2017
DOI: 10.1134/s1063780x1711006x
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Improvement of plasma energy confinement in tokamak under radiative cooling of the edge plasma

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Cited by 8 publications
(18 citation statements)
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“…It is important to check that this is valid also for He, which has Z = 2 and radiates at the very edge of the plasma. In T-10 experiments [12], it was shown that W d saturated at the same level for Ne and He injection for other similar conditions. Plasma in this tokamak was bounded with a circular metal limiter.…”
Section: Dependence Of Energy Confinement On Radiation Lossesmentioning
confidence: 81%
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“…It is important to check that this is valid also for He, which has Z = 2 and radiates at the very edge of the plasma. In T-10 experiments [12], it was shown that W d saturated at the same level for Ne and He injection for other similar conditions. Plasma in this tokamak was bounded with a circular metal limiter.…”
Section: Dependence Of Energy Confinement On Radiation Lossesmentioning
confidence: 81%
“…To understand this phenomenon, special experiments were performed in the T-10 tokamak (major radius of toroidal plasma R = 1.5 m, minor radius a = 0.3 m), where, in addition to ohmic heating (OH), plasma was heated by ECR power [12]. It has been shown that in conditions where the plasma density is maintained constant by a feedback system (Figure 4), the stored energy W d is independent of the plasma density ( Figure 4a); W d may be increased by 40% due to the Ne injection with a constant density (within 10%).…”
Section: Most Unclear Experimental Fact: Ri Modementioning
confidence: 99%
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“…For this latter purpose, massive neon or argon gas is puffed. The contamination with light impurities can also increase plasma confinement in suitable plasma scenarios [5][6][7][8][9]. It is carried out by injecting a small percentage of impurity gas amount in respect of fuel, in this way the reduction of heat loads on the material plates is realized, meanwhile, a radiative improved confinement can be obtained.…”
Section: Introductionmentioning
confidence: 99%
“…ITER must be investigated in order to extend the knowledge of the impurity mechanism [12,13]. The possibility of exploiting the properties of plasmas contaminated by medium and light Z impurities has being explored in several tokamak devices [5][6][7][8][9], neon, argon and nitrogen are routinely used. JET [14], ASDEX-Upgrade [15] and DIII-D [16] have published detachment studies in helium plasmas.…”
Section: Introductionmentioning
confidence: 99%