High Mach flow associated with X point MARFE and plasma detachment

Hatayama, A.; Segawa, H.; Schneider, R.; Coster, D.; Hayashi, Nobuhiko; Sakurai, S.; Asakura, N.; Ogasawara, Masatada

doi:10.1088/0029-5515/40/12/305

Cited by 33 publications

(35 citation statements)

References 39 publications

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“…Direct measurements of the private flux region E r ~ 3T e /λ q ~ 5-20 kV/m [54,130,131] suggests that E×B fluxes are comparable to the parallel fluxes under attached conditions, but are substantially smaller following detachment [131]. Enhancement of the divertor parallel flows upon detachment have been both measured [130,6] and simulated using UEDGE and B2 [132,133].…”

Section: Sol Flow and Classical Drifts Effectsmentioning

confidence: 98%

Chapter 4: Power and particle control

Loarte¹,

et al. 2007

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Abstract.Progress, since the ITER Physics Basis publication, in understanding the processes that will determine the properties of the plasma edge and its interaction with material elements in ITER is described. Experimental areas where significant progress has taken place are : energy transport in the SOL in particular of the anomalous transport scaling, particle transport in the SOL that plays a major role in the interaction of diverted plasmas with the main chamber material elements, ELM energy deposition on material elements and the transport mechanism for the ELM energy from the main plasma to the plasma facing components, the physics of plasma detachment and neutral dynamics including the edge density profile structure and the control of plasma particle content and He removal, the erosion of low and high Z materials in fusion devices, their transport to the core plasma and their migration at the plasma edge including the formation of mixed materials, the processes determining the size and location of the retention of tritium in fusion devices and methods to remove it and the processes determining the efficiency of the various fuelling methods as well as their development towards the ITER requirements. This experimental progress has been accompanied by the development of modelling tools for the physical processes at the edge plasma and plasma-materials interaction and the further validation of these models by comparing their predictions with the new experimental results. Progress in the modelling development and validation has been mostly concentrated in the following areas : refinement of the predictions for ITER with plasma edge modelling codes by inclusion of detailed geometrical features of the divertor and the introduction of physical effects, which can play a 2 major role in determining the divertor parameters at the divertor for ITER conditions such as hydrogen radiation transport and neutral-neutral collisions, modelling of the ion orbits at the plasma edge, which can play a role in determining power deposition at the divertor target, models for plasma-materials and plasma dynamics interaction during ELMs and disruptions, models for the transport of impurities at the plasma edge to describe the core contamination by impurities and the migration of eroded materials at the edge plasma and its associated tritium retention and models for the turbulent processes that determine the anomalous transport of energy and particles across the SOL. The implications for the expected performance of the reference regimes in ITER, the operation of the ITER device and the lifetime of the plasma facing materials are discussed. Introduction.This chapter outlines the significant progress achieved since the ITER Physics Basis in understanding basic scrape-off layer (SOL) and divertor processes in a tokamak. The interaction of plasma with first-wall surfaces will have considerable impact on the performance of fusion plasmas, the lifetime of plasma facing components, and the retention of tritium in next step Burning Plasma E...

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Section: Sol Flow and Classical Drifts Effectsmentioning

confidence: 98%

Chapter 4: Power and particle control

Loarte¹,

et al. 2007

Self Cite

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“…As was discussed in Ref. [6][7][8], the driving mechanism of this HMAD is explained as follows: 1) the decrease in the electron temperature toward the target plate along the field line leads to the clear separation of the ionization region near the X-point and the momentum loss region in front of the target plate, 2) the static pressure drops in the ionization region mainly due to the rapid decrease in T e along the field line, while the total (static and dynamic) pressure is being kept almost constant, and 3) the dynamic pressure increases due to 1) and 2).…”

Section: Simulation Modelmentioning

confidence: 86%

“…Recently, numerical simulation by using SOLPS 4.0 code [3][4][5] has been done to clarify the physical mechanism of the HMAD [6]. In addition, comparisons of numerical results with the experimental data in JT-60U were done.…”

Section: Introductionmentioning

confidence: 99%

“…In addition, comparisons of numerical results with the experimental data in JT-60U were done. The effects of the divertor geometry on the HMAD were also studied [7]. However, in these analyses [6,7], the effects of drifts and current were not taken into account.…”

Section: Introductionmentioning

confidence: 99%

“…The effects of the divertor geometry on the HMAD were also studied [7]. However, in these analyses [6,7], the effects of drifts and current were not taken into account. These effects possibly affect the HMAD and the flow structure in the detached state in the divertor region.…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Effect of Drifts on the Plasma Flow in the Detachment

Hoshino

Hatayama

Kawashima

et al. 2006

Contrib. Plasma Phys.

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The effects of the drifts have been studied on the high parallel Mach flows near the X-point associated with the divertor plasma detachment. Numerical calculations using a 2D edge plasma simulation code (the SOLPS 5.0 code) have been applied to the analysis of the JT-60U W-shaped divertor plasmas. The following three cases are compared for the detached plasma: without the drifts, with only the diamagnetic drift, with both of the diamagnetic drift and the E × B drift. The parallel Mach number near the separatrix with both drifts becomes slightly larger than the results obtained without drifts or with only the diamagnetic drift. This increase in the parallel Mach number near the separatrix is mainly due to the radial E × B drift. However, the main features and the basic mechanism of the high Mach flows near the X-point associated with the divertor plasma detachment still remain unchanged even under the presence of the effects of drifts.

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Simple Core‐SOL‐Divertor Model To Investigate Plasma Operational Space

Hiwatari

Kuzuyama

Hatayama

et al. 2004

Contrib. Plasma Phys.

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We develop a simple Core‐SOL‐Divertor (C‐S‐D) model to investigate the core and edge operational space. To construct the integrated C‐S‐D model, 0D core plasma model of ITER physics guidelines and two‐point SOLdivertor model are applied. To get the reasonable boundary condition at the core‐edge interface, we investigate the particle balance for the divertor, SOL, and core plasma region, respectively. Moreover, we apply the C‐S‐D model to LH transition phase of ITER and compare with the scaling model, which consists of the two‐point model and the SOL density scaling law. According to the above comparison, we find that the particle flux across the separatrix should be applied for the boundary condition in case of the transition phenomena. In addition, the oscillation of the divertor density at the LH transition is predicted. This oscillation has a possibility to have an effect on the divertor operation of ITER. (© 2004 WILEY‐VCH Verlag GmbH & Co. KGaA, Weinheim)

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High Mach flow associated with X point MARFE and plasma detachment

Cited by 33 publications

References 39 publications

Chapter 4: Power and particle control

Chapter 4: Power and particle control

Effect of Drifts on the Plasma Flow in the Detachment

Simple Core‐SOL‐Divertor Model To Investigate Plasma Operational Space

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