The ELMy H-mode plasmas realized with the supersonic molecular beam injection（SMBI） are studied in relation to the energy confinement and the heating power for the L–H transition（P_（L-H） ） in the HL-2A tokamak....The ELMy H-mode plasmas realized with the supersonic molecular beam injection（SMBI） are studied in relation to the energy confinement and the heating power for the L–H transition（P_（L-H） ） in the HL-2A tokamak. A database is assembled for this study based on the ELMy H-mode discharges during the experimental campaigns in the period 2009–2013at the HL-2A tokamak. The statistical results show that the SMBI is favourable for reaching the H-mode by reducing the heating power at the L–H transition and for the H-mode performance by improving the energy confinement compared with the ordinary gas puffing（GP）. The reduction of P_（L-H） is about 20% when the density is low, and the energy confinement enhancement factor of H_（H98y2）= τ_E/τ_（th,98y2） ≈ 1.5 is achieved with the SMBI. Note that in the database the density dependence of P_（L-H） is non-monotonic with the ˉne,min≈ 3×10^（19） m^（-3） at which the P_（L-H） is minimum. Most of P_（L-H） data are on the low density branch where the P_（L-H） increases with the decrease in density. The minimum of the P_（L-H） in HL-2A is comparable to the ITPA multi-machine threshold power scaling P_（thr_scal08）. The physics behind the reduction of the P_（L-H） with the SMBI is also investigated in relation to the change of the density gradient at the plasma edge, the gas fuelling efficiency, and the recycling.展开更多
Detailed investigations on the filamentary structures associated with the type-I edge-localized modes（ELMs） should be helpful for protecting the materials of a plasma-facing wall on a future large device.Related exp...Detailed investigations on the filamentary structures associated with the type-I edge-localized modes（ELMs） should be helpful for protecting the materials of a plasma-facing wall on a future large device.Related experiments have been carefully conducted in the Experimental Advanced Superconducting Tokamak（EAST） using combined Langmuir-magnetic probes.The experimental results indicate that the radially outward velocity of type-I ELMy filaments can be up to 1.7 kms^（-1） in the far scrape-off layer（SOL） region.It is remarkable that the electron temperature of these filaments is detected to be ~50eV,corresponding to a fraction of 1/6 to the temperature near the pedestal top,while the density ~3×10^（19）m^（-3） of these filaments could be approximate to the line-averaged density.In addition,associated magnetic fluctuations have been clearly observed at the same time,which show good agreement with the density perturbations.A localized current on the order of ~100kA could be estimated within the filaments.展开更多
JET has made unique contributions to the physics basis of ITER by virtue ofits ITER-like geometry, large plasma size and D-T capability. The paper discusses recent JET resultsand their implications for ITER in the are...JET has made unique contributions to the physics basis of ITER by virtue ofits ITER-like geometry, large plasma size and D-T capability. The paper discusses recent JET resultsand their implications for ITER in the areas of standard ELMy H-mode, D-T operation and advancedtokamak modes. In ELMy H-mode the separation of plasma energy into core and pedestal contributionsshows that core confinement scales like gyroBohm transport. High triangularity has a beneficialeffect on confinement and leads to an integrated plasma performance exceeding the ITER Q =10reference case. A revised type I ELM scaling predicts acceptable ELM energy losses for ITER, whileprogress in physics understanding of NTMs shows how to control them in ITER. The D-T experiments of1997 have validated ICRF scenarios for heating ITER/a reactor and identified ion minority schemes(e.g. (~3He)DT) with strong ion heating. They also show that the slowing down of alpha particles isclassical so that the self-heating by fusion alphas should cause no unexpected problems. With thePellet Enhanced Performance mode of 1988, JET has produced the first advanced tokamak mode, withpeaked pressure profiles sustained by reversed magnetic shear and strongly reduced transport. Morerecently, LHCD has provided easy tuning of reversed shear and reliable access to ITBs. Improvedphysics understanding shows that rational g-surfaces play a key role in the formation anddevelopment of ITBs. The demonstration of real time feedback control of plasma current and pressureprofiles opens the path towards fully controlled steady-state tokamak plasmas.展开更多
The first experimental investigation of the tungsten behavior in ELMy H-mode plasmas with co-/counter neutral beam injection(NBI)and unfavor-able/favorable B t was performed on EAST.Tungsten was found to accumulate ea...The first experimental investigation of the tungsten behavior in ELMy H-mode plasmas with co-/counter neutral beam injection(NBI)and unfavor-able/favorable B t was performed on EAST.Tungsten was found to accumulate easily in ELMy H-mode plasma with co-NBI heating and unfavorable B t.Thus,in this case the tungsten concentration can exceed 10^(-4),resulting in degradation of the plasma confinement and periodic H–L transitions.To reduce the tungsten concentration in steady-state type-I ELMy H-mode operation,counter-NBI is applied to modify the density and temperature and brake the plasma toroidal rotation.The applied counter-NBI decreases the PHZ+E_(r) inward pinch velocity and rever-ses the direction of neoclassical inward convection,thus decreasing the tungsten concentration from-7×10^(-5) to-2×10^(-5) in type-I ELMy H-mode plasma with favorable B_(t).A comparison of the effects of different B_(t) directions on the tungsten behavior also shows that favor-able B_(t) is beneficial for reducing the tungsten concentration in the core plasma.These results imply that counter-NBI with favorable B_(t) can effectively prevent tungsten accu-mulation and expand the operating window for exploring steady-state type-I ELMy H-mode operation of EAST.展开更多
基金supported by the National Natural Science Foundation of China(Grant Nos.11375057 and 11175061)the National Magnetic Confinement Fusion Science Program,China(Grant Nos.2010GB102003 and 2014GB108003)
文摘The ELMy H-mode plasmas realized with the supersonic molecular beam injection（SMBI） are studied in relation to the energy confinement and the heating power for the L–H transition（P_（L-H） ） in the HL-2A tokamak. A database is assembled for this study based on the ELMy H-mode discharges during the experimental campaigns in the period 2009–2013at the HL-2A tokamak. The statistical results show that the SMBI is favourable for reaching the H-mode by reducing the heating power at the L–H transition and for the H-mode performance by improving the energy confinement compared with the ordinary gas puffing（GP）. The reduction of P_（L-H） is about 20% when the density is low, and the energy confinement enhancement factor of H_（H98y2）= τ_E/τ_（th,98y2） ≈ 1.5 is achieved with the SMBI. Note that in the database the density dependence of P_（L-H） is non-monotonic with the ˉne,min≈ 3×10^（19） m^（-3） at which the P_（L-H） is minimum. Most of P_（L-H） data are on the low density branch where the P_（L-H） increases with the decrease in density. The minimum of the P_（L-H） in HL-2A is comparable to the ITPA multi-machine threshold power scaling P_（thr_scal08）. The physics behind the reduction of the P_（L-H） with the SMBI is also investigated in relation to the change of the density gradient at the plasma edge, the gas fuelling efficiency, and the recycling.
基金supported by National Natural Science Foundation of China under Contracts Nos.11275047,11705128,11422546,11575235,11575236 and 11505222Key Research Program of Frontier Sciences,CAS,Grant No.QYZDB-SSWSLH001National Magnetic Confinement Fusion Science Program of China under Contract Nos.2015GB101000 and 2013GB107003
文摘Detailed investigations on the filamentary structures associated with the type-I edge-localized modes（ELMs） should be helpful for protecting the materials of a plasma-facing wall on a future large device.Related experiments have been carefully conducted in the Experimental Advanced Superconducting Tokamak（EAST） using combined Langmuir-magnetic probes.The experimental results indicate that the radially outward velocity of type-I ELMy filaments can be up to 1.7 kms^（-1） in the far scrape-off layer（SOL） region.It is remarkable that the electron temperature of these filaments is detected to be ~50eV,corresponding to a fraction of 1/6 to the temperature near the pedestal top,while the density ~3×10^（19）m^（-3） of these filaments could be approximate to the line-averaged density.In addition,associated magnetic fluctuations have been clearly observed at the same time,which show good agreement with the density perturbations.A localized current on the order of ~100kA could be estimated within the filaments.
文摘JET has made unique contributions to the physics basis of ITER by virtue ofits ITER-like geometry, large plasma size and D-T capability. The paper discusses recent JET resultsand their implications for ITER in the areas of standard ELMy H-mode, D-T operation and advancedtokamak modes. In ELMy H-mode the separation of plasma energy into core and pedestal contributionsshows that core confinement scales like gyroBohm transport. High triangularity has a beneficialeffect on confinement and leads to an integrated plasma performance exceeding the ITER Q =10reference case. A revised type I ELM scaling predicts acceptable ELM energy losses for ITER, whileprogress in physics understanding of NTMs shows how to control them in ITER. The D-T experiments of1997 have validated ICRF scenarios for heating ITER/a reactor and identified ion minority schemes(e.g. (~3He)DT) with strong ion heating. They also show that the slowing down of alpha particles isclassical so that the self-heating by fusion alphas should cause no unexpected problems. With thePellet Enhanced Performance mode of 1988, JET has produced the first advanced tokamak mode, withpeaked pressure profiles sustained by reversed magnetic shear and strongly reduced transport. Morerecently, LHCD has provided easy tuning of reversed shear and reliable access to ITBs. Improvedphysics understanding shows that rational g-surfaces play a key role in the formation anddevelopment of ITBs. The demonstration of real time feedback control of plasma current and pressureprofiles opens the path towards fully controlled steady-state tokamak plasmas.
基金supported by the National Key R&D Program of China(Nos.2018YFE0311100 and 2017YFE0301205)National Natural Science Foundation of China(Nos.11905146,11775269,11575244,11575249,11575235,11422546,11805133,and U19A20113)+4 种基金Users with Excellence Program of Hefei Science Center,CAS(No.2019HSC-UE014)National Magnetic Confinement Fusion Science Program of China(Nos.2015GB110005,2015GB103003,2015GB101002,and 2015GB103000)Key Research Program of Frontier Sciences,CAS(No.QYZDB-SSWSLH001)CASHIPS Director’s Fund(No.BJPY2019A01)Shenzhen Clean Energy Research Institute.
文摘The first experimental investigation of the tungsten behavior in ELMy H-mode plasmas with co-/counter neutral beam injection(NBI)and unfavor-able/favorable B t was performed on EAST.Tungsten was found to accumulate easily in ELMy H-mode plasma with co-NBI heating and unfavorable B t.Thus,in this case the tungsten concentration can exceed 10^(-4),resulting in degradation of the plasma confinement and periodic H–L transitions.To reduce the tungsten concentration in steady-state type-I ELMy H-mode operation,counter-NBI is applied to modify the density and temperature and brake the plasma toroidal rotation.The applied counter-NBI decreases the PHZ+E_(r) inward pinch velocity and rever-ses the direction of neoclassical inward convection,thus decreasing the tungsten concentration from-7×10^(-5) to-2×10^(-5) in type-I ELMy H-mode plasma with favorable B_(t).A comparison of the effects of different B_(t) directions on the tungsten behavior also shows that favor-able B_(t) is beneficial for reducing the tungsten concentration in the core plasma.These results imply that counter-NBI with favorable B_(t) can effectively prevent tungsten accu-mulation and expand the operating window for exploring steady-state type-I ELMy H-mode operation of EAST.
