Results 1 to 10 of about 744 (275)

Effects of divertor geometry on detachment and core plasma performance with impurity seeding in EAST

Nuclear Fusion
Divertor detachment operation compatible with the core plasma is an effective method to alleviate the steady-state heat flux approaching the divertor target; this scheme will be adopted by high-performance tokamaks in the future, such as International ...
L.Y. Meng, L. Wang, J.B. Liu, K.D. Li, X. Lin, X.J. Liu, G.Z. Jia, J. Guo, T. He, L. Yu, P.J. Tang, J.C. Xu, W.M. Zhang, L. Zhang, J.J. Yang, Y.M. Duan, F.B. Zhong, T. Zhang, M.R. Wang, Z.C. Lin, T.Q. Jia, B. Zhang, Q. Zang, Y.W. Yu, Z.X. Chen, G.S. Xu, B.N. Wan   +26 more
doaj   +2 more sources

Facilitated core-edge integration through divertor nitrogen seeding in the HL-2A tokamak

Nuclear Fusion
A divertor detachment with sustainable high-performance plasmas has been achieved through divertor nitrogen seeding in the HL-2A tokamak. The closed divertor structure facilitates achieving high divertor neutral pressure due to its efficient particle ...
N. Wu, J. Cheng, K.Y. Yi, R. Wang, M.K. Han, Z.H. Huang, W.C. Wang, Y. He, L.W. Yan, H.L. Du, J.M. Gao, H.C. Ma, X.X. He, Z.C. Yang, J. Wen, K. Zhang, T. Wu, W.P. Guo, X. Yu, L. Liu, Y.G. Li, L. Nie, Z.B. Shi, D.Z. Wang, W.L. Zhong   +24 more
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Density dependence of SOL power width in ASDEX upgrade L-Mode

Nuclear Materials and Energy, 2017
Understanding the heat transport in the scrape-off layer (SOL) and the divertor region is essential for the design of large fusion devices such as ITER and DEMO.
B. Sieglin, T. Eich, M. Faitsch, A. Herrmann, D. Nille, A. Scarabosio, ASDEX Upgrade Team   +6 more
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Dependence of neutral pressure on detachment in the small angle slot divertor at DIII-D

Nuclear Materials and Energy, 2019
Local neutral pressure measurements in the closed small angle slot (SAS) divertor [1,2] on DIII-D show a large increase when the divertor plasma shifts from high recycling into detachment. In-tile pressure gauges were installed to measure the pressure in
M.W. Shafer, B. Covele, J.M. Canik, L. Casali, H.Y. Guo, A.W. Leonard, J.D. Lore, A.G. McLean, A.L. Moser, P.C. Stangeby, D. Taussig, H.Q. Wang, J.G. Watkins   +12 more
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The effect of divertor closure on the impurity stagnation point in detached L-mode discharges on DIII-D

Nuclear Materials and Energy
This paper presents experimental measurements of the location of the impurity flow stagnation point in the scrape-off-layer (SOL) of a tokamak plasma. Coherence imaging of carbon-2+ emission (465 nm) is used to track the main-chamber impurity velocity of
M.G. Burke, F. Scotti, S.L. Allen, W.H. Meyer, A. Holm, M. Zhao, A.G. McLean, M. Fenstermacher, H.Q. Wang, R. Wilcox   +9 more
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Manipulating density pedestal structure to improve core–edge integration towards low collisionality

Nuclear Fusion
DIII-D experiments have achieved promising core–edge integrated plasma scenarios which combine a high-temperature low-collisionality pedestal (pedestal top temperature T _e _,ped > 0.8 keV and collisionality ν * _ped < 1) with a partially detached ...
H.Q. Wang, R.J. Hong, R. Groebner, X. Jian, T. Rhodes, A.W. Leonard, X. Ma, S. Mordijck, T. Wilks, Z. Yan, M.W. Shafer, F. Scotti, D. Truong, J. Ren, F. Laggner, B.A. Grierson, T.H. Osborne, D.M. Thomas, J.G. Watkins   +18 more
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Investigating the effect of BT direction on W source-to-core pathways during the SAS-VW campaign on DIII-D

Nuclear Materials and Energy
Experiments using the V-shaped closed slot tungsten (W) coated SAS-VW divertor in DIII-D studied the effects of the BT direction on core contamination of eroded tungsten from a closed slot divertor configuration.
J.D. Mateja, S.A. Zamperini, T. Odstrcil, J.H. Nichols, T.E. Ray, A. Cacheris, T. Abrams, A.G. McLean, G. Sinclair, S.H. Messer, R. Maurizio, D.M. Thomas, D.C. Donovan   +12 more
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Role of turbulent separatrix tangle in the improvement of the integrated pedestal and heat exhaust issue for stationary-operation tokamak fusion reactors

Nuclear Fusion
The magnetic separatrix surface is designed to provide the final and critical confinement to the hot stationary-operation core plasma in modern tokamak reactors in the absence of an external magnetic perturbation (MP) or transient magneto-hydrodynamic ...
C.S. Chang, S. Ku, R. Hager, J. Choi, D. Pugmire, S. Klasky, A. Loarte, R.A Pitts   +7 more
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2D distribution of hydrogen/impurity radiation and flow formation in stochastic layer during detachment transition in LHD

Nuclear Materials and Energy, 2017
2D distribution of hydrogen/impurity radiation and impurity flow have been measured in the edge stochastic layer of LHD during detachment transition by using a newly developed visible spectrometer system with 130 channel optic fiber array.
M. Kobayashi, S. Morita, M. Goto
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Simulation study of the influence of E× B drift on tungsten impurity transport in the scrape-off layer

Nuclear Fusion, 2023
Tungsten (W) is used as the plasma-facing material in the divertor region of future fusion reactors, such as ITER; however, its concentration in the core plasma must be maintained at an extremely low level.
Jin Guo, Yuchen Xu, Shifeng Mao, Minyou Ye   +3 more
doaj   +1 more source