Experimental verification of FOREV-2D simulations for the plasma shield

Pestchanyi, S.; Landman, I.

doi:10.1016/j.jnucmat.2009.01.217

Cited by 8 publications

(3 citation statements)

References 5 publications

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“…The CFC parameters (evaporation energy, and both heat conduction coefficient and heat diffusivity) are close to that of tungsten, and will give us similar estimate of the CFC's Êmax . Thus, we see that our simple model predicts the similar values of Êmax for both CFC and tungsten (even though the radiation capabilities of carbon and tungsten are very different), which agree very well with both experimental data [14,15] and rather comprehensive numerical simulation results [36]. But what is more important is that the model shows that Êmax depends very weakly (logarithmically) on such uncertain parameters as Ėrad and q 0 .…”

Section: Plasma-wall Interaction Issues Of Vapor-plasma Shieldingsupporting

confidence: 81%

“…Experiments with plasma guns followed by rather comprehensive numerical simulations [14,15,36] have demonstrated the impact of shielding effects as a response of the wall material (both CFC and tungsten) on the incident plasma heat flux, which is as high in magnitude as the heat flux caused by giant ELMs and disruptions in ITER. In particular, the vapor plasma shielding results in the saturation of the energy (per unit surface area) accumulated by the wall at some level, Êmax , even though the total energy (per unit surface area) delivered by plasma, E 0 , can be significantly larger than Êmax (see figure 6 in [14]).…”

Section: Plasma-wall Interaction Issues Of Vapor-plasma Shieldingmentioning

confidence: 99%

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Physics of the edge plasma and first wall in fusion devices: synergistic effects

Krasheninnikov¹,

Pigarov²,

Lee³

2015

Plasma Phys. Control. Fusion

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Various synergistic effects resulting from plasma-wall interactions in magnetic fusion devices are considered. The crucial role of the first wall out-gassing processes in the recovery of pedestal density in the high-confinement mode of tokamak operation after giant type-I edge localized modes (ELMs) transient events as well as in the setting the ELM period is discussed. The shielding effects of vapor plasma formed during interactions of extremely large plasma heat fluxes with material surfaces are analyzed. The strongly non-linear impact of secondary electron emission from the divertor target on the incident plasma heat flux is discussed.

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Section: Plasma-wall Interaction Issues Of Vapor-plasma Shieldingsupporting

confidence: 81%

Section: Plasma-wall Interaction Issues Of Vapor-plasma Shieldingmentioning

confidence: 99%

Physics of the edge plasma and first wall in fusion devices: synergistic effects

Krasheninnikov¹,

Pigarov²,

Lee³

2015

Plasma Phys. Control. Fusion

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show abstract

“…Without liquefied Be in the loaded area, the main damage mechanisms were the relief of thermally induced stresses via plastic deformation and crack formation. However, it has been reported that the melting threshold for Be drops with an increasing pulse number since the thermal conductivity in the heat affected zone is significantly reduced by at least a factor of four after 100 pulses with t = 1 ms and L abs = 900 MW m −2 due to crack formation [8,9] . Thus, even though the Be melting threshold initially is not exceeded by the exerted loading conditions, it could start to melt after several shots with the same loading conditions and then the observed BeO driven damage acceleration could be enabled.…”

Section: Damage Evolution With Pulse Numbermentioning

confidence: 99%

Investigation of damages induced by ITER-relevant heat loads during massive gas injections on Beryllium

Spilker

Linke

Pintsuk

et al. 2016

Nuclear Materials and Energy

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a b s t r a c tMassive gas injections (MGIs) will be used in ITER to mitigate the strong damaging effect of full performance plasma disruptions on the plasma facing components. The MGI method transforms the stored plasma energy to radiation that is spread across the vacuum vessel with poloidal and toroidal asymmetries. This work investigated the impact of MGI like heat loading on the first wall armor material beryllium. ITER-relevant power densities of 90-260 MW m −2 in combination with pulse durations of 5-10 ms were exerted onto the S-65 grade beryllium specimens in the electron beam facility JUDITH 1. All tested loading conditions led to noticeable surface morphology changes and in the expected worst case scenario, a crater with thermally induced cracks with a depth of up to ∼340 μm formed in the loaded area. The level of destruction in the loaded area was strongly dependent on the pulse number but also on the formation of beryllium oxide. The cyclic melting of beryllium could lead to an armor thinning mechanism under the presence of melt motion driving forces such as surface tension, magnetic forces, and plasma pressure.

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Optimization of MGI in JET using the TOKES code and mitigation of RE damage for the first wall

Pestchanyi

Boboc

Базылев

et al. 2014

Fusion Engineering and Design

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Experimental verification of FOREV-2D simulations for the plasma shield

Cited by 8 publications

References 5 publications

Physics of the edge plasma and first wall in fusion devices: synergistic effects

Physics of the edge plasma and first wall in fusion devices: synergistic effects

Investigation of damages induced by ITER-relevant heat loads during massive gas injections on Beryllium

Optimization of MGI in JET using the TOKES code and mitigation of RE damage for the first wall

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