Analysis of performance of the optimized divertor in ITER

Kukushkin, A.S.; Pacher, H.D.; Loarte, A.; Komarov, V.; Kotov, V.; Merola, M.; Pacher, G.W.; Reiter, D.

doi:10.1088/0029-5515/49/7/075008

Cited by 120 publications

(113 citation statements)

References 8 publications

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“…The two candidate mechanisms [13,[54][55][56] are neutral fueling and a particle pinch, the latter mechanism being beneficial for ITER, which will have a narrow neutral penetration length [57]. A nonlinear TEM simulation produced a particle flux Γ/Γ GB = 6.8 ± 1.1, with Γ GB = n 0 c s ρ 2 s /a 2 (for reference, the neoclassical contribution to the particle flux was calculated by GENE to be Γ N C /Γ GB = 1.54).…”

Section: A Phase S3mentioning

confidence: 99%

Gyrokinetic study of ASDEX Upgrade inter-ELM pedestal profile evolution

et al. 2015

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The gyrokinetic GENE code is used to study inter-ELM H-mode pedestal profile evolution for an ASDEX Upgrade discharge. Density gradient driven trapped electron modes (TEM) are the dominant pedestal instability during the early density-buildup phase. Nonlinear simulations produce particle transport levels consistent with experimental expectations. Later inter-ELM phases appear to be simultaneously constrained by electron temperature gradient (ETG) and kinetic ballooning mode (KBM) turbulence. The electron temperature gradient achieves a critical value early in the ELM cycle, concurrent with the appearance of both microtearing modes (MTM) and ETG modes. Nonlinear ETG simulations demonstrate that the profiles lie at a nonlinear critical gradient. The nominal profiles are stable to KBM, but moderate increases in β are sufficient to surpass the KBM threshold. Certain aspects of the dynamics support the premise of KBM-constrained pedestal evolution; the density and temperature profiles separately undergo large changes, but in a manner that keeps the pressure profile constant and near the KBM limit.

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Section: A Phase S3mentioning

confidence: 99%

Gyrokinetic study of ASDEX Upgrade inter-ELM pedestal profile evolution

et al. 2015

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“…The calculations are performed for the current reference configuration F57 [4]. The computational grid is shown in Fig.…”

Section: Main Plasma and First Wallmentioning

confidence: 99%

Numerical estimates of the ITER first mirrors degradation due to atomic fluxes

Kotov

Reiter

Kukushkin

et al. 2011

Fusion Engineering and Design

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“…It is in that particular region that the most intense interactions between the plasma and the plasma-facing components take place. The partially detached plasma in the divertor region are expected to have a high electron density (10 20 -10 21 m −3 ) and electron temperatures of 1 -10 eV [2,3]. This leads to extremely intense particle and heat flux densities on the divertor of ∼10 24 ions m −2 s −1 and ∼10 MW m −2 , respectively.…”

Section: Introductionmentioning

confidence: 99%

Surface morphology and deuterium retention of tungsten after low- and high-flux deuterium plasma exposure

Hoen¹,

Balden²,

Manhard³

et al. 2014

Nucl. Fusion

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Abstract.The surface morphology and deuterium retention were investigated of polycrystalline tungsten targets that were exposed to deuterium plasmas at widely varying conditions. By changing only one parameter at a time, the isolated effects of flux, time and pre-damaging on surface modifications and deuterium retention were studied. The sample exposed to low-flux plasma (10 20 m −2 s −1 ) is mostly smooth with only a few areas containing very large blisters (50 -500 µm). The samples exposed to high-flux plasmas (10 24 m −2 s −1 ) show large numbers of smaller blisters (1 -10 µm) and in addition even smaller protrusions (<750 nm). The size of the blisters and their density strongly increase with fluence. Pre-damaging tungsten with MeV ions leads to less blisters but to more protrusions. In addition to these (sub-)micrometer-sized structures, all samples show formation of nanostructures. Comparison of a low-flux and high-flux sample exposed to similar fluence showed that the variation in morphology is dominated by the flux differences. It is shown that the blisters and protrusions originate in inter-and intra-granular cavities, respectively. The depth of the cavities underneath the surface correlates well with the depth distributions of the retained deuterium. Trapping of significant amounts of deuterium therefore seems to take place in and/or close to these cavities and gives rise to an additional peak in the thermal desorption spectrum at 700 K.PACS numbers: 28.52.Fa, 28.52. Nh, 52.40.Hf, 52.77.Dq, 61.80.Jh, Submitted to: Nuclear Fusion Surface morphology and deuterium retention at high-flux deuterium plasmas 2

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Analysis of performance of the optimized divertor in ITER

Cited by 120 publications

References 8 publications

Gyrokinetic study of ASDEX Upgrade inter-ELM pedestal profile evolution

Gyrokinetic study of ASDEX Upgrade inter-ELM pedestal profile evolution

Numerical estimates of the ITER first mirrors degradation due to atomic fluxes

Surface morphology and deuterium retention of tungsten after low- and high-flux deuterium plasma exposure

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