Subroutines for some plasma surface interaction processes: physical sputtering, chemical erosion, radiation enhanced sublimation, backscattering and thermal evaporation

Warrier, M.; Schneider, R.; Bonnin, X.

doi:10.1016/j.cpc.2004.02.011

Cited by 46 publications

(39 citation statements)

References 22 publications

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“…and are shown in Table 1 and Table 2, where most of these were used in MD or KMC simulations [14,15,16,25] and gleaned from either experiments (E D , E HD or an educated guess was used (like ω o corresponds to typical phonon frequency [19]). The backscattering rate R is from [27]. The simulated domain of the target is 3 µm, the thickness of the co-deposit is 2 µm, and incident HIs flux Γ 0 = 10 24 atoms.m −2 .s −1 , unless stated otherwise.…”

Section: Hydrogen Isotope Retention In Porous Materialsmentioning

confidence: 99%

“…The heating module is applied here to a Be/C/W materials wall, where the heating conductivity data is obtained from [26,27]. The wall thickness (distance of surface to the cool side) is L. The coolant temperature is fixed to T 0 = 400 K.…”

Section: The Temperature Distributionmentioning

confidence: 99%

“…HT rap is HI trapping at an open bond site; HdT rap means detrapping of trapped HI atoms, SD means surface diffusion. R is the backscattering coefficient which can be calculated via [27] (same definition to metal module).…”

Section: Porosity Modulementioning

confidence: 99%

“…is the HIs implantation profile, Γ 0 is the particle flux (atom/m 2 /s), R is the backscattering coefficient which can be calculated via [27]; a is the lattice constant; C 0 t is the intrinsic trap site density; T is the temperature and k b is the Boltzmann constant. In this metal module, we assume that there is no grains or voids in the metal materials wall.…”

Section: Metal Modulementioning

confidence: 99%

See 3 more Smart Citations

Modelling of hydrogen isotope inventory in mixed materials including porous deposited layers in fusion devices

Sang¹,

Bonnin²,

Warrier³

et al. 2012

Nucl. Fusion

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Abstract.Hydrogen isotopes inventory (HII) is a key issue for fusion devices like ITER. Simultaneous use of Be, W and C as the wall material for different parts of plasmafacing components (PFCs) will bring in material mixing issues, which compound that of hydrogen isotopes retention. To simulate the hydrogen inventory in the PFCs, we have developed a flexible standalone model called HIIPC (Hydrogen Isotope Inventory Processes Code). The particle balance based model for reaction-diffusion and HII in metal and porous media (mainly carbon and co-deposited layer) is presented, coupled with a heating model which can calculate the temperature distribution. Some sample results are given to illustrate the model's capabilities and show good qualitative agreement with experiment.

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Section: Hydrogen Isotope Retention In Porous Materialsmentioning

confidence: 99%

Section: The Temperature Distributionmentioning

confidence: 99%

Section: Porosity Modulementioning

confidence: 99%

Section: Metal Modulementioning

confidence: 99%

See 2 more Smart Citations

Modelling of hydrogen isotope inventory in mixed materials including porous deposited layers in fusion devices

Sang¹,

Bonnin²,

Warrier³

et al. 2012

Nucl. Fusion

Self Cite

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“…Third, Warrier et al [25] have published subroutines implementing existing models for sputtering, chemical erosion, radiation-enhanced sublimation, backscattering and evaporation. The intriguing aspect of their package is that it includes a routine for solving a 1-D heat diffusion equation so that the surface temperature can be estimated; the surface temperature is needed to evaluate the rates for chemical erosion, radiation-enhanced sublimation, and evaporation.…”

Section: Directions For Model Improvementmentioning

confidence: 99%

Towards a revised Monte Carlo neutral particle surface interaction model

Stotler

2006

Phys. Scr.

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The components of the neutral-and plasma-surface interaction model used in the Monte Carlo neutral transport code DEGAS 2 are reviewed. The idealized surfaces and processes handled by that model are inadequate for accurately simulating neutral transport behavior in present day and future fusion devices. We identify some of the physical processes missing from the model, such as mixed materials and implanted hydrogen, and make some suggestions for improving the model.

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Plasma Edge Physics with B2‐Eirene

Schneider

Bonnin

Borraß

et al. 2006

Contrib. Plasma Phys.

483

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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Subroutines for some plasma surface interaction processes: physical sputtering, chemical erosion, radiation enhanced sublimation, backscattering and thermal evaporation

Cited by 46 publications

References 22 publications

Modelling of hydrogen isotope inventory in mixed materials including porous deposited layers in fusion devices

Modelling of hydrogen isotope inventory in mixed materials including porous deposited layers in fusion devices

Towards a revised Monte Carlo neutral particle surface interaction model

Plasma Edge Physics with B2‐Eirene

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