, Colandrea, C, Dal Molin, A, Duval, B, Ficker, O, Griener, M, Papp, G, Pautasso, G, Paz-Soldan, C, Reux, C, Tomesova, E, Wijkamp, T, Sheikh U., Decker J., Hoppe M., Pedrini M., Sieglin B., Simons L., Cazabonne J., Caloud J., Cerovsky J., Coda S., Colandrea C., Dal Molin A., Duval B., Ficker O., Griener M., Papp G., Pautasso G., Paz-Soldan C., Reux C., Tomesova E., and Wijkamp T.

Abstract

This paper discusses the development of a benign termination scenario for runaway electron (RE) beams on ASDEX Upgrade and TCV. A systematic study revealed that a low electron density (n e) companion plasma was required to achieve a large MHD instability, which expelled the confined REs over a large wetted area and allowed for the conversion of magnetic energy to radiation. Control of the companion plasma ne was achieved via neutral pressure regulation and was agnostic to material injection method. The neutral pressure required for recombination was found to be dependent on impurity species, quantity and RE current. On TCV, n e increased at neutral pressures above 1 Pa, indicating that higher collisionality between the REs and neutrals may lead to an upper pressure limit. The conversion of magnetic energy to radiated energy was measured on both machines and a decrease in efficiency was observed at high neutral pressure on TCV. The benign termination technique was able to prevent any significant increase in maximum heat flux on AUG from 200 to 600 kA of RE current, highlighting the ability of this approach to handle fully formed RE beams.

Published
2024

9. Benign termination of runaway electron beams on ASDEX Upgrade and TCV

Author

Sheikh, U., Decker, J., Hoppe, Mathias, Pedrini, M., Sieglin, B., Simons, L., Cazabonne, J., Caloud, J., Cerovsky, J., Coda, S., Colandrea, C., Dal Molin, A., Duval, B., Ficker, O., Griener, M., Papp, G., Pautasso, G., Paz-Soldan, C., Reux, C., Tomesova, E., Wijkamp, T., Sheikh, U., Decker, J., Hoppe, Mathias, Pedrini, M., Sieglin, B., Simons, L., Cazabonne, J., Caloud, J., Cerovsky, J., Coda, S., Colandrea, C., Dal Molin, A., Duval, B., Ficker, O., Griener, M., Papp, G., Pautasso, G., Paz-Soldan, C., Reux, C., Tomesova, E., and Wijkamp, T.

Abstract

This paper discusses the development of a benign termination scenario for runaway electron (RE) beams on ASDEX Upgrade and TCV. A systematic study revealed that a low electron density (n e) companion plasma was required to achieve a large MHD instability, which expelled the confined REs over a large wetted area and allowed for the conversion of magnetic energy to radiation. Control of the companion plasma ne was achieved via neutral pressure regulation and was agnostic to material injection method. The neutral pressure required for recombination was found to be dependent on impurity species, quantity and RE current. On TCV, n e increased at neutral pressures above 1 Pa, indicating that higher collisionality between the REs and neutrals may lead to an upper pressure limit. The conversion of magnetic energy to radiated energy was measured on both machines and a decrease in efficiency was observed at high neutral pressure on TCV. The benign termination technique was able to prevent any significant increase in maximum heat flux on AUG from 200 to 600 kA of RE current, highlighting the ability of this approach to handle fully formed RE beams., QC 20240201

Published
2024
Full Text
View/download PDF

11. Overview of the TCV tokamak experimental programme

Author

Reimerdes, H, Agostini, M, Alessi, E, Alberti, S, Andrebe, Y, Arnichand, H, Balbin, J, Bagnato, F, Baquero-Ruiz, M, Bernert, M, Bin, W, Blanchard, P, Blanken, T, Boedo, J, Brida, D, Brunner, S, Bogar, C, Bogar, O, Bolzonella, T, Bombarda, F, Bouquey, F, Bowman, C, Brunetti, D, Buermans, J, Bufferand, H, Calacci, L, Camenen, Y, Carli, S, Carnevale, D, Carpanese, F, Causa, F, Cavalier, J, Cavedon, M, Cazabonne, J, Cerovsky, J, Chandra, R, Chandrarajan Jayalekshmi, A, Chellai, O, Chmielewski, P, Choi, D, Ciraolo, G, Classen, I, Coda, S, Colandrea, C, Dal Molin, A, David, P, De Baar, M, Decker, J, Dekeyser, W, De Oliveira, H, Douai, D, Dreval, M, Dunne, M, Duval, B, Elmore, S, Embreus, O, Eriksson, F, Faitsch, M, Falchetto, G, Farnik, M, Fasoli, A, Fedorczak, N, Felici, F, Fevrier, O, Ficker, O, Fil, A, Fontana, M, Fransson, E, Frassinetti, L, Furno, I, Gahle, D, Galassi, D, Galazka, K, Galperti, C, Garavaglia, S, Garcia-Munoz, M, Geiger, B, Giacomin, M, Giruzzi, G, Gobbin, M, Golfinopoulos, T, Goodman, T, Gorno, S, Granucci, G, Graves, J, Griener, M, Gruca, M, Gyergyek, T, Haelterman, R, Hakola, A, Han, W, Happel, T, Harrer, G, Harrison, J, Henderson, S, Hogeweij, G, Hogge, J, Hoppe, M, Horacek, J, Huang, Z, Iantchenko, A, Innocente, P, Insulander Bjork, K, Ionita-Schrittweiser, C, Isliker, H, Jardin, A, Jaspers, R, Karimov, R, Karpushov, A, Kazakov, Y, Komm, M, Kong, M, Kovacic, J, Krutkin, O, Kudlacek, O, Kumar, U, Kwiatkowski, R, Labit, B, Laguardia, L, Lammers, J, Laribi, E, Laszynska, E, Lazaros, A, Linder, O, Linehan, B, Lipschultz, B, Llobet, X, Loizu, J, Lunt, T, Macusova, E, Marandet, Y, Maraschek, M, Marceca, G, Marchetto, C, Marchioni, S, Marmar, E, Martin, Y, Martinelli, L, Matos, F, Maurizio, R, Mayoral, M, Mazon, D, Menkovski, V, Merle, A, Merlo, G, Meyer, H, Mikszuta-Michalik, K, Molina Cabrera, P, Morales, J, Moret, J, Moro, A, Moulton, D, Muhammed, H, Myatra, O, Mykytchuk, D, Napoli, F, Nem, R, Nielsen, A, Nocente, M, Nowak, S, Offeddu, N, Olsen, J, Orsitto, F, Pan, O, Papp, G, Pau, A, Perek, A, Pesamosca, F, Peysson, Y, Pigatto, L, Piron, C, Poradzinski, M, Porte, L, Putterich, T, Rabinski, M, Raj, H, Rasmussen, J, Ratta, G, Ravensbergen, T, Ricci, D, Ricci, P, Rispoli, N, Riva, F, Rivero-Rodriguez, J, Salewski, M, Sauter, O, Schmidt, B, Schrittweiser, R, Sharapov, S, Sheikh, U, Sieglin, B, Silva, M, Smolders, A, Snicker, A, Sozzi, C, Spolaore, M, Stagni, A, Stipani, L, Sun, G, Tala, T, Tamain, P, Tanaka, K, Tema Biwole, A, Terranova, D, Terry, J, Testa, D, Theiler, C, Thornton, A, Thrysoe, A, Torreblanca, H, Tsui, C, Vaccaro, D, Vallar, M, Van Berkel, M, Van Eester, D, Van Kampen, R, Van Mulders, S, Verhaegh, K, Verhaeghe, T, Vianello, N, Villone, F, Viezzer, E, Vincent, B, Voitsekhovitch, I, Vu, N, Walkden, N, Wauters, T, Weisen, H, Wendler, N, Wensing, M, Widmer, F, Wiesen, S, Wischmeier, M, Wijkamp, T, Wunderlich, D, Wuthrich, C, Yanovskiy, V, Zebrowski, J, Reimerdes H., Agostini M., Alessi E., Alberti S., Andrebe Y., Arnichand H., Balbin J., Bagnato F., Baquero-Ruiz M., Bernert M., Bin W., Blanchard P., Blanken T. C., Boedo J. A., Brida D., Brunner S., Bogar C., Bogar O., Bolzonella T., Bombarda F., Bouquey F., Bowman C., Brunetti D., Buermans J., Bufferand H., Calacci L., Camenen Y., Carli S., Carnevale D., Carpanese F., Causa F., Cavalier J., Cavedon M., Cazabonne J. A., Cerovsky J., Chandra R., Chandrarajan Jayalekshmi A., Chellai O., Chmielewski P., Choi D., Ciraolo G., Classen I. G. J., Coda S., Colandrea C., Dal Molin A., David P., De Baar M. R., Decker J., Dekeyser W., De Oliveira H., Douai D., Dreval M., Dunne M. G., Duval B. P., Elmore S., Embreus O., Eriksson F., Faitsch M., Falchetto G., Farnik M., Fasoli A., Fedorczak N., Felici F., Fevrier O., Ficker O., Fil A., Fontana M., Fransson E., Frassinetti L., Furno I., Gahle D. S., Galassi D., Galazka K., Galperti C., Garavaglia S., Garcia-Munoz M., Geiger B., Giacomin M., Giruzzi G., Gobbin M., Golfinopoulos T., Goodman T., Gorno S., Granucci G., Graves J. P., Griener M., Gruca M., Gyergyek T., Haelterman R., Hakola A., Han W., Happel T., Harrer G., Harrison J. R., Henderson S., Hogeweij G. M. D., Hogge J. -P., Hoppe M., Horacek J., Huang Z., Iantchenko A., Innocente P., Insulander Bjork K., Ionita-Schrittweiser C., Isliker H., Jardin A., Jaspers R. J. E., Karimov R., Karpushov A. N., Kazakov Y., Komm M., Kong M., Kovacic J., Krutkin O., Kudlacek O., Kumar U., Kwiatkowski R., Labit B., Laguardia L., Lammers J. T., Laribi E., Laszynska E., Lazaros A., Linder O., Linehan B., Lipschultz B., Llobet X., Loizu J., Lunt T., Macusova E., Marandet Y., Maraschek M., Marceca G., Marchetto C., Marchioni S., Marmar E. S., Martin Y., Martinelli L., Matos F., Maurizio R., Mayoral M. -L., Mazon D., Menkovski V., Merle A., Merlo G., Meyer H., Mikszuta-Michalik K., Molina Cabrera P. A., Morales J., Moret J. -M., Moro A., Moulton D., Muhammed H., Myatra O., Mykytchuk D., Napoli F., Nem R. D., Nielsen A. H., Nocente M., Nowak S., Offeddu N., Olsen J., Orsitto F. P., Pan O., Papp G., Pau A., Perek A., Pesamosca F., Peysson Y., Pigatto L., Piron C., Poradzinski M., Porte L., Putterich T., Rabinski M., Raj H., Rasmussen J. J., Ratta G. A., Ravensbergen T., Ricci D., Ricci P., Rispoli N., Riva F., Rivero-Rodriguez J. F., Salewski M., Sauter O., Schmidt B. S., Schrittweiser R., Sharapov S., Sheikh U. A., Sieglin B., Silva M., Smolders A., Snicker A., Sozzi C., Spolaore M., Stagni A., Stipani L., Sun G., Tala T., Tamain P., Tanaka K., Tema Biwole A., Terranova D., Terry J. L., Testa D., Theiler C., Thornton A., Thrysoe A., Torreblanca H., Tsui C. K., Vaccaro D., Vallar M., Van Berkel M., Van Eester D., Van Kampen R. J. R., Van Mulders S., Verhaegh K., Verhaeghe T., Vianello N., Villone F., Viezzer E., Vincent B., Voitsekhovitch I., Vu N. M. T., Walkden N., Wauters T., Weisen H., Wendler N., Wensing M., Widmer F., Wiesen S., Wischmeier M., Wijkamp T. A., Wunderlich D., Wuthrich C., Yanovskiy V., Zebrowski J., Reimerdes, H, Agostini, M, Alessi, E, Alberti, S, Andrebe, Y, Arnichand, H, Balbin, J, Bagnato, F, Baquero-Ruiz, M, Bernert, M, Bin, W, Blanchard, P, Blanken, T, Boedo, J, Brida, D, Brunner, S, Bogar, C, Bogar, O, Bolzonella, T, Bombarda, F, Bouquey, F, Bowman, C, Brunetti, D, Buermans, J, Bufferand, H, Calacci, L, Camenen, Y, Carli, S, Carnevale, D, Carpanese, F, Causa, F, Cavalier, J, Cavedon, M, Cazabonne, J, Cerovsky, J, Chandra, R, Chandrarajan Jayalekshmi, A, Chellai, O, Chmielewski, P, Choi, D, Ciraolo, G, Classen, I, Coda, S, Colandrea, C, Dal Molin, A, David, P, De Baar, M, Decker, J, Dekeyser, W, De Oliveira, H, Douai, D, Dreval, M, Dunne, M, Duval, B, Elmore, S, Embreus, O, Eriksson, F, Faitsch, M, Falchetto, G, Farnik, M, Fasoli, A, Fedorczak, N, Felici, F, Fevrier, O, Ficker, O, Fil, A, Fontana, M, Fransson, E, Frassinetti, L, Furno, I, Gahle, D, Galassi, D, Galazka, K, Galperti, C, Garavaglia, S, Garcia-Munoz, M, Geiger, B, Giacomin, M, Giruzzi, G, Gobbin, M, Golfinopoulos, T, Goodman, T, Gorno, S, Granucci, G, Graves, J, Griener, M, Gruca, M, Gyergyek, T, Haelterman, R, Hakola, A, Han, W, Happel, T, Harrer, G, Harrison, J, Henderson, S, Hogeweij, G, Hogge, J, Hoppe, M, Horacek, J, Huang, Z, Iantchenko, A, Innocente, P, Insulander Bjork, K, Ionita-Schrittweiser, C, Isliker, H, Jardin, A, Jaspers, R, Karimov, R, Karpushov, A, Kazakov, Y, Komm, M, Kong, M, Kovacic, J, Krutkin, O, Kudlacek, O, Kumar, U, Kwiatkowski, R, Labit, B, Laguardia, L, Lammers, J, Laribi, E, Laszynska, E, Lazaros, A, Linder, O, Linehan, B, Lipschultz, B, Llobet, X, Loizu, J, Lunt, T, Macusova, E, Marandet, Y, Maraschek, M, Marceca, G, Marchetto, C, Marchioni, S, Marmar, E, Martin, Y, Martinelli, L, Matos, F, Maurizio, R, Mayoral, M, Mazon, D, Menkovski, V, Merle, A, Merlo, G, Meyer, H, Mikszuta-Michalik, K, Molina Cabrera, P, Morales, J, Moret, J, Moro, A, Moulton, D, Muhammed, H, Myatra, O, Mykytchuk, D, Napoli, F, Nem, R, Nielsen, A, Nocente, M, Nowak, S, Offeddu, N, Olsen, J, Orsitto, F, Pan, O, Papp, G, Pau, A, Perek, A, Pesamosca, F, Peysson, Y, Pigatto, L, Piron, C, Poradzinski, M, Porte, L, Putterich, T, Rabinski, M, Raj, H, Rasmussen, J, Ratta, G, Ravensbergen, T, Ricci, D, Ricci, P, Rispoli, N, Riva, F, Rivero-Rodriguez, J, Salewski, M, Sauter, O, Schmidt, B, Schrittweiser, R, Sharapov, S, Sheikh, U, Sieglin, B, Silva, M, Smolders, A, Snicker, A, Sozzi, C, Spolaore, M, Stagni, A, Stipani, L, Sun, G, Tala, T, Tamain, P, Tanaka, K, Tema Biwole, A, Terranova, D, Terry, J, Testa, D, Theiler, C, Thornton, A, Thrysoe, A, Torreblanca, H, Tsui, C, Vaccaro, D, Vallar, M, Van Berkel, M, Van Eester, D, Van Kampen, R, Van Mulders, S, Verhaegh, K, Verhaeghe, T, Vianello, N, Villone, F, Viezzer, E, Vincent, B, Voitsekhovitch, I, Vu, N, Walkden, N, Wauters, T, Weisen, H, Wendler, N, Wensing, M, Widmer, F, Wiesen, S, Wischmeier, M, Wijkamp, T, Wunderlich, D, Wuthrich, C, Yanovskiy, V, Zebrowski, J, Reimerdes H., Agostini M., Alessi E., Alberti S., Andrebe Y., Arnichand H., Balbin J., Bagnato F., Baquero-Ruiz M., Bernert M., Bin W., Blanchard P., Blanken T. C., Boedo J. A., Brida D., Brunner S., Bogar C., Bogar O., Bolzonella T., Bombarda F., Bouquey F., Bowman C., Brunetti D., Buermans J., Bufferand H., Calacci L., Camenen Y., Carli S., Carnevale D., Carpanese F., Causa F., Cavalier J., Cavedon M., Cazabonne J. A., Cerovsky J., Chandra R., Chandrarajan Jayalekshmi A., Chellai O., Chmielewski P., Choi D., Ciraolo G., Classen I. G. J., Coda S., Colandrea C., Dal Molin A., David P., De Baar M. R., Decker J., Dekeyser W., De Oliveira H., Douai D., Dreval M., Dunne M. G., Duval B. P., Elmore S., Embreus O., Eriksson F., Faitsch M., Falchetto G., Farnik M., Fasoli A., Fedorczak N., Felici F., Fevrier O., Ficker O., Fil A., Fontana M., Fransson E., Frassinetti L., Furno I., Gahle D. S., Galassi D., Galazka K., Galperti C., Garavaglia S., Garcia-Munoz M., Geiger B., Giacomin M., Giruzzi G., Gobbin M., Golfinopoulos T., Goodman T., Gorno S., Granucci G., Graves J. P., Griener M., Gruca M., Gyergyek T., Haelterman R., Hakola A., Han W., Happel T., Harrer G., Harrison J. R., Henderson S., Hogeweij G. M. D., Hogge J. -P., Hoppe M., Horacek J., Huang Z., Iantchenko A., Innocente P., Insulander Bjork K., Ionita-Schrittweiser C., Isliker H., Jardin A., Jaspers R. J. E., Karimov R., Karpushov A. N., Kazakov Y., Komm M., Kong M., Kovacic J., Krutkin O., Kudlacek O., Kumar U., Kwiatkowski R., Labit B., Laguardia L., Lammers J. T., Laribi E., Laszynska E., Lazaros A., Linder O., Linehan B., Lipschultz B., Llobet X., Loizu J., Lunt T., Macusova E., Marandet Y., Maraschek M., Marceca G., Marchetto C., Marchioni S., Marmar E. S., Martin Y., Martinelli L., Matos F., Maurizio R., Mayoral M. -L., Mazon D., Menkovski V., Merle A., Merlo G., Meyer H., Mikszuta-Michalik K., Molina Cabrera P. A., Morales J., Moret J. -M., Moro A., Moulton D., Muhammed H., Myatra O., Mykytchuk D., Napoli F., Nem R. D., Nielsen A. H., Nocente M., Nowak S., Offeddu N., Olsen J., Orsitto F. P., Pan O., Papp G., Pau A., Perek A., Pesamosca F., Peysson Y., Pigatto L., Piron C., Poradzinski M., Porte L., Putterich T., Rabinski M., Raj H., Rasmussen J. J., Ratta G. A., Ravensbergen T., Ricci D., Ricci P., Rispoli N., Riva F., Rivero-Rodriguez J. F., Salewski M., Sauter O., Schmidt B. S., Schrittweiser R., Sharapov S., Sheikh U. A., Sieglin B., Silva M., Smolders A., Snicker A., Sozzi C., Spolaore M., Stagni A., Stipani L., Sun G., Tala T., Tamain P., Tanaka K., Tema Biwole A., Terranova D., Terry J. L., Testa D., Theiler C., Thornton A., Thrysoe A., Torreblanca H., Tsui C. K., Vaccaro D., Vallar M., Van Berkel M., Van Eester D., Van Kampen R. J. R., Van Mulders S., Verhaegh K., Verhaeghe T., Vianello N., Villone F., Viezzer E., Vincent B., Voitsekhovitch I., Vu N. M. T., Walkden N., Wauters T., Weisen H., Wendler N., Wensing M., Widmer F., Wiesen S., Wischmeier M., Wijkamp T. A., Wunderlich D., Wuthrich C., Yanovskiy V., and Zebrowski J.

Abstract

The tokamak à configuration variable (TCV) continues to leverage its unique shaping capabilities, flexible heating systems and modern control system to address critical issues in preparation for ITER and a fusion power plant. For the 2019-20 campaign its configurational flexibility has been enhanced with the installation of removable divertor gas baffles, its diagnostic capabilities with an extensive set of upgrades and its heating systems with new dual frequency gyrotrons. The gas baffles reduce coupling between the divertor and the main chamber and allow for detailed investigations on the role of fuelling in general and, together with upgraded boundary diagnostics, test divertor and edge models in particular. The increased heating capabilities broaden the operational regime to include Te/Ti ∼1 and have stimulated refocussing studies from L-mode to H-mode across a range of research topics. ITER baseline parameters were reached in type-I ELMy H-modes and alternative regimes with 'small' (or no) ELMs explored. Most prominently, negative triangularity was investigated in detail and confirmed as an attractive scenario with H-mode level core confinement but an L-mode edge. Emphasis was also placed on control, where an increased number of observers, actuators and control solutions became available and are now integrated into a generic control framework as will be needed in future devices. The quantity and quality of results of the 2019-20 TCV campaign are a testament to its successful integration within the European research effort alongside a vibrant domestic programme and international collaborations.

Published
2022

12. Reduction in benefits of total flux expansion on divertor detachment due to parallel flows

Author

Carpita, M., Février, O., Reimerdes, H., Theiler, C., Duval, B. P., Colandrea, C., Durr-Legoupil-Nicoud, G., Galassi, D., Gorno, S., Huett, E., Loizu, J., Martinelli, L., Perek, A., Simons, L., Sun, G., Wüthrich, E. Tonello. C., and team, the TCV

Subjects
Plasma Physics (physics.plasm-ph), FOS: Physical sciences, Physics - Plasma Physics
Abstract

The Super-X divertor (SXD) is an alternative divertor configuration leveraging total flux expansion at the outer strike point (OSP). Key features for the attractiveness of the SXD are facilitated detachment access and control, as predicted by the extended 2-point model (2PM). However, parallel flows are not consistently included in the 2PM. In this work, the 2PM is refined to overcome this limitation: the role of total flux expansion on the pressure balance is made explicit, by including the effect of parallel flows. In consequence, the effect of total flux expansion on detachment access and control is weakened, compared to predictions of the 2PM. This new model partially explains discrepancies between the 2PM and experiments performed on TCV, in ohmic L-mode scenarios, where in core density ramps in lower single-null (SN) configuration, the impact of the OSP major radius Rt on the CIII emission front movement in the divertor outer leg - used as a proxy for the plasma temperature - is substantially weaker than 2PM predictions; and in OSP sweeps in lower and upper SN configurations, with a constant core density, the peak parallel particle flux density at the OSP is almost independent of Rt, while the 2PM predicts a linear dependence. Finally, analytical and numerical modelling of parallel flows in the divertor is presented, to support the argument. It is shown that an increase in total flux expansion can favour supersonic flows at the OSP. Parallel flows are also shown to be relevant by analysing SOLPS-ITER simulations of TCV.

Published
2023
Full Text
View/download PDF

13. Overview of the TCV tokamak experimental programme

Author

Reimerdes, H., Agostini, M., Alessi, E., Alberti, S., Andrebe, Y., Arnichand, H., Balbin, J., Bagnato, F., Baquero-Ruiz, M., Bernert, M., Bin, W., Blanchard, P., Blanken, T. C., Boedo, J. A., Brida, D., Brunner, S., Bogar, C., Bogar, O., Bolzonella, T., Bombarda, F., Bouquey, F., Bowman, C., Brunetti, D., Buermans, J., Bufferand, H., Calacci, L., Camenen, Y., Carli, S., Carnevale, D., Carpanese, F., Causa, F., Cavalier, J., Cavedon, M., Cazabonne, J. A., Cerovsky, J., Chandra, R., Chandrarajan Jayalekshmi, A., Chellaï, O., Chmielewski, P., Choi, D., Ciraolo, G., Classen, I.G.J., Coda, S., Colandrea, C., Dal Molin, A., David, P., de Baar, M.R., Decker, J., Dekeyser, W., De Oliveira, H., Douai, D., Dreval, M., Dunne, M. G., Duval, B. P., Elmore, S., Embreus, O., Eriksson, F., Faitsch, M., Falchetto, G., Farnik, M., Fasoli, A., Fedorczak, N., Felici, F., Février, O., Ficker, O., Fil, A., Fontana, M., Fransson, E., Frassinetti, L., Furno, I., Gahle, D. S., Galassi, D., Galazka, K., Galperti, C., Garavaglia, S., Garcia-Munoz, M., Geiger, B., Giacomin, M., Giruzzi, G., Gobbin, M., Golfinopoulos, T., Goodman, T., Gorno, S., Granucci, G., Graves, J. P., Griener, M., Gruca, M., Gyergyek, T., Haelterman, R., Hakola, A., Han, W., Happel, T., Harrer, G., Harrison, J. R., Henderson, S., Hogeweij, G. M.D., Hogge, J. P., Hoppe, M., Horacek, J., Huang, Z., Iantchenko, A., Innocente, P., Insulander Björk, K., Ionita-Schrittweiser, C., Isliker, H., Jardin, A., Jaspers, R.J.E., Karimov, R., Karpushov, A. N., Kazakov, Y., Komm, M., Kong, M., Kovacic, J., Krutkin, O., Kudlacek, O., Kumar, U., Kwiatkowski, R., Labit, B., Laguardia, L., Lammers, J.T., Laribi, E., Laszynska, E., Lazaros, A., Linder, O., Linehan, B., Lipschultz, B., Llobet, X., Loizu, J., Lunt, T., Macusova, E., Marandet, Y., Maraschek, M., Marceca, G., Marchetto, C., Marchioni, S., Marmar, E. S., Martin, Y., Martinelli, L., Matos, F., Maurizio, R., Mayoral, M. L., Mazon, D., Menkovski, V., Merle, A., Merlo, G., Meyer, H., Mikszuta-Michalik, K., Molina Cabrera, P. A., Morales, J., Moret, J. M., Moro, A., Moulton, D., Muhammed, H., Myatra, O., Mykytchuk, D., Napoli, F., Nem, R.D., Nielsen, A. H., Nocente, M., Nowak, S., Offeddu, N., Olsen, J., Orsitto, F. P., Pan, O., Papp, G., Pau, A., Perek, A., Pesamosca, F., Peysson, Y., Pigatto, L., Piron, C., Poradzinski, M., Porte, L., Pütterich, T., Rabinski, M., Raj, H., Rasmussen, J. J., Rattá, G. A., Ravensbergen, T., Ricci, D., Ricci, P., Rispoli, N., Riva, F., Rivero-Rodriguez, J. F., Salewski, M., Sauter, O., Schmidt, B. S., Schrittweiser, R., Sharapov, S., Sheikh, U. A., Sieglin, B., Silva, M., Smolders, A., Snicker, A., Sozzi, C., Spolaore, M., Stagni, A., Stipani, L., Sun, G., Tala, T., Tamain, P., Tanaka, K., Tema Biwole, A., Terranova, D., Terry, J. L., Testa, D., Theiler, C., Thornton, A., Thrysøe, A., Torreblanca, H., Tsui, C. K., Vaccaro, D., Vallar, M., van Berkel, M., Van Eester, D., van Kampen, R.J.R., van Mulders, S., Verhaegh, K., Verhaeghe, T., Vianello, N., Villone, F., Viezzer, E., Vincent, B., Voitsekhovitch, I., Vu, N. M.T., Walkden, N., Wauters, T., Weisen, H., Wendler, N., Wensing, M., Widmer, F., Wiesen, S., Wischmeier, M., Wijkamp, T.A., Wünderlich, D., Wüthrich, C., Yanovskiy, V., Zebrowski, J., Reimerdes, H., Agostini, M., Alessi, E., Alberti, S., Andrebe, Y., Arnichand, H., Balbin, J., Bagnato, F., Baquero-Ruiz, M., Bernert, M., Bin, W., Blanchard, P., Blanken, T. C., Boedo, J. A., Brida, D., Brunner, S., Bogar, C., Bogar, O., Bolzonella, T., Bombarda, F., Bouquey, F., Bowman, C., Brunetti, D., Buermans, J., Bufferand, H., Calacci, L., Camenen, Y., Carli, S., Carnevale, D., Carpanese, F., Causa, F., Cavalier, J., Cavedon, M., Cazabonne, J. A., Cerovsky, J., Chandra, R., Chandrarajan Jayalekshmi, A., Chellaï, O., Chmielewski, P., Choi, D., Ciraolo, G., Classen, I.G.J., Coda, S., Colandrea, C., Dal Molin, A., David, P., de Baar, M.R., Decker, J., Dekeyser, W., De Oliveira, H., Douai, D., Dreval, M., Dunne, M. G., Duval, B. P., Elmore, S., Embreus, O., Eriksson, F., Faitsch, M., Falchetto, G., Farnik, M., Fasoli, A., Fedorczak, N., Felici, F., Février, O., Ficker, O., Fil, A., Fontana, M., Fransson, E., Frassinetti, L., Furno, I., Gahle, D. S., Galassi, D., Galazka, K., Galperti, C., Garavaglia, S., Garcia-Munoz, M., Geiger, B., Giacomin, M., Giruzzi, G., Gobbin, M., Golfinopoulos, T., Goodman, T., Gorno, S., Granucci, G., Graves, J. P., Griener, M., Gruca, M., Gyergyek, T., Haelterman, R., Hakola, A., Han, W., Happel, T., Harrer, G., Harrison, J. R., Henderson, S., Hogeweij, G. M.D., Hogge, J. P., Hoppe, M., Horacek, J., Huang, Z., Iantchenko, A., Innocente, P., Insulander Björk, K., Ionita-Schrittweiser, C., Isliker, H., Jardin, A., Jaspers, R.J.E., Karimov, R., Karpushov, A. N., Kazakov, Y., Komm, M., Kong, M., Kovacic, J., Krutkin, O., Kudlacek, O., Kumar, U., Kwiatkowski, R., Labit, B., Laguardia, L., Lammers, J.T., Laribi, E., Laszynska, E., Lazaros, A., Linder, O., Linehan, B., Lipschultz, B., Llobet, X., Loizu, J., Lunt, T., Macusova, E., Marandet, Y., Maraschek, M., Marceca, G., Marchetto, C., Marchioni, S., Marmar, E. S., Martin, Y., Martinelli, L., Matos, F., Maurizio, R., Mayoral, M. L., Mazon, D., Menkovski, V., Merle, A., Merlo, G., Meyer, H., Mikszuta-Michalik, K., Molina Cabrera, P. A., Morales, J., Moret, J. M., Moro, A., Moulton, D., Muhammed, H., Myatra, O., Mykytchuk, D., Napoli, F., Nem, R.D., Nielsen, A. H., Nocente, M., Nowak, S., Offeddu, N., Olsen, J., Orsitto, F. P., Pan, O., Papp, G., Pau, A., Perek, A., Pesamosca, F., Peysson, Y., Pigatto, L., Piron, C., Poradzinski, M., Porte, L., Pütterich, T., Rabinski, M., Raj, H., Rasmussen, J. J., Rattá, G. A., Ravensbergen, T., Ricci, D., Ricci, P., Rispoli, N., Riva, F., Rivero-Rodriguez, J. F., Salewski, M., Sauter, O., Schmidt, B. S., Schrittweiser, R., Sharapov, S., Sheikh, U. A., Sieglin, B., Silva, M., Smolders, A., Snicker, A., Sozzi, C., Spolaore, M., Stagni, A., Stipani, L., Sun, G., Tala, T., Tamain, P., Tanaka, K., Tema Biwole, A., Terranova, D., Terry, J. L., Testa, D., Theiler, C., Thornton, A., Thrysøe, A., Torreblanca, H., Tsui, C. K., Vaccaro, D., Vallar, M., van Berkel, M., Van Eester, D., van Kampen, R.J.R., van Mulders, S., Verhaegh, K., Verhaeghe, T., Vianello, N., Villone, F., Viezzer, E., Vincent, B., Voitsekhovitch, I., Vu, N. M.T., Walkden, N., Wauters, T., Weisen, H., Wendler, N., Wensing, M., Widmer, F., Wiesen, S., Wischmeier, M., Wijkamp, T.A., Wünderlich, D., Wüthrich, C., Yanovskiy, V., and Zebrowski, J.

Abstract

The tokamak à configuration variable (TCV) continues to leverage its unique shaping capabilities, flexible heating systems and modern control system to address critical issues in preparation for ITER and a fusion power plant. For the 2019-20 campaign its configurational flexibility has been enhanced with the installation of removable divertor gas baffles, its diagnostic capabilities with an extensive set of upgrades and its heating systems with new dual frequency gyrotrons. The gas baffles reduce coupling between the divertor and the main chamber and allow for detailed investigations on the role of fuelling in general and, together with upgraded boundary diagnostics, test divertor and edge models in particular. The increased heating capabilities broaden the operational regime to include Te/Ti ∼1 and have stimulated refocussing studies from L-mode to H-mode across a range of research topics. ITER baseline parameters were reached in type-I ELMy H-modes and alternative regimes with 'small' (or no) ELMs explored. Most prominently, negative triangularity was investigated in detail and confirmed as an attractive scenario with H-mode level core confinement but an L-mode edge. Emphasis was also placed on control, where an increased number of observers, actuators and control solutions became available and are now integrated into a generic control framework as will be needed in future devices. The quantity and quality of results of the 2019-20 TCV campaign are a testament to its successful integration within the European research effort alongside a vibrant domestic programme and international collaborations.

Published
2022

14. Validation of edge turbulence codes against the TCV-X21 diverted L-mode reference case

Author

Oliveira, D. S., Body, T., Galassi, D., Theiler, C., Laribi, E., Tamain, P., Stegmeir, A., Giacomin, M., Zholobenko, W., Ricci, P., Bufferand, H., Boedo, J. A., Ciraolo, G., Colandrea, C., Coster, D., De Oliveira, H., Fourestey, G., Gorno, S., Imbeaux, F., Jenko, F., Naulin, V., Offeddu, N., Reimerdes, H., Serre, E., Tsui, C. K., Varini, N., Vianello, N., Wiesenberger, M., Wüthrich, C., Oliveira, D. S., Body, T., Galassi, D., Theiler, C., Laribi, E., Tamain, P., Stegmeir, A., Giacomin, M., Zholobenko, W., Ricci, P., Bufferand, H., Boedo, J. A., Ciraolo, G., Colandrea, C., Coster, D., De Oliveira, H., Fourestey, G., Gorno, S., Imbeaux, F., Jenko, F., Naulin, V., Offeddu, N., Reimerdes, H., Serre, E., Tsui, C. K., Varini, N., Vianello, N., Wiesenberger, M., and Wüthrich, C.

Abstract

Self-consistent full-size turbulent-transport simulations of the divertor and scrape-off-layer (SOL) of existing tokamaks have recently become feasible. This enables the direct comparison of turbulence simulations against experimental measurements. In this work, we perform a series of diverted ohmic L-mode discharges on the tokamak à configuration variable (TCV) tokamak, building a first-of-a-kind dataset for the validation of edge turbulence models. This dataset, referred to as TCV-X21, contains measurements from five diagnostic systems from the outboard midplane (OMP) to the divertor targets - giving a total of 45 one- and two-dimensional comparison observables in two toroidal magnetic field directions. The experimental dataset is used to validate three flux-driven 3D fluid-turbulence models - GBS, GRILLIX and TOKAM3X. With each model, we perform simulations of the TCV-X21 scenario, individually tuning the particle and power source rates to achieve a reasonable match of the upstream separatrix value of density and electron temperature. We find that the simulations match the experimental profiles for most observables at the OMP - both in terms of profile shape and absolute magnitude - while a comparatively poorer agreement is found towards the divertor targets. The match between simulation and experiment is seen to be sensitive to the value of the resistivity, the heat conductivities, the power injection rate and the choice of sheath boundary conditions. Additionally, despite targeting a sheath-limited regime, the discrepancy between simulations and experiment also suggests that the neutral dynamics should be included. The results of this validation show that turbulence models are able to perform simulations of existing devices and achieve reasonable agreement with experimental measurements. Where disagreement is found, the validation helps to identify how the models can be improved. By publicly releasing the experimental dataset and validation analysis, this wo

Published
2022

15. Overview of the TCV tokamak experimental programme

Author

Reimerdes, H. Agostini, M. Alessi, E. Alberti, S. and Andrebe, Y. Arnichand, H. Balbin, J. Bagnato, F. and Baquero-Ruiz, M. Bernert, M. Bin, W. Blanchard, P. and Blanken, T. C. Boedo, J. A. Brida, D. Brunner, S. Bogar, C. Bogar, O. Bolzonella, T. Bombarda, F. Bouquey, F. and Bowman, C. Brunetti, D. Buermans, J. Bufferand, H. and Calacci, L. Camenen, Y. Carli, S. Carnevale, D. and Carpanese, F. Causa, F. Cavalier, J. Cavedon, M. and Cazabonne, J. A. Cerovsky, J. Chandra, R. Jayalekshmi, A. Chandrarajan Chellai, O. Chmielewski, P. Choi, D. and Ciraolo, G. Classen, I. G. J. Coda, S. Colandrea, C. Dal Molin, A. David, P. de Baar, M. R. Decker, J. Dekeyser, W. de Oliveira, H. Douai, D. Dreval, M. Dunne, M. G. and Duval, B. P. Elmore, S. Embreus, O. Eriksson, F. and Faitsch, M. Falchetto, G. Farnik, M. Fasoli, A. and Fedorczak, N. Felici, F. Fevrier, O. Ficker, O. Fil, A. and Fontana, M. Fransson, E. Frassinetti, L. Furno, I and Gahle, D. S. Galassi, D. Galazka, K. Galperti, C. and Garavaglia, S. Garcia-Munoz, M. Geiger, B. Giacomin, M. and Giruzzi, G. Gobbin, M. Golfinopoulos, T. Goodman, T. and Gorno, S. Granucci, G. Graves, J. P. Griener, M. Gruca, M. Gyergyek, T. Haelterman, R. Hakola, A. Han, W. and Happel, T. Harrer, G. Harrison, J. R. Henderson, S. and Hogeweij, G. M. D. Hogge, J-P Hoppe, M. Horacek, J. and Huang, Z. Iantchenko, A. Innocente, P. Bjork, K. Insulander and Ionita-Schrittweiser, C. Isliker, H. Jardin, A. Jaspers, R. J. E. Karimov, R. Karpushov, A. N. Kazakov, Y. Komm, M. Kong, M. Kovacic, J. Krutkin, O. Kudlacek, O. and Kumar, U. Kwiatkowski, R. Labit, B. Laguardia, L. and Lammers, J. T. Laribi, E. Laszynska, E. Lazaros, A. and Linder, O. Linehan, B. Lipschultz, B. Llobet, X. Loizu, J. Lunt, T. Macusova, E. Marandet, Y. Maraschek, M. and Marceca, G. Marchetto, C. Marchioni, S. Marmar, E. S. and Martin, Y. Martinelli, L. Matos, F. Maurizio, R. and Mayoral, M-L Mazon, D. Menkovski, V Merle, A. Merlo, G. and Meyer, H. Mikszuta-Michalik, K. Cabrera, P. A. Molina and Morales, J. Moret, J-M Moro, A. Moulton, D. Muhammed, H. and Myatra, O. Mykytchuk, D. Napoli, F. Nem, R. D. and Nielsen, A. H. Nocente, M. Nowak, S. Offeddu, N. Olsen, J. Orsitto, F. P. Pan, O. Papp, G. Pau, A. Perek, A. and Pesamosca, F. Peysson, Y. Pigatto, L. Piron, C. and Poradzinski, M. Porte, L. Putterich, T. Rabinski, M. and Raj, H. Rasmussen, J. J. Ratta, G. A. Ravensbergen, T. and Ricci, D. Ricci, P. Rispoli, N. Riva, F. and Rivero-Rodriguez, J. F. Salewski, M. Sauter, O. Schmidt, B. S. Schrittweiser, R. Sharapov, S. Sheikh, U. A. Sieglin, B. Silva, M. Smolders, A. Snicker, A. Sozzi, C. and Spolaore, M. Stagni, A. Stipani, L. Sun, G. Tala, T. and Tamain, P. Tanaka, K. Biwole, A. Tema Terranova, D. and Terry, J. L. Testa, D. Theiler, C. Thornton, A. Thrysoe, A. Torreblanca, H. Tsui, C. K. Vaccaro, D. Vallar, M. and van Berkel, M. Van Eester, D. van Kampen, R. J. R. Van Mulders, S. Verhaegh, K. Verhaeghe, T. Vianello, N. and Villone, F. Viezzer, E. Vincent, B. Voitsekhovitch, I and Vu, N. M. T. Walkden, N. Wauters, T. Weisen, H. Wendler, N. Wensing, M. Widmer, F. Wiesen, S. Wischmeier, M. and Wijkamp, T. A. Wunderlich, D. Wuthrich, C. Yanovskiy, V and Zebrowski, J. EUROfusion MST1 Team

Abstract

The tokamak a configuration variable (TCV) continues to leverage its unique shaping capabilities, flexible heating systems and modern control system to address critical issues in preparation for ITER and a fusion power plant. For the 2019-20 campaign its configurational flexibility has been enhanced with the installation of removable divertor gas baffles, its diagnostic capabilities with an extensive set of upgrades and its heating systems with new dual frequency gyrotrons. The gas baffles reduce coupling between the divertor and the main chamber and allow for detailed investigations on the role of fuelling in general and, together with upgraded boundary diagnostics, test divertor and edge models in particular. The increased heating capabilities broaden the operational regime to include T (e)/T (i) similar to 1 and have stimulated refocussing studies from L-mode to H-mode across a range of research topics. ITER baseline parameters were reached in type-I ELMy H-modes and alternative regimes with `small' (or no) ELMs explored. Most prominently, negative triangularity was investigated in detail and confirmed as an attractive scenario with H-mode level core confinement but an L-mode edge. Emphasis was also placed on control, where an increased number of observers, actuators and control solutions became available and are now integrated into a generic control framework as will be needed in future devices. The quantity and quality of results of the 2019-20 TCV campaign are a testament to its successful integration within the European research effort alongside a vibrant domestic programme and international collaborations.

Published
2022

16. Improved heat and particle flux mitigation in high core confinement, baffled, alternative divertor configurations in the TCV tokamak

Author

Raj, H., Theiler, C., Thornton, A., Février, O., Gorno, S., Bagnato, F., Blanchard, P., Colandrea, C., de Oliveira, H., Perek, A., Duval, B.P., Labit, B., Reimerdes, H., Sheikh, U., Vallar, M., Vincent, B., team, TCV, and Team, EUROfusionMST1

Subjects
Nuclear and High Energy Physics, langmuir probes, geometry, divertor heat load mitigation, FOS: Physical sciences, Condensed Matter Physics, h-mode, Physics - Plasma Physics, Plasma Physics (physics.plasm-ph), power, high confinement, advanced divertor configurations, detachment, baffles, tokamak
Abstract

Nitrogen seeded detachment has been achieved in the tokamak a configuration variable (TCV) in alternative divertor configurations (ADCs), namely X-divertor and X-point target, with and without baffles in H-mode plasmas with high core confinement. Both ADCs show a remarkable reduction in the inter-ELM particle and heat fluxes to the target compared to the standard divertor configuration. 95%–98% of the inter-ELM peak heat flux to the target is mitigated as a synergetic effect of ADCs, baffling, and nitrogen seeded detachment. The effect of divertor geometry and baffles on core-divertor compatibility is investigated in detail. The power balance in these experiments is also investigated to explore the physics behind the observed reduction in heat fluxes in the ADCs.

Published
2022

17. Validation of 2D Te and ne measurements made with Helium imaging spectroscopy in the volume of the TCV divertor

Author

Linehan, B., Perek, A., Duval, B.P., Bagnato, F., Blanchard, P., Colandrea, C., de Oliveira, H., Février, O., Flom, E., Wijkamp, T., Gorno, S., Goto, M., Marmar, S., Martinelli, L., Mathews, A., Munoz-Burgos, J.M., Mykytchuk, D., Offeddu, N., Oliveira, D.S., Reimerdes, H., Reiter, D., Schmitz, O., Terry, J.L., Theiler, C., Tsui, C.K., Vincent, B., Wuthrich, C., Zholobenko, W., team, TCV, and TCV Team

Subjects
Nuclear and High Energy Physics, Condensed Matter Physics
Abstract

Multi-spectral imaging of helium atomic emission (HeMSI) has been used to create 2D poloidal maps of T e and n e in TCV’s divertor. To achieve these measurements, TCV’s MANTIS multispectral cameras (Perek et al 2019 Rev. Sci. Instrum. 90 123514) simultaneously imaged four He I lines (two singlet and two triplet) and a He II line (468 nm) from passively present He and He+. The images, which were absolutely calibrated and covered the whole divertor region, were inverted through the assumption of toroidal symmetry to create emissivity profiles and, consequently, line-ratio profiles. A collisional-radiative model (CRM) was applied to the line-ratio profiles to produce 2D poloidal maps of T e and n e . The collisional-radiative modeling was accomplished with the Goto helium CRM code (Zholobenko et al 2018 Nucl. Fusion 58 126006, Zholobenko et al 2018 Technical Report, Goto 2003 J. Quant. Spectrosc. Radiat. Transfer 76 331–44) which accounts for electron-impact excitation (EIE) and deexcitation, and electron–ion recombination (EIR) with He + . The HeMSI T e and n e measurements were compared with co-local Thomson scattering measurements. The two sets of measurements exhibited good agreement for ionizing plasmas: ( 5 eV ⩽ T e ⩽ 60 eV , and 2 × 10 18 m − 3 ⩽ n e ⩽ 3 × 10 19 m − 3 ) in the case of majority helium plasmas, and ( 10 eV ⩽ T e ⩽ 40 eV , 2 × 10 18 m − 3 ⩽ n e ⩽ 3 × 10 19 m − 3 ) in the case of majority deuterium plasmas. However, there were instances where HeMSI measurements diverged from Thomson scattering. When T e ⩽ 10 eV in majority deuterium plasmas, HeMSI deduced inaccurately high values of T e . This disagreement cannot be rectified within the CRM’s EIE and EIR framework. Second, on sporadic occasions within the private flux region, HeMSI produced erroneously high measurements of n e . Multi-spectral imaging of Helium emission has been demonstrated to produce accurate 2D poloidal maps of T e and n e within the divertor of a tokamak for plasma conditions relevant to contemporary divertor studies.

Published
2023

18. Divertor closure effects on the TCV boundary plasma

Author

Février, O., Reimerdes, H., Theiler, C., Brida, D., Colandrea, C., de Oliveira, H., Duval, B.P., Galassi, D., Gorno, S., Perek, A., Henderson, S., Komm, M., Labit, B., Linehan, B., Martinelli, L., Raj, H., Sheikh, H., Tsui, C.K., Wensing, M., team, TCV, Team, EUROfusionMST1, TCV Team, EUROfusion MST1 Team, and Science and Technology of Nuclear Fusion

Subjects
Nuclear and High Energy Physics, Tokamak, Materials science, Materials Science (miscellaneous), Divertor, TK9001-9401, Front (oceanography), Baffle, Mechanics, Plasma, 01 natural sciences, 010305 fluids & plasmas, law.invention, Core (optical fiber), Gas baffle, Nuclear Energy and Engineering, Closure (computer programming), law, detachment, 0103 physical sciences, Nuclear engineering. Atomic power, Tokamak à configuration variable, 010306 general physics
Abstract

The Tokamak a Configuration Variable (TCV) has recently been equipped with gas baffles to increase its divertor closure for a broad range of divertor magnetic geometries. First experimental results reported in Reimerdes et al. (2021) demonstrated compatibility with a broad range of divertor magnetic geometries and confirmed the main design constraints of the baffles, in particular an increased divertor neutral pressure. The present article presents a more in-depths analysis and extended experiments of this first baffle assessment on the TCV boundary plasma. It is shown that the divertor neutral pressure increased following the installation of the baffles, as predicted by SOLPS-ITER and SolEdge2D-EIRENE simulations. Varying the divertor closure by changing the position of the plasma showed that the plasma equilibrium designed to assess the baffle effect was not far from the optimal trade-off between plasma plugging and recycling on the baffles. The baffles facilitate access to a partially detached regime in both L- and H-modes. In L-Mode, with the ion ∇ B -drift directed from the X-Point to the plasma core, a reduction of the line-averaged density detachment threshold by approximately 20% is observed at the outer target, while inner strike point detachment is only achieved in the presence of baffles. Multispectral imaging shows that the CIII front moves from the outer target towards the X-Point at a lower line-averaged plasma density, indicating a colder outer leg. In H-mode, the CIII front is generally located near the X-Point between the ELMs, while without baffles, N 2 -seeding is required to move the front up to that location.

Published
2021

19. SOLPS-ITER validation with TCV L-mode discharges editors-pick

Author

Wensing, M., Reimerdes, H., Fevrier, O., Colandrea, C., Martinelli, L., Verhaegh, K., Bagnato, F., Blanchard, P., Vincent, B., Perek, A., Gorno, S., de Oliveira, H., Theiler, C., Duval, B., Tsui, C., Baquero-Ruiz, M., Wischmeier, M., TCV Team, and EUROfusion MST1 Team

Published
2021

20. Experimental verification of X-point potential well formation in unfavorable magnetic field direction

Author

Wensing, M., primary, de Oliveira, H., additional, Loizu, J., additional, Colandrea, C., additional, Février, O., additional, Gorno, S., additional, Reimerdes, H., additional, Theiler, C., additional, Smolders, A., additional, Duval, B.P., additional, Tsui, C.K., additional, Wischmeier, M., additional, Brida, D., additional, Henderson, S., additional, and Komm, M., additional

Published
2020
Full Text
View/download PDF

21. Detachment in conventional and advanced double-null plasmas in TCV

Author

Fevrier, O., Theiler, C., Coda, S., Colandrea, C., de Oliveira, H., Duval, B. P., Gorno, S., Labit, B., Linehan, B., Maurizio, R., Perek, A., Reimerdes, H., and Wuthrich, C.

Subjects
power, power exhaust, detachment, design, divertor, double-null, performance
Abstract

Divertor detachment is investigated on the Tokamak a Configuration Variable (TCV) for conventional and alternative double-null (DN) magnetic geometries in L-mode, Ohmic density ramps and then compared to precisely matched single-null (SN) geometries. The poloidal flux expansion at the outer strikepoint(s) is varied by a factor 2 and the total flux expansion by 30% in lower single null (LSN) and DN configurations. Leg power sharing for DN and near-DN in attached conditions is in line with previous studies in other devices, with balanced power partition between upper and lower divertor achieved for vertical bar delta R-sep vertical bar less than or similar to lambda (q) /2. This results in a reduction in the lower outer target integral and peak heat flux compared to a LSN by 30%. Unlike previous studies, lambda (q) is fairly insensitive to delta R-sep. The detachment threshold in these geometries is investigated from target measurements with wall-embedded Langmuir probes and two-dimensional CIII line emissivity profiles across the two divertor regions. DN plasmas display clear benefits compared to their LSN counterparts. Transitioning from a LSN to DN shows a substantial reduction, of approx. 20%-25%, in the detachment threshold for the active divertor legs as well as a 50% higher radiated fraction at all < n(e)>. The density limit is simultaneously reduced in DN by 10%-20%. Across the explored range, poloidal flux expansion has only a small effect on the detachment threshold in LSN (as seen in previous experiments), and no effect in DN, with similar observations for the total flux expansion. In general, no strong benefits of increased poloidal or total flux expansion are observed across the explored range.

22. Estimating cross-field particle transport at the outer midplane of TCV by tracking filaments with machine learning

Author

Han, W., Offeddu, N., Golfinopoulos, T., Theiler, C., Terry, J. L., Wuthrich, C., Galassi, D., Colandrea, C., and Marmar, E. S.

Subjects
gas puff imaging, machine learning, particle transport, edge/sol turbulence, scrape-off-layer, turbulence, edge, tokamak, negative triangularity
Abstract

Cross-field transport of particles in the boundary region of magnetically confined fusion plasmas is dominated by turbulence. Blobs, intermittent turbulent structures with large amplitude and a filamentary shape appearing in the scrape-off layer (SOL), are known from theoretical and experimental studies to be the main contributor to the cross-field particle transport. The dynamics of blobs differs depending on various plasma conditions, including triangularity (d). In this work, we analyze triangularity dependence of the cross-field particle transport at the outer midplane of plasmas with d = +0.38, +0.15, -0.14, and -0.26 on the Tokamak a` Configuration Variable, using our novel machine learning (ML) blob-tracking approach applied to gas puff imaging data. The cross-field particle flux determined in this way is of the same order as the overall transport inferred from KN1D, GBS, and SOLPS-ITER simulations, suggesting that the blobs identified by the ML blob-tracking account for most of the cross-field particle transport in the SOL. Also, the ML blob-tracking and KN1D show a decrease in the cross-field particle transport as d becomes more negative. The blob-by-blob analysis of the result from the tracking reveals that the decrease of cross-field particle transport with decreasing d is accompanied by a decrease in the number of blobs in a fixed time, which tend to have larger area and lower radial speed. Also, the blobs in these plasmas are in the connected sheath regime, and show a velocity scaling consistent with the two-region model.

23. Relevance of E x B drifts for particle and heat transport in divertors

Author

Tsui, C. K., Boedo, J. A., Fevrier, O., Reimerdes, H., Colandrea, C., and Gorno, S.

Subjects
power, diii-d, scrape-off layer, divertor, tcv, tokamaks, tokamak, target asymmetry, electric-fields
Abstract

Radial electric fields up to similar to 4 kV m(-1) are observed in the boundary between the private flux region (PFR) and the scrape-off layer (SOL) driving E X B drifts between the inner and outer targets at speeds up to 2.8 km s(-1) in the Tokamak a configuration variable divertor. The resulting E X B fluxes, located in a narrow region (Delta(rho psi) < 0.012 in normalized radius or Delta R - R-sep < 4 mm mapped to the outer midplane) are equivalent to around 20% of the total heat and particle flux to the divertor targets (inner + outer). At the peak E-r, the E X B poloidal transport is equivalent to parallel flows with M-parallel to similar to 3. In the snowflake divertor with a second X-point in the outer SOL, the drifts in the PFR-SOL boundary were equivalent to around 30% of the total heat and particle flux to the divertor targets and cover a region similar to 50% wider than in the single null (Delta(rho psi) similar to 0.018, Delta R - R-sep similar to 6 mm). The location of the PFR-SOL boundary drift shifts radially in the E-parallel to x B direction when reversing the toroidal field direction. Peaks in density and electron pressure have been identified near the primary X-point along with large gradients in density, temperature, and potential, the latter resulting in a local electric field similar to 2.7 kV m(-1) which drives a drift (1.9 km s(-1)) upwards towards the closed flux surfaces. Floating potential (V-f) magnitudes up to 75 V (similar to 2 kT(e)) were measured, indicating that V-f and parallel currents should not be neglected when estimating plasma potential.

24. Validation of 2D T e and n e measurements made with Helium imaging spectroscopy in the volume of the TCV divertor

Author

Linehan, B. L., Perek, A., Duval, B. P., Bagnato, F., Blanchard, P., Colandrea, C., De Oliveira, H., Fevrier, O., Flom, E., Gorno, S., Goto, M., Marmar, E., Martinelli, L., Mathews, A., Munoz-Burgos, J., Mykytchuk, D., Offeddu, N., Oliveira, D. S., Reimerdes, H., Reiter, D., Schmitz, O., Terry, J. L., Theiler, C., Tsui, C. K., Vincent, B., Wijkamp, T., Wuethrich, C., and Zholobenko, W.

Subjects
helium collisional radiative modeling, density, scrape-off layer, tokamak divertor, edge, multi-spectral imaging, plasma boundary physics, plasmas, populations, recombination, tokamak diagnostics, neutral helium, electron-temperature, collisional-radiative model, divertor, tcv, implementation
Abstract

Multi-spectral imaging of helium atomic emission (HeMSI) has been used to create 2D poloidal maps of T-e and ne in TCV's divertor. To achieve these measurements, TCV's MANTIS multispectral cameras (Perek et al 2019 Rev. Sci. Instrum. 90 123514) simultaneously imaged four He I lines (two singlet and two triplet) and a He II line (468 nm) from passively present He and He+. The images, which were absolutely calibrated and covered the whole divertor region, were inverted through the assumption of toroidal symmetry to create emissivity profiles and, consequently, line-ratio profiles. A collisional-radiative model (CRM) was applied to the line-ratio profiles to produce 2D poloidal maps of Te and ne. The collisional-radiative modeling was accomplished with the Goto helium CRM code (Zholobenko et al 2018 Nucl. Fusion 58 126006, Zholobenko et al 2018 Technical Report, Goto 2003 J. Quant. Spectrosc. Radiat. Transfer 76 331-44) which accounts for electron-impact excitation (EIE) and deexcitation, and electron-ion recombination (EIR) with He+. The HeMSI T-e and ne measurements were compared with co-local Thomson scattering measurements. The two sets of measurements exhibited good agreement for ionizing plasmas: (5 eV 5 T-e 5 60 eV, and 2 x 10(18)m(-3) 5 ne 5 3 x 1019m(-3)) in the case of majority helium plasmas, and (10 eV 5 T-e 5 40 eV, 2 x 1018m-3 5 ne 5 3 x 10(19)m(-3)) in the case of majority deuterium plasmas. However, there were instances where HeMSI measurements diverged from Thomson scattering. When T-e 5 10 eV in majority deuterium plasmas, HeMSI deduced inaccurately high values of T-e. This disagreement cannot be rectified within the CRM's EIE and EIR framework. Second, on sporadic occasions within the private flux region, HeMSI produced erroneously high measurements of ne. Multi-spectral imaging of Helium emission has been demonstrated to produce accurate 2D poloidal maps of Te and ne within the divertor of a tokamak for plasma conditions relevant to contemporary divertor studies.

26. Overview of the TCV tokamak experimental programme

Author

H. Reimerdes, M. Agostini, E. Alessi, S. Alberti, Y. Andrebe, H. Arnichand, J. Balbin, F. Bagnato, M. Baquero-Ruiz, M. Bernert, W. Bin, P. Blanchard, T.C. Blanken, J.A. Boedo, D. Brida, S. Brunner, C. Bogar, O. Bogar, T. Bolzonella, F. Bombarda, F. Bouquey, C. Bowman, D. Brunetti, J. Buermans, H. Bufferand, L. Calacci, Y. Camenen, S. Carli, D. Carnevale, F. Carpanese, F. Causa, J. Cavalier, M. Cavedon, J.A. Cazabonne, J. Cerovsky, R. Chandra, A. Chandrarajan Jayalekshmi, O. Chellaï, P. Chmielewski, D. Choi, G. Ciraolo, I.G.J. Classen, S. Coda, C. Colandrea, A. Dal Molin, P. David, M.R. de Baar, J. Decker, W. Dekeyser, H. de Oliveira, D. Douai, M. Dreval, M.G. Dunne, B.P. Duval, S. Elmore, O. Embreus, F. Eriksson, M. Faitsch, G. Falchetto, M. Farnik, A. Fasoli, N. Fedorczak, F. Felici, O. Février, O. Ficker, A. Fil, M. Fontana, E. Fransson, L. Frassinetti, I. Furno, D.S. Gahle, D. Galassi, K. Galazka, C. Galperti, S. Garavaglia, M. Garcia-Munoz, B. Geiger, M. Giacomin, G. Giruzzi, M. Gobbin, T. Golfinopoulos, T. Goodman, S. Gorno, G. Granucci, J.P. Graves, M. Griener, M. Gruca, T. Gyergyek, R. Haelterman, A. Hakola, W. Han, T. Happel, G. Harrer, J.R. Harrison, S. Henderson, G.M.D. Hogeweij, J.-P. Hogge, M. Hoppe, J. Horacek, Z. Huang, A. Iantchenko, P. Innocente, K. Insulander Björk, C. Ionita-Schrittweiser, H. Isliker, A. Jardin, R.J.E. Jaspers, R. Karimov, A.N. Karpushov, Y. Kazakov, M. Komm, M. Kong, J. Kovacic, O. Krutkin, O. Kudlacek, U. Kumar, R. Kwiatkowski, B. Labit, L. Laguardia, J.T. Lammers, E. Laribi, E. Laszynska, A. Lazaros, O. Linder, B. Linehan, B. Lipschultz, X. Llobet, J. Loizu, T. Lunt, E. Macusova, Y. Marandet, M. Maraschek, G. Marceca, C. Marchetto, S. Marchioni, E.S. Marmar, Y. Martin, L. Martinelli, F. Matos, R. Maurizio, M.-L. Mayoral, D. Mazon, V. Menkovski, A. Merle, G. Merlo, H. Meyer, K. Mikszuta-Michalik, P.A. Molina Cabrera, J. Morales, J.-M. Moret, A. Moro, D. Moulton, H. Muhammed, O. Myatra, D. Mykytchuk, F. Napoli, R.D. Nem, A.H. Nielsen, M. Nocente, S. Nowak, N. Offeddu, J. Olsen, F.P. Orsitto, O. Pan, G. Papp, A. Pau, A. Perek, F. Pesamosca, Y. Peysson, L. Pigatto, C. Piron, M. Poradzinski, L. Porte, T. Pütterich, M. Rabinski, H. Raj, J.J. Rasmussen, G.A. Rattá, T. Ravensbergen, D. Ricci, P. Ricci, N. Rispoli, F. Riva, J.F. Rivero-Rodriguez, M. Salewski, O. Sauter, B.S. Schmidt, R. Schrittweiser, S. Sharapov, U.A. Sheikh, B. Sieglin, M. Silva, A. Smolders, A. Snicker, C. Sozzi, M. Spolaore, A. Stagni, L. Stipani, G. Sun, T. Tala, P. Tamain, K. Tanaka, A. Tema Biwole, D. Terranova, J.L. Terry, D. Testa, C. Theiler, A. Thornton, A. Thrysøe, H. Torreblanca, C.K. Tsui, D. Vaccaro, M. Vallar, M. van Berkel, D. Van Eester, R.J.R. van Kampen, S. Van Mulders, K. Verhaegh, T. Verhaeghe, N. Vianello, F. Villone, E. Viezzer, B. Vincent, I. Voitsekhovitch, N.M.T. Vu, N. Walkden, T. Wauters, H. Weisen, N. Wendler, M. Wensing, F. Widmer, S. Wiesen, M. Wischmeier, T.A. Wijkamp, D. Wünderlich, C. Wüthrich, V. Yanovskiy, J. Zebrowski, the EUROfusion MST1 Team, EUROfusion MST1 Team, Control Systems Technology, Liquid metal heat shields, Science and Technology of Nuclear Fusion, Group Heemels, Mechanical Engineering, Data Mining, EAISI Health, ICMS Affiliated, EAISI High Tech Systems, Applied Physics and Science Education, Reimerdes, H, Agostini, M, Alessi, E, Alberti, S, Andrebe, Y, Arnichand, H, Balbin, J, Bagnato, F, Baquero-Ruiz, M, Bernert, M, Bin, W, Blanchard, P, Blanken, T, Boedo, J, Brida, D, Brunner, S, Bogar, C, Bogar, O, Bolzonella, T, Bombarda, F, Bouquey, F, Bowman, C, Brunetti, D, Buermans, J, Bufferand, H, Calacci, L, Camenen, Y, Carli, S, Carnevale, D, Carpanese, F, Causa, F, Cavalier, J, Cavedon, M, Cazabonne, J, Cerovsky, J, Chandra, R, Chandrarajan Jayalekshmi, A, Chellai, O, Chmielewski, P, Choi, D, Ciraolo, G, Classen, I, Coda, S, Colandrea, C, Dal Molin, A, David, P, De Baar, M, Decker, J, Dekeyser, W, De Oliveira, H, Douai, D, Dreval, M, Dunne, M, Duval, B, Elmore, S, Embreus, O, Eriksson, F, Faitsch, M, Falchetto, G, Farnik, M, Fasoli, A, Fedorczak, N, Felici, F, Fevrier, O, Ficker, O, Fil, A, Fontana, M, Fransson, E, Frassinetti, L, Furno, I, Gahle, D, Galassi, D, Galazka, K, Galperti, C, Garavaglia, S, Garcia-Munoz, M, Geiger, B, Giacomin, M, Giruzzi, G, Gobbin, M, Golfinopoulos, T, Goodman, T, Gorno, S, Granucci, G, Graves, J, Griener, M, Gruca, M, Gyergyek, T, Haelterman, R, Hakola, A, Han, W, Happel, T, Harrer, G, Harrison, J, Henderson, S, Hogeweij, G, Hogge, J, Hoppe, M, Horacek, J, Huang, Z, Iantchenko, A, Innocente, P, Insulander Bjork, K, Ionita-Schrittweiser, C, Isliker, H, Jardin, A, Jaspers, R, Karimov, R, Karpushov, A, Kazakov, Y, Komm, M, Kong, M, Kovacic, J, Krutkin, O, Kudlacek, O, Kumar, U, Kwiatkowski, R, Labit, B, Laguardia, L, Lammers, J, Laribi, E, Laszynska, E, Lazaros, A, Linder, O, Linehan, B, Lipschultz, B, Llobet, X, Loizu, J, Lunt, T, Macusova, E, Marandet, Y, Maraschek, M, Marceca, G, Marchetto, C, Marchioni, S, Marmar, E, Martin, Y, Martinelli, L, Matos, F, Maurizio, R, Mayoral, M, Mazon, D, Menkovski, V, Merle, A, Merlo, G, Meyer, H, Mikszuta-Michalik, K, Molina Cabrera, P, Morales, J, Moret, J, Moro, A, Moulton, D, Muhammed, H, Myatra, O, Mykytchuk, D, Napoli, F, Nem, R, Nielsen, A, Nocente, M, Nowak, S, Offeddu, N, Olsen, J, Orsitto, F, Pan, O, Papp, G, Pau, A, Perek, A, Pesamosca, F, Peysson, Y, Pigatto, L, Piron, C, Poradzinski, M, Porte, L, Putterich, T, Rabinski, M, Raj, H, Rasmussen, J, Ratta, G, Ravensbergen, T, Ricci, D, Ricci, P, Rispoli, N, Riva, F, Rivero-Rodriguez, J, Salewski, M, Sauter, O, Schmidt, B, Schrittweiser, R, Sharapov, S, Sheikh, U, Sieglin, B, Silva, M, Smolders, A, Snicker, A, Sozzi, C, Spolaore, M, Stagni, A, Stipani, L, Sun, G, Tala, T, Tamain, P, Tanaka, K, Tema Biwole, A, Terranova, D, Terry, J, Testa, D, Theiler, C, Thornton, A, Thrysoe, A, Torreblanca, H, Tsui, C, Vaccaro, D, Vallar, M, Van Berkel, M, Van Eester, D, Van Kampen, R, Van Mulders, S, Verhaegh, K, Verhaeghe, T, Vianello, N, Villone, F, Viezzer, E, Vincent, B, Voitsekhovitch, I, Vu, N, Walkden, N, Wauters, T, Weisen, H, Wendler, N, Wensing, M, Widmer, F, Wiesen, S, Wischmeier, M, Wijkamp, T, Wunderlich, D, Wuthrich, C, Yanovskiy, V, and Zebrowski, J

Subjects
Nuclear and High Energy Physics, Tokamak, feedback-control, Nuclear fusion, TCV, EUROfusion, ddc:620, plasmas, Condensed Matter Physics, tokamak, nuclear fusion, QC
Abstract

The tokamak à configuration variable (TCV) continues to leverage its unique shaping capabilities, flexible heating systems and modern control system to address critical issues in preparation for ITER and a fusion power plant. For the 2019–20 campaign its configurational flexibility has been enhanced with the installation of removable divertor gas baffles, its diagnostic capabilities with an extensive set of upgrades and its heating systems with new dual frequency gyrotrons. The gas baffles reduce coupling between the divertor and the main chamber and allow for detailed investigations on the role of fuelling in general and, together with upgraded boundary diagnostics, test divertor and edge models in particular. The increased heating capabilities broaden the operational regime to include T e/T i ∼ 1 and have stimulated refocussing studies from L-mode to H-mode across a range of research topics. ITER baseline parameters were reached in type-I ELMy H-modes and alternative regimes with ‘small’ (or no) ELMs explored. Most prominently, negative triangularity was investigated in detail and confirmed as an attractive scenario with H-mode level core confinement but an L-mode edge. Emphasis was also placed on control, where an increased number of observers, actuators and control solutions became available and are now integrated into a generic control framework as will be needed in future devices. The quantity and quality of results of the 2019–20 TCV campaign are a testament to its successful integration within the European research effort alongside a vibrant domestic programme and international collaborations.

Published
2022

Catalog

Books, media, physical & digital resources
See catalog results