Comparison of B2-EIRENE calculations with multi-machine experimental measurements

Loarte, A.; Kukushkin, A.S.; Pacher, H.D.; Coster, D.; Schneider, R.; Asakura, N.; Itami, K.; LaBombard, B.; Lipschultz, B.; Maggi, C. F.; Monk, R.D.; Porter, G. D.; Shimada, M.; Sugihara, M.; Terry, J.

doi:10.1016/s0022-3115(98)00685-0

Cited by 16 publications

(17 citation statements)

References 22 publications

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“…In interpretative mode, these free parameters are adjusted to fit the experimental data; this leads to different values of cross-field diffusivities resulting from fits to different experiments [502] (see also section 4.2.1). Predictive modelling, such as extrapolation to ITER, requires then a choice of these free parameters on the basis of other constraints.…”

Section: Model Parametersmentioning

confidence: 99%

“…The cross-field transport, which determines the profile, should then be constrained by considerations of Larmor radius and stability. First, the profile width must be larger than the poloidal Larmor radius of the ions, which is the measure of radial excursion of the banana particle orbits in the SOL, thus eliminating for ITER modelling the lower of the diffusivities fitting the experiment [502].…”

Section: Model Parametersmentioning

confidence: 99%

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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: Model Parametersmentioning

confidence: 99%

Section: Model Parametersmentioning

confidence: 99%

Chapter 4: Power and particle control

Loarte¹,

et al. 2007

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“…This grid leaves large gaps between the main wall and the last ring of grid cells, but is commonly used by plasma codes such as SOLPS (B2/Eirene) due to the rectangular data structure of the grid cells. The background plasma (pure deuterium) is generated by DIVIMP "sol28" option, an onion skin model (OSM) with particle and momentum conservation [13,14,15] and 6 successive iterations with Eirene07 [16]. Experimental electron temperature (T e ) and density profiles (n e ) from Langmuir probe data are used as constraints for the OSM in the divertor and outer mid plane.…”

Section: Application Of the Model To Jetmentioning

confidence: 99%

Interpretation of Be migration studies at JET and validation of an integrated numerical model for plasma impurity transport and wall composition dynamics

Reinelt

Krieger

Lisgo

et al. 2011

Journal of Nuclear Materials

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Abstract:Fusion experiments with wall cladding of different chemical elements face the problem of material mixing by the plasma-wall interaction. Understanding of experiments that investigate this long term material re-distribution require an iterative approach that takes the local erosion, the global transport of material by the scrape-off layer (SOL) plasma and the local redeposition into account. We present a model that combines parameterized DIVIMP calculations and a simplified sputtering model to simulate the time evolution of first wall material migration in a fusion experiment. The simulations are benchmarked by Be evaporation experiments performed previously at JET. The time evolution of the spectroscopically measured Be erosion fluxes for 800 s total plasma time at the main wall and inner divertor can be reproduced by the model using an extended calculation grid for DIVIMP and an increased cross field diffusivity for impurity ions in the SOL. Discrepancies were found in the outer divertor region.

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“…For the D a profile, a difference between the experimental measurements and the modelling results can also be found, especially at the inner SOL part. The difference between the experimental measurements and the modelling results for the D a profile may come from the crude treatment of In order to get the modelling results for the validation assessment of the models in the coupling version of edge plasma transport code B2-Eirene, B2-Eirene has been used for modelling L-mode shot 24830 on JT-60U tokamak [11]. In the modelling the radial transport coefficients without spatial dependent were chosen, i.e.…”

Section: Introductionmentioning

confidence: 99%