Vapour shielding of liquid-metal CPS-based targets under ELM-like and disruption transient loading

This paper presents experimental studies of plasma-surface interactions during powerful plasma impacts of a quasi-stationary plasma accelerator (QSPA) on the Sn capillary porous systems (CPSs) in conditions simulating disruption and edge localized modes (ELM) like loads. Experiments were carried out using two QSPA devices. ELM-like plasma exposures were performed with QSPA-M test-bed facility. A large-scale QSPA Kh-50 device was used to simulate plasma disruptions and giant ELMs. Variation of the plasma stream energy density has been performed to study the onset of vapour shield. It is shown that during plasma exposures of a Sn-CPS target with the QSPA plasma load <1 MJ m−2, single dust particles traces have been registered. A further increase in the heat load leads to the splashing of the eroded material. For ELM-like impacts, a rather weak melt motion was observed on the target surface. A post-mortem analysis has shown that the CPS structure was not destroyed in the course of many repetitive ELM-like pulses. Surface morphology has changed from a smooth surface to corrugation structures with the formation of some cavities in mesh cells due to the influence of the surface tension and capillary effects. Spectral lines of Sn I and Sn II have been identified by optical emission spectroscopy in the near-surface plasma. A plasma shield, that consists mostly of Sn neutrals appears at Q ∼ 0.1 MJ m−2. An increase in the surface heat load resulted in the intensive emission of Sn II lines, which started to be observed at Q ∼ 0.3 MJ m−2. The plasma electron density near the surface increases significantly at Q > 0.5 MJ m−2, which corresponds to the strong vapour shielding of the exposed surface. A comparison between the obtained results on the vapour shielding of Sn CPS and available numerical simulation using the TOKES code has been performed.

[1]  Y. Petrov,et al.  PARAMETERS OF HYDROGEN PLASMA STREAMS IN QSPA-M AND THEIR DEPENDENCE ON EXTERNAL MAGNETIC FIELD , 2021 .

[2]  J. Contributors,et al.  Resolidification-controlled melt dynamics under fast transient tokamak plasma loads , 2020, Nuclear Fusion.

[3]  V. Makhlai,et al.  Damaging of inclined/misaligned castellated tungsten surfces exposed to a large number of repetitive QSPA plasma loads , 2020, Physica Scripta.

[4]  F. Maviglia,et al.  Simulation of the Divertor Target Shielding During Major Disruption in DEMO , 2019, Fusion Science and Technology.

[5]  Y. Petrov,et al.  Influence of a magnetic field on plasma energy transfer to material surfaces in edge-localized mode simulation experiments with QSPA-M , 2019, Nuclear Fusion.

[6]  T. Morgan,et al.  Power handling and vapor shielding of pre-filled lithium divertor targets in Magnum-PSI , 2019, Nuclear Fusion.

[7]  J. V. Dommelen,et al.  Using 3D-printed tungsten to optimize liquid metal divertor targets for flow and thermal stresses , 2019, Nuclear Fusion.

[8]  Angel Ibarra,et al.  DEMO design activity in Europe: Progress and updates , 2018, Fusion Engineering and Design.

[9]  J. Karhunen,et al.  Plasma–wall interaction studies within the EUROfusion consortium: progress on plasma-facing components development and qualification , 2017 .

[10]  Y. Petrov,et al.  Novel test-bed facility for PSI issues in fusion reactor conditions on the base of next generation QSPA plasma accelerator , 2017 .

[11]  J. W. Genuit,et al.  Power handling of a liquid-metal based CPS structure under high steady-state heat and particle fluxes , 2017 .

[12]  F. Peeters,et al.  Tin re-deposition and erosion measured by cavity-ring-down-spectroscopy under a high flux plasma beam , 2017 .

[13]  R. Nygren,et al.  Liquid surfaces for fusion plasma facing components—A critical review. Part I: Physics and PSI , 2016 .

[14]  R. Pitts,et al.  Simulation of divertor targets shielding during transients in ITER , 2016 .

[15]  K. Bystrov,et al.  Self-Regulated Plasma Heat Flux Mitigation Due to Liquid Sn Vapor Shielding. , 2016, Physical review letters.

[16]  S. Krasheninnikov,et al.  Vapor shielding models and the energy absorbed by divertor targets during transient events , 2016 .

[17]  M. Sadowski,et al.  Tungsten Melt Losses under QSPA Kh-50 Plasma Exposures Simulating ITER ELMs and Disruptions , 2014 .

[18]  Y. Igitkhanov,et al.  Two-dimensional modeling of disruption mitigation by gas injection , 2011 .

[19]  A. Vertkov,et al.  Application of lithium in systems of fusion reactors. 2. The issues of practical use of lithium in experimental facilities and fusion devices , 2009 .

[20]  V. I. Tereshin,et al.  Experimental study of plasma energy transfer and material erosion under ELM-like heat loads , 2009 .

[21]  A. Vertkov,et al.  Application of lithium in systems of fusion reactors. 1. Physical and chemical properties of lithium , 2009 .

[22]  A. Loarte,et al.  Melt damage simulation of W-macrobrush and divertor gaps after multiple transient events in ITER , 2007 .

[23]  V. I. Tereshin,et al.  Application of powerful quasi-steady-state plasma accelerators for simulation of ITER transient heat loads on divertor surfaces , 2007 .

[24]  V. Gusev,et al.  Behavior of Capillary-Porous Systems with Liquid Lithium under Influence of Pulsed Deuterium Plasma , 2019, Inorganic Materials: Applied Research.

[25]  N. Cardozo,et al.  Liquid metals as a divertor plasma-facing material explored using the Pilot-PSI and Magnum-PSI linear devices , 2017 .

[26]  Wissenschaftliche Berichte Tokamak Code TOKES Models and Implementation , 2009 .

[27]  B. Bazylev,et al.  DROPLET FORMATION AT THE W-MACROBRUSH TARGETS UNDER TRANSIENT EVENTS IN ITER , 2007 .