Results 1 to 10 of about 112,088 (330)
Divertor of the European DEMO: Engineering and technologies for power exhaust
Fusion Engineering and Design, 2022 In a power plant scale fusion reactor, a huge amount of thermal power produced by the fusion reaction and external heating must be exhausted through the narrow area of the divertor targets.
Pietro Alessandro Di Maio +2 more
exaly +2 more sources
Physics basis for the first ITER tungsten divertor
Nuclear Materials and Energy, 2019 On the eve of component procurement, this paper discusses the present physics basis for the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining the overall design, and outlining relevant aspects of the Research Plan ...
X Bonnin +2 more
exaly +2 more sources
Integration of full divertor detachment with improved core confinement for tokamak fusion plasmas
Nature Communications, 2021 Divertor detachment offers a promising solution to the challenge of plasma-wall interactions for steady-state operation of fusion reactors. Here, we demonstrate the excellent compatibility of actively controlled full divertor detachment with a high ...
Liang Wang, Huiqian Wang, S Y Ding
exaly +2 more sources
Role of molecular effects in divertor plasma recombination
Nuclear Materials and Energy, 2017 Molecule-Activated Recombination (MAR) effect is re-considered in view of divertor plasma conditions. A strong isotopic effect is demonstrated. In deuterium plasmas, the reaction chain through D2+ formation, usually considered dominant and included in 2D
Andrey Pshenov
exaly +3 more sources
European divertor target concepts for DEMO: Design rationales and high heat flux performance
Nuclear Materials and Energy, 2018 The divertor target plates are the most thermally loaded in-vessel components in a fusion reactor where high heat fluxes are produced on the plasma-facing components (PFCs) by intense plasma bombardment, radiation and nuclear heating.
Bernd Böswirth +2 more
exaly +2 more sources
Physics conclusions in support of ITER W divertor monoblock shaping
Nuclear Materials and Energy, 2017 The key remaining physics design issue for the ITER tungsten (W) divertor is the question of monoblock (MB) front surface shaping in the high heat flux target areas of the actively cooled targets. Engineering tolerance specifications impose a challenging
Jan Coenen, Yann Corre, Renaud Dejarnac
exaly +2 more sources
The effect of divertor closure on detachment onset in DIII-D
Nuclear Materials and Energy, 2019 Experiments at DIII-D use different divertor geometries to measure the effect of divertor closure on detachment onset. We compare matched H-mode discharges in the closed (upper) divertor and the open (lower) divertor and use as a detachment onset metric ...
Anthony Leonard
exaly +2 more sources
Nuclear Materials and Energy, 2019 Analytical expressions for the divertor radiation around the onset of detachment based on the divertor neutral pressure and the upstream separatrix density are tested against measurements on strongly nitrogen seeded high confinement mode (H-mode ...
A. Kallenbach +8 more
doaj +2 more sources
Nuclear Materials and Energy, 2022 Dedicated experiments in DIII-D find that magnetic shaping and divertor target geometry significantly affect the divertor plasma conditions and divertor detachment process in the small-angle-slot (SAS) divertor.
H.Q. Wang +12 more
doaj +1 more source
DTT - Divertor Tokamak Test facility: A testbed for DEMO
Fusion engineering and design, 2021 The effective treatment of the heat and power exhaust is a critical issue in the road map to the realization of the fusion energy. In order to provide possible, reliable, well assessed and on-time answers to DEMO, the Divertor Tokamak Test facility (DTT)
R. Ambrosino
semanticscholar +1 more source