Effect of core-edge coupling on operation regimes of ITER-like reactor

Stankiewicz, R.; Zagórski, R.

doi:10.1016/s0022-3115(02)01473-3

Cited by 15 publications

(12 citation statements)

References 8 publications

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“…First the general plasma performance in the FAST tokamak has been analyzed in the frame of a relatively simple self-consistent description of the core and edge plasma. Secondly, the simulations of the plasma parameters in the scrape-off layer and divertor region have been done with the help of a more sophisticated 2D multi-fluid model of the boundary plasma implemented in the COREDIV code [3,4]. In the simple model the edge plasma density is prescribed at the stagnation point (upstream plasma density n sep ) and used as input parameter.…”

Section: Computing Toolsmentioning

confidence: 99%

Edge plasma physics issues for the Fusion Advanced Studies Torus (FAST) in reactor relevant conditions

Maddaluno

Zagórski²,

Ridolfini

et al. 2009

Nucl. Fusion

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The issue of "First wall materials & compatibility with ITER /DEMO relevant plasmas" is among the R&D missions for possible new European plasma fusion devices that the FAST project will address. FAST can operate with ITER relevant values of P/R (up to 22 MW/m, against the ITER 24 MW/m, inclusive of the particles power), thanks to its compactness; thus it can investigate the physics of large heat loads on divertor plates. The FAST divertor will be made of bulk W tiles, for basic operations, but also fully toroidal divertor targets made of liquid lithium (L-Li) are foreseen. To have reliable predictions of the thermal loads on the divertor plates and of the core plasma purity a number of numerical self-consistent simulations have been made for the H-mode and steady-state scenario by using the code COREDIV. This code, already validated in the past on experimental data (namely JET, FTU, Textor), is able to describe self-consistently the core and edge plasma in a tokamak device by imposing the continuity of energy and particle fluxes and of particle densities and temperatures at the separatrix. In the present work the results of such calculations will be illustrated, including heat loads on the divertor. The overall picture shows that, marginally in the intermediate and, necessarily in the high density H-mode scenarios (=2 and 5·10 20 m -3 respectively), impurity seeding should be foreseen with W as target material: however, only a small amount of Ar (0.03% atomic concentration), not affecting the core purity, is sufficient to maintain the divertor peak loads below 18 MW/m 2 , that represents the safety limit for the W monoblock technology, presently accepted for the ITER divertor tiles. Li always needs additional impurities for decreasing divertor heat loads, the Z eff value being than 1.8. At low plasma densities (but 1.3·10 20 m -3 ), typical of steady state regimes, W by alone is effective in dissipating the input power by radiative losses, without excessive core contamination. Impurity seeding would lead to excessive W sputtering by Ar and too high Z eff . The impact of the ELMs on the divertor in the case of a good H-mode with low pedestal dimensionless collisionality will be discussed too.

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Section: Computing Toolsmentioning

confidence: 99%

Edge plasma physics issues for the Fusion Advanced Studies Torus (FAST) in reactor relevant conditions

Maddaluno

Zagórski²,

Ridolfini

et al. 2009

Nucl. Fusion

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“…Two basic approaches are usually used in order to tackle the problem. In the first one the time evolution of the whole system is studied with various levels of approximation and complexity of the model applied to both parts of the system [1][2][3][4]. A review of the different models is presented in [3].…”

Section: Introductionmentioning

confidence: 99%

“…In this paper, operation regimes of a fusion reactor in the presence of seeded impurity are analyzed with the help of the COREDIV code [4], which was recently extended to include the transport of several sputtered and/or injected impurities. An efficient iteration procedure has been developed for finding the stationary solution of the problem [4].…”

Section: Introductionmentioning

confidence: 99%

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Influence of core–edge coupling and impurities on the operation regimes of a fusion reactor

Stankiewicz

Zagórski

2005

Journal of Nuclear Materials

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“…The codes usually follow the time evolution of the whole system and require large computation time due to small time scale involved in the problem. The authors developed the code COREDIV with efficient iteration scheme for finding the stationary solution [4,5]. The COREDIV model consists of the 1D radial transport in the core plasma which has been coupled to the 2D multifluid code EPIT describing plasma transport in the edge.…”

Section: Introductionmentioning

confidence: 99%

Influence of seeded impurities on the fusion reactor operation

Stankiewicz

Zagórski

2004

Czech. J. Phys.

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In order to study the influence of seeded impurities on ITER -like reactor operation the COREDIV code has been extended to include the transport of several sputtered and/or injected impurities. In the COREDIV code the core plasma is treated in the frame of 1D radial transport model whereas in the edge the 2D multifluid code EPIT is used. The EPIT code solves in the slab geometry the MHD equations for densities and velocities for all ions species as well as for electron and ion temperatures. The iteration scheme in the code leads to steady state solution of coupled core and SOL system. The numerical results for Carbon and Nickel plate and seeded impurities Silicon and Neon are presented.PACS : 52.55.Fa

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Effect of core-edge coupling on operation regimes of ITER-like reactor

Cited by 15 publications

References 8 publications

Edge plasma physics issues for the Fusion Advanced Studies Torus (FAST) in reactor relevant conditions

Edge plasma physics issues for the Fusion Advanced Studies Torus (FAST) in reactor relevant conditions

Influence of core–edge coupling and impurities on the operation regimes of a fusion reactor

Influence of seeded impurities on the fusion reactor operation

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