Plasma Physics and Controlled Fusion最新文献

{"title":"Comparison of detachment in Ohmic plasmas with positive and negative triangularity","authors":"O Février, C K Tsui, G Durr-Legoupil-Nicoud, C Theiler, M Carpita, S Coda, C Colandrea, B P Duval, S Gorno, E Huett, B Linehan, A Perek, L Porte, H Reimerdes, O Sauter, E Tonello, M Zurita, T Bolzonella, F Sciortino, the TCV Team and the EUROfusion Tokamak Exploitation Team","doi":"10.1088/1361-6587/ad3c1c","DOIUrl":"https://doi.org/10.1088/1361-6587/ad3c1c","url":null,"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: δ) 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 could not be cooled to below 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 (λq) 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, λint. 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.","PeriodicalId":20239,"journal":{"name":"Plasma Physics and Controlled Fusion","volume":"47 1","pages":""},"PeriodicalIF":2.2,"publicationDate":"2024-04-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140804037","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Modelling of power exhaust in TCV positive and negative triangularity L-mode plasmas","authors":"E Tonello, F Mombelli, O Février, G Alberti, T Bolzonella, G Durr-Legoupil-Nicoud, S Gorno, H Reimerdes, C Theiler, N Vianello, M Passoni, the TCV Team and the WPTE Team","doi":"10.1088/1361-6587/ad3c19","DOIUrl":"https://doi.org/10.1088/1361-6587/ad3c19","url":null,"abstract":"L-mode negative triangularity (NT) operation is a promising alternative to the positive triangularity (PT) H-mode as a high-confinement edge localised mode-free operational regime. In this work, two TCV Ohmic L-mode core density ramps with opposite triangularity are investigated using SOLPS-ITER modelling. This numerical study aims to investigate the power exhaust differences between NT and PT focusing, in particular, on the geometrical effect of triangularity. To disentangle the latter from differences related to cross-field transport, anomalous diffusivities for particle ( ) and energy ( ) transport are fixed to the same values in PT and NT. The simulation results clearly show dissimilar transport and accumulation of neutral particles in the scrape-off layer for the two configurations. This gives rise to different ionization sources in the edge and divertor regions and produces differences in the poloidal and cross-field fluxes, ultimately leading to different power and particle divertor fluxes in the two configurations. Simulations recover the experimental feature of a hotter and attached outer target ( ) in the NT scenario compared to the PT counterpart.","PeriodicalId":20239,"journal":{"name":"Plasma Physics and Controlled Fusion","volume":"1 1","pages":""},"PeriodicalIF":2.2,"publicationDate":"2024-04-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140804035","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Radial drift of plasma blobs in a toroidal magnetic field with fully kinetic and reduced fluid models","authors":"Nathan Mackey, Sergey Blinov, Adam Stanier, Ari Le","doi":"10.1088/1361-6587/ad3c1b","DOIUrl":"https://doi.org/10.1088/1361-6587/ad3c1b","url":null,"abstract":"In curved magnetic geometries, field-aligned regions of enhanced plasma pressure and density, termed ‘blobs,’ move as coherent filaments across the magnetic field lines. Coherent blobs account for a significant fraction of transport at the edges of magnetic fusion experiments and arise in naturally-occurring space plasmas. This work examines the dynamics of blobs with a fully kinetic electromagnetic particle-in-cell code and with a drift-reduced fluid code. In low-beta regimes with moderate blob speeds, good agreement is found in the maximum blob velocity between the two simulation schemes and simple analytical estimates. The fully kinetic code demonstrates that blob speeds saturate near the initial sound speed, which is a regime outside the validity of the reduced fluid model.","PeriodicalId":20239,"journal":{"name":"Plasma Physics and Controlled Fusion","volume":"66 1","pages":""},"PeriodicalIF":2.2,"publicationDate":"2024-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140611271","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Study on stray electrons ejecting from a long-pulse negative ion source for fusion","authors":"Yuwen Yang, Jianglong Wei, Yuming Gu, Yahong Xie, Chundong Hu","doi":"10.1088/1361-6587/ad3c1e","DOIUrl":"https://doi.org/10.1088/1361-6587/ad3c1e","url":null,"abstract":"The negative ion based neutral beam injection is a desirable plasma heating and current drive method for the large-scale magnetic fusion devices. Due to the strict requirements and difficult development of the negative ion source for fusion, a long-pulse negative ion source has been developed under the framework of the Comprehensive Research Facility for Fusion Technology in China. This negative ion source consists of a single radio frequency (RF) driver plasma source and a three-electrode accelerator. The typical extraction and acceleration voltage are 4–8 kV and 40–50 kV, respectively. During one shot of the long-pulse (∼100 s) beam extraction, the gas pressure in the vacuum vessel increased sharply and the temperature of the cryopump rise from 8 K to 20 K. Moreover, the vessel wall appeared a high temperature after several long-pulse shots. A self-consistent simulation of beam-gas interaction revealed that the heat loads on the vessel wall should be caused by the stray electrons ejecting from the accelerator. Those stray electrons are mainly generated via the stripping or ionization collisions and strongly deflected by the downstream side of the deflection magnetic field for the co-extracted electron. The location of hot spots measured by infrared thermography is consistent with the simulation results. To solve this problem, a series of electron dumps are designed to avoid the direct impinging of the ejecting electrons on the cryopump and the vessel wall. And the results suggest that the hot spots are almost eliminated.","PeriodicalId":20239,"journal":{"name":"Plasma Physics and Controlled Fusion","volume":"78 1","pages":""},"PeriodicalIF":2.2,"publicationDate":"2024-04-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140611267","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Impact of increasing plasma-wall gap on plasma response to RMP fields in ITER","authors":"X Bai, A Loarte, Y Q Liu, S D Pinches, F Koechl, L Li, M Dubrov, Y Gribov","doi":"10.1088/1361-6587/ad3aa0","DOIUrl":"https://doi.org/10.1088/1361-6587/ad3aa0","url":null,"abstract":"The impact of increasing plasma-wall gap on controlling edge-localized modes (ELMs) is numerically evaluated for the ITER 5 MA/2.65 T H-mode scenarios with full tungsten wall, based on the MARS-F computed plasma response to the applied <italic toggle=\"yes\">n</italic>= 3–5 (<italic toggle=\"yes\">n</italic> is the toroidal mode number) resonant magnetic perturbation (RMP) fields. Three new scenarios, referred to as standard, clearance and outergap, are considered assuming different plasma-wall gap sizes over a range on which vertically stability can be maintained by in-vessel coils in ITER. The latter are shown to have both direct and indirect effects on the plasma response and hence ELM control in ITER. The indirect and also primary influence occurs via change of the equilibrium edge safety factor <italic toggle=\"yes\">q₉₅\u0000</italic>, which decreases with increasing the plasma-wall gap (at fixed plasma current and toroidal field), leading to a multi-peaking structure in the plasma response as measured by the plasma displacement near the X-point or the edge-localized resonant radial magnetic field perturbation. The direct, albeit secondary effect, is the reduction of local peak amplitudes with increasing the plasma-wall gap thus weakening the RMP field efficiency for ELM control with a given current in the control coils. A slight reduction of the plasma current, from 5 MA to 4.77, 4.92 and 4.65 MA for the standard, clearance and outergap scenarios, respectively, is found to be sufficient to access the <italic toggle=\"yes\">q</italic>\u0000₉₅ window for the best ELM control with the <italic toggle=\"yes\">n</italic>= 3 RMP. The <italic toggle=\"yes\">n</italic>= 4 coil current configuration with the <italic toggle=\"yes\">n</italic>= 5 sideband is also found favorable for ELM control in ITER, by producing RMP fields with mixed toroidal spectra compared to <italic toggle=\"yes\">n</italic> = 3.","PeriodicalId":20239,"journal":{"name":"Plasma Physics and Controlled Fusion","volume":"221 1","pages":""},"PeriodicalIF":2.2,"publicationDate":"2024-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140611265","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Influence of the magnetic configuration on the high-field side scrape-off layer at ASDEX Upgrade and the role of the secondary separatrix","authors":"D Hachmeister, C Silva, J Santos, G D Conway, L Gil, A Silva, U Stroth, J Vicente, E Wolfrum, R M McDermott, R Dux, D Brida, R Fischer, B Kurzan, the ASDEX Upgrade Team4, the EUROfusion MST1 Team5","doi":"10.1088/1361-6587/ad3a9f","DOIUrl":"https://doi.org/10.1088/1361-6587/ad3a9f","url":null,"abstract":"In tokamaks, radial transport is ballooning, meaning it is enhanced at the low-field side (LFS). This work investigates the effect of the magnetic configuration on the high-field side (HFS) scrape-off layer. Our experiments involved L-mode and H-mode discharges at ASDEX Upgrade, in which we scanned the magnetic configuration from a lower to an upper single-null shape, thus varying the location of the secondary separatrix. We show that the secondary separatrix determines the width of the HFS scrape-off layer, meaning that the density is much lower in the region that is magnetically disconnected from the LFS scrape-off layer, outside the secondary separatrix. Furthermore, we observe that the large density often seen in the HFS divertor drastically decreases as the separation between the primary and secondary separatrices falls below a particular value. This value is different for L-mode and H-mode plasmas and closely matches the power decay length measured at the LFS midplane. We also show how the HFS scrape-off layer density is smaller in an upper single-null than in a lower single-null, when the ionic grad-B drift points down. This difference is likely caused by reversing the <inline-formula>\u0000<tex-math><?CDATA $mathrm{E}timesmathrm{B}$?></tex-math>\u0000<mml:math overflow=\"scroll\"><mml:mrow><mml:mrow><mml:mi mathvariant=\"normal\">E</mml:mi></mml:mrow><mml:mo>×</mml:mo><mml:mrow><mml:mi mathvariant=\"normal\">B</mml:mi></mml:mrow></mml:mrow></mml:math>\u0000<inline-graphic xlink:href=\"ppcfad3a9fieqn1.gif\" xlink:type=\"simple\"></inline-graphic>\u0000</inline-formula> drifts in the active divertor when switching the active X-point from the bottom to the top. We further observe that the neutral density in the lower divertor also correlates with the plasma shape and the high-density region in the HFS scrape-off layer. During the shape scans analyzed here, the HFS divertor remained partially detached throughout, with transitory reattachment modulated by ELM activity in H-mode. This work provides novel experimental data that can be leveraged to further the modeling capabilities and understanding of scrape-off layer physics in highly shaped plasmas.","PeriodicalId":20239,"journal":{"name":"Plasma Physics and Controlled Fusion","volume":"3 1","pages":""},"PeriodicalIF":2.2,"publicationDate":"2024-04-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140611383","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"On electromagnetic turbulence and transport in STEP","authors":"M Giacomin, D Kennedy, F J Casson, Ajay C J, D Dickinson, B S Patel, C M Roach","doi":"10.1088/1361-6587/ad366f","DOIUrl":"https://doi.org/10.1088/1361-6587/ad366f","url":null,"abstract":"In this work, we present first-of-their-kind nonlinear local gyrokinetic (GK) simulations of electromagnetic turbulence at mid-radius in the burning plasma phase of the conceptual high-<italic toggle=\"yes\">β</italic>, reactor-scale, tight-aspect-ratio tokamak Spherical Tokamak for Energy Production (STEP). A prior linear analysis in Kennedy <italic toggle=\"yes\">et al</italic> (2023 <italic toggle=\"yes\">Nucl. Fusion</italic>\u0000<bold>63</bold> 126061) reveals the presence of unstable hybrid kinetic ballooning modes (KBMs), where inclusion of the compressional magnetic field fluctuation, <inline-formula>\u0000<tex-math><?CDATA $delta B_{parallel}$?></tex-math>\u0000<mml:math overflow=\"scroll\"><mml:mrow><mml:mi>δ</mml:mi><mml:msub><mml:mi>B</mml:mi><mml:mrow><mml:mo>∥</mml:mo></mml:mrow></mml:msub></mml:mrow></mml:math>\u0000<inline-graphic xlink:href=\"ppcfad366fieqn1.gif\" xlink:type=\"simple\"></inline-graphic>\u0000</inline-formula>, is crucial, and subdominant microtearing modes (MTMs) are found at binormal scales approaching the ion-Larmor radius. Local nonlinear GK simulations on the selected surface in the central core region suggest that hybrid KBMs can drive large turbulent transport, and that there is negligible turbulent transport from subdominant MTMs when hybrid KBMs are artificially suppressed (through the omission of <inline-formula>\u0000<tex-math><?CDATA $delta B_{parallel}$?></tex-math>\u0000<mml:math overflow=\"scroll\"><mml:mrow><mml:mi>δ</mml:mi><mml:msub><mml:mi>B</mml:mi><mml:mrow><mml:mo>∥</mml:mo></mml:mrow></mml:msub></mml:mrow></mml:math>\u0000<inline-graphic xlink:href=\"ppcfad366fieqn2.gif\" xlink:type=\"simple\"></inline-graphic>\u0000</inline-formula>). Nonlinear simulations that include perpendicular equilibrium flow shear can saturate at lower fluxes that are more consistent with the available sources in STEP. This analysis suggests that hybrid KBMs could play an important role in setting the turbulent transport in STEP, and possible mechanisms to mitigate turbulent transport are discussed. Increasing the safety factor or the pressure gradient strongly reduces turbulent transport from hybrid KBMs in the cases considered here. Challenges of simulating electromagnetic turbulence in this high-<italic toggle=\"yes\">β</italic> regime are highlighted. In particular the observation of radially extended turbulent structures in the absence of equilibrium flow shear motivates future advanced global GK simulations that include <inline-formula>\u0000<tex-math><?CDATA $delta B_parallel$?></tex-math>\u0000<mml:math overflow=\"scroll\"><mml:mrow><mml:mi>δ</mml:mi><mml:msub><mml:mi>B</mml:mi><mml:mo>∥</mml:mo></mml:msub></mml:mrow></mml:math>\u0000<inline-graphic xlink:href=\"ppcfad366fieqn3.gif\" xlink:type=\"simple\"></inline-graphic>\u0000</inline-formula>.","PeriodicalId":20239,"journal":{"name":"Plasma Physics and Controlled Fusion","volume":"57 1","pages":""},"PeriodicalIF":2.2,"publicationDate":"2024-03-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140597285","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Decoupled magnetic control of spherical tokamak divertors via vacuum harmonic constraints","authors":"O P Bardsley, J L Baker, C Vincent","doi":"10.1088/1361-6587/ad319d","DOIUrl":"https://doi.org/10.1088/1361-6587/ad319d","url":null,"abstract":"Power exhaust is a critical challenge for spherical tokamak reactors, making the design, optimisation and control of advanced divertor configurations crucial. These tasks are greatly simplified if the poloidal magnetic fields in the core and divertor regions can be varied independently. We present a novel method which facilitates decoupling of the core plasma equilibrium from the divertor geometry optimisation and control, using vacuum spherical harmonic (SH) constraints. This has the advantage that it avoids iterative solution of the Grad–Shafranov equation, making it easy to use, rapid and reliable. By comparing a large number of MAST-U equilibrium reconstructions against their approximations using SHs, a small number (<inline-formula>\u0000<tex-math><?CDATA ${sim}4$?></tex-math>\u0000<mml:math overflow=\"scroll\"><mml:mrow><mml:mrow><mml:mo>∼</mml:mo></mml:mrow><mml:mn>4</mml:mn></mml:mrow></mml:math>\u0000<inline-graphic xlink:href=\"ppcfad319dieqn1.gif\" xlink:type=\"simple\"></inline-graphic>\u0000</inline-formula>) of harmonics is found to be sufficient to closely reproduce the plasma boundary shape. We show experimentally that poloidal field changes designed to leave harmonics unaffected indeed have no effect on the core plasma shape. When augmented with divertor geometry constraints, this approach gives a powerful tool for creating advanced magnetic configurations, and its simplicity brings improvements in speed and robustness when solving coil position optimisation problems. We discuss the clear benefits to real-time feedback control, feed-forward scenario design and coilset optimisation with a view to future reactors.","PeriodicalId":20239,"journal":{"name":"Plasma Physics and Controlled Fusion","volume":"71 1","pages":""},"PeriodicalIF":2.2,"publicationDate":"2024-03-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140315289","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Multi-machine benchmark of the self-consistent 1D scrape-off layer model DIV1D from stagnation point to target with SOLPS-ITER","authors":"G L Derks, E Westerhof, M van Berkel, J H Jenneskens, J T W Koenders, S Mijin, D Moulton, H Reimerdes, H Wu","doi":"10.1088/1361-6587/ad2e37","DOIUrl":"https://doi.org/10.1088/1361-6587/ad2e37","url":null,"abstract":"This paper extends a 1D dynamic physics-based model of the scrape-off layer (SOL) plasma, DIV1D, to include the core SOL and possibly a second target. The extended model is benchmarked on 1D mapped SOLPS-ITER simulations to find input settings for DIV1D that allow it to describe SOL plasmas from upstream to target—calibrating it on a scenario and device basis. The benchmark shows a quantitative match between DIV1D and 1D mapped SOLPS-ITER profiles for the heat flux, electron temperature, and electron density within roughly 50% on: (1) the Tokamak Configuration Variable (TCV) for a gas puff scan; (2) a single SOLPS-ITER simulation of the Upgraded Mega Ampere Spherical Tokamak; and (3) the Upgraded Axially Symmetric Divertor EXperiment in Garching Tokamak (AUG) for a simultaneous scan in heating power and gas puff. Once calibrated, DIV1D self-consistently describes dependencies of the SOL solution on core fluxes and external neutral gas densities for a density scan on TCV whereas a varying SOL width is used in DIV1D for AUG to match a simultaneous change in power and density. The ability to calibrate DIV1D on a scenario and device basis is enabled by accounting for cross field transport with an effective flux expansion factor and by allowing neutrals to be exchanged between SOL and adjacent domains.","PeriodicalId":20239,"journal":{"name":"Plasma Physics and Controlled Fusion","volume":"44 1","pages":""},"PeriodicalIF":2.2,"publicationDate":"2024-03-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140315103","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Spin-polarized 3He shock waves from a solid-gas composite target at high laser intensities","authors":"L Reichwein, X F Shen, M Büscher, A Pukhov","doi":"10.1088/1361-6587/ad30c0","DOIUrl":"https://doi.org/10.1088/1361-6587/ad30c0","url":null,"abstract":"We investigate collisionless shock acceleration of spin-polarized <inline-formula>\u0000<tex-math><?CDATA ${}^3$?></tex-math>\u0000<mml:math overflow=\"scroll\"><mml:msup><mml:mrow></mml:mrow><mml:mn>3</mml:mn></mml:msup></mml:math>\u0000<inline-graphic xlink:href=\"ppcfad30c0ieqn1.gif\" xlink:type=\"simple\"></inline-graphic>\u0000</inline-formula>He for laser pulses with normalized vector potentials in the range <inline-formula>\u0000<tex-math><?CDATA $a_0 = 100-200$?></tex-math>\u0000<mml:math overflow=\"scroll\"><mml:msub><mml:mi>a</mml:mi><mml:mn>0</mml:mn></mml:msub><mml:mo>=</mml:mo><mml:mn>100</mml:mn><mml:mo>−</mml:mo><mml:mn>200</mml:mn></mml:math>\u0000<inline-graphic xlink:href=\"ppcfad30c0ieqn2.gif\" xlink:type=\"simple\"></inline-graphic>\u0000</inline-formula>. The setup utilized in the 2D-particle-in-cell simulations consists of a solid carbon foil that is placed in front of the main Helium target. The foil is heated by the laser pulse and shields the Helium from the highly oscillating fields. In turn, a shock wave with more homogeneous fields is induced, leading to highly polarized ion beams. We observe that the inclusion of radiation reaction into our simulations leads to a higher beam charge without affecting the polarization degree to a significant extent.","PeriodicalId":20239,"journal":{"name":"Plasma Physics and Controlled Fusion","volume":"9 1","pages":""},"PeriodicalIF":2.2,"publicationDate":"2024-03-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140315042","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}