Divertor power spreading in DEMO reactor by impurity seeding

Zagórski, R.; Gałązka, K.; Ivanova‐Stanik, I.

doi:10.1016/j.fusengdes.2016.03.058

Cited by 7 publications

(2 citation statements)

References 13 publications

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“…In our earlier simulations for AUG with N seeding [20], we have investigated the influence of the prompt redeposition on the simulation results. It appears that the effect of the reduced sputtering yield due to the prompt re-deposition process is only important for relatively small levels of seeding [20,[26][27][28], therefore, in the present study with relatively strong and combined N and Kr seeding, the effect of the prompt re-deposition is neglected.…”

Section: Modelmentioning

confidence: 99%

COREDIV modelling of nitrogen and krypton seeding at the ASDEX Upgrade tokamak

Ivanova‐Stanik

Zagórski

Chomiczewska

et al. 2022

Plasma Phys. Control. Fusion

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Self-consistent core-scrape-off layer numerical simulations of an ASDEX-Upgrade discharge where the nitrogen (N) seeding is gradually replaced with the krypton (Kr) seeding during the plasma current flat-top phase are presented. These simulations are performed with the COREDIV code focusing on the prediction of the impurity evolution (W, Kr, N) with matched global plasma parameters: total and core radiation, temperature at the target plate and W concentration. The numerical results are compared with experimental measurements for shot #30503 at three different time points: 2.5 s (only N seeding), 4.2 s (N + Kr seeding) and 5.2 s (only Kr seeding). The calculated electron temperature at the divertor plate can be reduced to 3 eV with the highest Kr seeding. A good agreement between modelling results and experimental observations is reported.

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Section: Modelmentioning

confidence: 99%

COREDIV modelling of nitrogen and krypton seeding at the ASDEX Upgrade tokamak

Ivanova‐Stanik

Zagórski

Chomiczewska

et al. 2022

Plasma Phys. Control. Fusion

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“…It can be observed that D has a negligible influence on á ñ Z eff . It should be pointed out that for the purpose of a fusion reactor it is beneficial to keep the á ñ Z eff as low as possible to avoid fuel dilution (DEMO simulations indicate that the tolerable á ñ Z eff is in the range 2-2.5 [23]). However, for the purpose of studying radiative exhaust by different impurities we present simulations with á ñ Z eff up to about 5, what corresponds to plasmas with 0.5% of Kr or 4% of Ne.…”

Section: The Influence Of Different D ⊥mentioning

confidence: 99%

Numerical analyses of JT-60SA tokamak with tungsten divertor by COREDIV code

Gałązka

Ivanova‐Stanik

Stępniewski

et al. 2017

Plasma Phys. Control. Fusion

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An analysis of radiative power exhaust for JT-60SA tokamak with tungsten divertor is performed with the help of self-consistent, core-edge integrated COREDIV code. Two scenarios of operation (low and high density) were investigated in the scope of different parameters (electron density at the separatrix and transport in the scrape-off layer) with impurity seeding (Ne and Kr). The calculations show that in case of tungsten divertor the power load to the plate is mitigated and the central plasma dilution is smaller compared to the carbon divertor. In the most cases the energy flux through the separatrix is above the L-H transition threshold. For the high density case with neon seeding operation in full detachment mode is observed. It is demonstrated that transport in the SOL has a high influence on the result of calculations, for instance by changing the electron density on the separatrix the influx of heavy impurities (W, Kr) into the core region can be reduced.

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