A one shot method for divertor target shape optimization

Dekeyser, Wouter; Reiter, D.; Baelmans, Martine

doi:10.1002/pamm.201410487

Cited by 10 publications

(15 citation statements)

References 8 publications

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“…Given these promising results, further progress can now be made towards computationally affordable simulations of reactor‐relevant plasmas. Concerning numerics, the first step should be the introduction of a nine‐point stencil to accurately capture the isotropic‐neutral transport in non‐orthogonal grid geometries . Secondly, a grid extending up to the vessel wall is necessary to model the neutrals in realistic test cases.…”

Section: Discussion and Outlookmentioning

confidence: 99%

“…It should be noted that, in contrast to the plasma, neutrals are transported isotropically, therefore requiring a nine‐point stencil for their discretization . As this feature is currently absent in the SOLPS‐ITER code, we perform this benchmark on an orthogonal grid, using a so‐called slab case.…”

Section: Comparison To Eirene Kinetic Simulation Of Neutralsmentioning

confidence: 99%

“…It should be noted that, in contrast to the plasma, neutrals are transported isotropically, therefore requiring a nine-point stencil for their discretization. [11] As this feature is currently absent in the SOLPS-ITER code, we perform this benchmark on an orthogonal grid, using a so-called slab case. In this simplified geometry, it is assumed that theand r-directions coincide with the vertical and radial coordinates of a cylindrical coordinate system with the origin at the central symmetry axis of the tokamak, as depicted in Figure 1.…”

Section: Case Set-upmentioning

confidence: 99%

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Implementation of a consistent fluid‐neutral model in SOLPS‐ITER and benchmark with EIRENE

Blommaert

Dekeyser

Horsten

et al. 2018

Contributions to Plasma Physics

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In the quest for computationally affordable plasma edge transport simulations of reactor‐relevant plasmas, we consider fluid‐neutral models in this paper. To obtain good agreement with kinetic‐neutral models in charge‐exchange dominated regimes, model equations, transport coefficients, and boundary conditions have to be derived consistently from the kinetic description. In this paper, we describe a fully fluid plasma edge transport model that is aimed at reproducing the results of coupled finite‐volume/Monte Carlo runs with the kinetic Monte Carlo code EIRENE as closely as possible. To this end, we incorporate the rate coefficients from the AMJUEL reaction database, and boundary conditions are based on the reflection data from TRIM. The fluid‐neutral model is implemented into the SOLPS‐ITER code suite to compare the plasma sources with those of EIRENE on a simplified slab geometry. For a detached case, the results show a nearly perfect match between the fluid and kinetic model, with errors locally ranging up to a maximum discrepancy of 10% for particle and electron heat sources and 30% for parallel momentum sources. These very localized errors can be largely attributed to the discretization error, mainly near the ionization peak.

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Section: Discussion and Outlookmentioning

confidence: 99%

Section: Comparison To Eirene Kinetic Simulation Of Neutralsmentioning

confidence: 99%

Section: Case Set-upmentioning

confidence: 99%

See 1 more Smart Citation

Implementation of a consistent fluid‐neutral model in SOLPS‐ITER and benchmark with EIRENE

Blommaert

Dekeyser

Horsten

et al. 2018

Contributions to Plasma Physics

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“…For further details on deriving the exact adjoint state equations, the reader is referred to Ref. []. Finally, using the adjoint of the linearization with respect to the design variables ∂ ϕ c * ( ϕ , q ), it is found that the gradient can be expressed in the following way:

\nabla \overset{J}{true} ((), ϕ) = \nabla_{ϕ} scriptJ ((),, ϕ, q) + \partial_{ϕ} c^{*} ((),, ϕ, q) q^{*} .

…”

Section: Optimizationmentioning

confidence: 99%

Towards numerical optimization of snowflake topologies

Kerkhof

Blommaert

Heumann

et al. 2018

Contributions to Plasma Physics

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In this paper, the framework for gradient‐based optimization of snowflake magnetic divertor topologies is discussed. A continuous in‐parts adjoint approach is adopted to calculate the gradient. A robust grid generator developed within the in‐house DivOpt code enables different topologies in an automated way. However, a large flux expansion exists near second‐order and closely spaced first‐order X‐points. This might induce significant discretization errors. As accurate gradients are needed for the correct functioning of the numerical optimization algorithm, the importance of the discretization error is assessed by calculating the gradient with both finite differences and the continuous adjoint approach on three systematically refined grids. It is shown that sufficiently fine grids are needed to achieve accurate gradient calculation and a corresponding good functioning of the optimization algorithm.

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“…Therefore, the inverse transformation G´1 2 will be used to transform fluxes over iso-x and iso-y lines back to fluxes in the pθ, rq coordinate system and discretize the equations there. The computational stencil is then extended to compute correction terms resulting from the nonalignment of the radial lines with the coordinate axis e r [32]. It is for this reason that the plasma edge equations in section 3.3 will be presented in the pθ, rq-coordinate system, with the metric coefficients h θ , h r , and the Jacobian ?…”

Section: A Coordinate Transformation For Anisotropic Plasma Edge Tranmentioning

confidence: 99%

Towards Automated Magnetic Divertor Design for Optimal Heat Exhaust

et al. 2016

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Abstract. Avoiding excessive structure heat loads in future fusion tokamaks is regarded as one of the greatest design challenges. In this paper, we aim at developing a tool to study how the severe divertor heat loads can be mitigated by reconfiguring the magnetic confinement. For this purpose, a free boundary equilibrium code is integrated with a plasma edge transport code to work in an automated fashion. Next, a practical and efficient adjoint based sensitivity calculation is proposed to evaluate the sensitivities of the integrated code. The sensitivity calculation is finally applied to a realistic test case and compared with finite difference sensitivity calculations.

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A one shot method for divertor target shape optimization

Cited by 10 publications

References 8 publications

Implementation of a consistent fluid‐neutral model in SOLPS‐ITER and benchmark with EIRENE

Implementation of a consistent fluid‐neutral model in SOLPS‐ITER and benchmark with EIRENE

Towards numerical optimization of snowflake topologies

Towards Automated Magnetic Divertor Design for Optimal Heat Exhaust

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