Scaling of ITER divertor parameters – interpolation from 2D modelling and extrapolation

Pacher, H.D.; Kukushkin, A. S.; Pacher, G.W.; Janeschitz, G.

doi:10.1016/s0022-3115(02)01374-0

Cited by 31 publications

(69 citation statements)

References 5 publications

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“…A number of modelling results on the performance of the ITER divertor have been obtained in last five years [511,516,253,29,517,20,513,512,515] as new experimental results have been obtained, further physical effects have been included and a design optimisation of ITER toward lower cost has been performed. The primary aim of the studies has been the identification of the major control parameters, the exploration of the operational window, the investigation of the effect of divertor geometry, and the development of integrated modelling of the whole plasma by coupling of the edge and core models at their interface.…”

Section: Modelling Resultsmentioning

confidence: 99%

“…has been developed [517,20,512] providing a set of boundary conditions for the core plasma models and thus allowing consistent modelling of the whole ITER plasma [520,521,522]. Moreover, the results obtained with different assumptions on the surface composition can be put in a linear order and be then unified in the same scaling by introducing one more artificial input parameter [512].…”

Section: Modelling Resultsmentioning

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: Modelling Resultsmentioning

confidence: 99%

Section: Modelling Resultsmentioning

confidence: 99%

Chapter 4: Power and particle control

Loarte¹,

et al. 2007

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“…The edge and divertor plasma is modelled with the B2-Eirene code package, version solps4.2, employing a full multi-fluid description of the electrons and D, He, and C ions [1,2]. For most of the studies here, computational time limitations restricted our study to the linear neutral package (neither neutral-neutral collisions nor molecular kinetics) in toroidal geometry in EIRENE, but several studies were performed with the more complete non-linear Monte-Carlo neutral model as in [3].…”

Section: Edge and Divertor Modelling Of Iter And Demo Including Alsomentioning

confidence: 99%

Effect of the tokamak size in edge transport modelling and implications for DEMO

Pacher

Kukushkin

Pacher

et al. 2007

Journal of Nuclear Materials

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The edge plasma of four devices, AUG, JET, ITER and a prototypical DEMO near ignition, is modelled with B2-EIRENE with a linear neutral model, carbon impurity, and variable throughput and scrape-off layer power. The scaling from ITER to DEMO is quantified as a power law scaling in device size, and JET and AUG simulations are compared to this scaling. Compared to ITER at the same scrape-off layer power per unit device volume and the same operating point relative to the edge-based density limit, edge helium density and peak power per unit area is found to be similar, and helium influx lower, for DEMO with impurity seeding. With a full neutral model, helium parameters are improved by a factor 3. Results of core modelling show that ignited operation of DEMO is possible with the impurity seeding required to render peak power loads compatible with a helium-cooled divertor. ________________________________________________________________ JNM keywords: T0100, P0500, P0600 2

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“…1a) [3]. Use of this parameter, p DT , ensures a good parameterization of the modelling results [4,5].…”

Section: Definition Of Neutral Gas Parametersmentioning

confidence: 99%

“…The effective pumping speed S DT used in [1][2][3][4][5][6] is related, but not proportional, to the pumping speed at the pump duct. Indeed, the neutrals at the PFR interface have a high (several eV) energy whereas the engineering pumping speed is evaluated at room temperature.…”

Section: Definition Of Neutral Gas Parametersmentioning

confidence: 99%

Effect of the dome on divertor performance in ITER

Kukushkin

Pacher

Kotov

et al. 2007

Journal of Nuclear Materials

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The effect of variation of the divertor geometry in ITER is re-evaluated with the recently developed non-linear model of the transport of the neutral particles, taking into account neutral-neutral and molecule-ion collisions. The importance of the "dome" for the neutral gas compression in the divertor is confirmed. Unlike earlier studies with a linear model of neutral transport, the present results show only a weak sensitivity of the divertor performance to the details of the divertor shape.

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Scaling of ITER divertor parameters – interpolation from 2D modelling and extrapolation

Cited by 31 publications

References 5 publications

Chapter 4: Power and particle control

Chapter 4: Power and particle control

Effect of the tokamak size in edge transport modelling and implications for DEMO

Effect of the dome on divertor performance in ITER

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