Kinetic models of ELMs burst

Sigmar, D. J.; Batishcheva, A. A.; Batishchev, Oleg; Krasheninnikov, S. I.; Catto, Peter J.

doi:10.1002/ctpp.2150360224

Cited by 9 publications

(6 citation statements)

References 2 publications

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“…In the fast phase, the distribution function cannot equilibrate, and kinetic effects reduce the parallel heat conduction by a factor of two, according to modelling in [292,293]. These fast and slow features are also reproduced by one dimensional ELM modelling for JET [294].…”

Section: Modelling Of Time Dependent Phenomena (Elms)mentioning

confidence: 89%

Chapter 4: Power and particle control

Divertor¹,

Database²,

Editors³

1999

Nucl. Fusion

282

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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: Modelling Of Time Dependent Phenomena (Elms)mentioning

confidence: 89%

Chapter 4: Power and particle control

Divertor¹,

Database²,

Editors³

1999

Nucl. Fusion

282

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“…Results from kinetic modelling [95,96] show that in this phase the distribution function is unable to equilibrate. One gets an elevated tail and a much larger heat conduction coefficient (factor of ten compared with the Maxwellian value) in the region between the heat front and the target.…”

Section: Limitationsmentioning

confidence: 97%

Plasma Edge Physics with B2‐Eirene

Schneider

Bonnin

Borraß

et al. 2006

Contrib. Plasma Phys.

484

426

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The B2‐Eirene code package was developed to give better insight into the physics in the scrape‐off layer (SOL), which is defined as the region of open field‐lines intersecting walls. The SOL is characterised by the competition of parallel and perpendicular transport defining by this a 2D system. The description of the plasma‐wall interaction due to the existence of walls and atomic processes are necessary ingredients for an understanding of the scrape‐off layer. This paper concentrates on understanding the basic physics by combining the results of the code with experiments and analytical models or estimates. This work will mainly focus on divertor tokamaks, but most of the arguments and principles can be easily adapted also to other concepts like island divertors in stellarators or limiter devices. The paper presents the basic equations for the plasma transport and the basic models for the neutral transport. This defines the basic ingredients for the SOLPS (Scrape‐Off Layer Plasma Simulator) code package. A first level of understanding is approached for pure hydrogenic plasmas based both on simple models and simulations with B2‐Eirene neglecting drifts and currents. The influence of neutral transport on the different operation regimes is here the main topic. This will finish with time‐dependent phenomena for the pure plasma, so‐called Edge Localised Modes (ELMs). Then, the influence of impurities on the SOL plasma is discussed. For the understanding of impurity physics in the SOL one needs a rather complex combination of different aspects. The impurity production process has to be understood, then the effects of impurities in terms of radiation losses have to be included and finally impurity transport is necessary. This will be introduced with rising complexity starting with simple estimates, analysing then the detailed parallel force balance and the flow pattern of impurities. Using this, impurity compression and radiation instabilities will be studied. This part ends, combining all the elements introduced before, with specific, detailed results from different machines. Then, the effect of drifts and currents is introduced and their consequences presented. Finally, some work on deriving scaling laws for the anomalous turbulent transport based on automatic edge transport code fitting procedures will be described. (© 2006 WILEY‐VCH Verlag GmbH & Co. KGaA, Weinheim)

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“…The effect of kinetic corrections on fluid like transport codes was investigated using parametric studies [42,101]. Increase in computing speed has recently allowed kinetic simulations of transient events such as ELMs [9,19,35,118,125,[128][129][130][131], and self-consistent modelling of ion orbit losses from the edge plasma [45-48, 77, 83, 91, 120, 141]; disruption thermal-quench modelling is envisioned in the near future [107]. Other topics include the role of neutrals [82,139], magnetic field ergodization [14] and impact on edge and SOL turbulence [15,32,33,111,140].…”

Section: Referencementioning

confidence: 99%

Parallel heat flux limits in the tokamak scrape-off layer

Fundamenski

2005

Plasma Phys. Control. Fusion

102

142

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It is well known that the classical Spitzer-Harm-Braginskii expression for the parallel plasma heat flux breaks down in the long mean free path limit, relevant to many practical applications, most crucially power exhaust via the tokamak scrape-off layer (SOL). This problem is usually addressed by limiting the heat flux to some fraction of the free streaming value, with constants of proportionality α σ , where σ ∈ {e, i}, ranging from 0.03 to 3. The following paper presents a brief overview of the problem, compares the results of various kinetic studies, suggests the optimal values of α σ for use in plasma-fluid codes, and examines the impact of these values on 2D SOL simulations using the EDGE2D transport code. In this context, gyro-kinetic parallel heat flux expressions for both electrons and ions are derived from the generalized transport equations-an improved version of Grad's 21-moment approach-and their implications to tokamak modelling are discussed.

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Kinetic models of ELMs burst

Cited by 9 publications

References 2 publications

Chapter 4: Power and particle control

Chapter 4: Power and particle control

Plasma Edge Physics with B2‐Eirene

Parallel heat flux limits in the tokamak scrape-off layer

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