Results 91 to 100 of about 96,750 (196)

Tungsten coating on jet mk IIGB-SRP divertor tiles

, 2002
Erosion and deposition at the JET vessel walls and divertor have been investigated over the last years by means of various coating structures. This work is still ongoing and a new set of CFC tiles with tungsten stripes was installed in the divertor ...
Lehto, Sari, Coad, J.P., Ahlgren, T., Kolehmainen, Jarno, Hole, D.E., Likonen, Jari; id_orcid, Mayer, M.   +6 more
core   +4 more sources

Tungsten nano-tendril growth in the Alcator C-Mod divertor

, 2011
Growth of tungsten nano-tendrils ('fuzz') has been observed for the first time in the divertor region of a high-power density tokamak experiment. After 14 consecutive helium L-mode discharges in Alcator C-Mod, the tip of a tungsten Langmuir probe at the ...
Lipschultz, Bruce, Brunner, Daniel Frederic, Whyte, Dennis G, Terry, James L, Labombard, Brian, Doerner, R. P., Baldwin, M. J., Wright, Graham   +7 more
core   +1 more source

Hydrogen inventory simulations for PFCs (HISP)

Nuclear Materials and Energy
Hydrogen Inventory Simulations for Plasma facing components (HISP) is an open-source simulation tool to model the evolution of hydrogen (H) isotopes inventory in plasma-facing-components (PFCs) of magnetic confinement fusion devices. The objective was to
Kaelyn Dunnell, Adria Lleal, Etienne Augustin Hodille, Jonathan Dufour, Remi Delaporte-Mathurin, Tom Wauters   +5 more
doaj   +1 more source

Statistical study of particle flux footprint widths with tungsten divertor in EAST

, 2019
The study of the divertor heat flux is of great importance for the operation of ITER and future fusion devices. In this paper, the behaviors of the widths of the particle flux footprints on the tungsten divertor in EAST have been statistically studied ...
Liu, J. B., Maingi, R., Liu, X., Liu, Y., Wang, L., Naulin, V., Xu, J. C., Nielsen, A. H., Goldston, R. J., Xu, G. S., Li, J., Deng, G. Z., Rasmussen, J. J.   +12 more
core   +1 more source

Global tungsten erosion and migration modeling for the EU-DEMO with the ERO2.0 code

Nuclear Fusion
Global tungsten migration, thus erosion, transport, and deposition, in the EU-DEMO tokamak is investigated using ERO2.0 simulations for an argon-seeded ELM-free H-mode plasma scenario with expected 2 GW fusion power developed with the narrow-grid version
C. Baumann, J. Romazanov, D. Matveev, A. Kirschner, F. Subba, S. Wiesen, S. Brezinsek, Ch. Linsmeier   +7 more
doaj   +1 more source

Erosion and impurity migration modelling in neon-seeded plasma discharges in ITER with a full-tungsten wall

Nuclear Fusion
The present work investigates global tungsten erosion and transport in two neon-seeded ITER discharges under burning plasma conditions using three-dimensional Monte-Carlo simulations with the ERO2.0 code.
C. Baumann, H.A. Kumpulainen, J. Romazanov, S. Rode, A. Kirschner, S. Brezinsek, A.A. Pshenov, T. Wauters, R.A. Pitts, A. Loarte   +9 more
doaj   +1 more source

Modelling fuel retention in the W divertor during the D/H/D changeover experiment in WEST

Nuclear Materials and Energy
A fuelling changeover experiment from Deuterium (D) to Hydrogen (H), and back has been performed in WEST to study the retention and removal in metallic devices with actively cooled ITER-grade tungsten divertor.
E.A. Hodille, D. Piccinelli, M. Bertoglio, T. Loarer, J. Dufour, J. Denis, E. Lascar, G. Ciraolo, P. Tamain, Y. Ferro, E. Geulin, A. Gallo, P. Moreau, S. Vartanian, R. Bisson, B. Pégourié, Y. Anquetin, J. Gaspar, Y. Corre, K. Dunnell, T. Wauters   +20 more
doaj   +1 more source

Fabrication of Tungsten and Carbon Clad Plates by Sinter Bonding Methods for Divertor System Characterization

, 2017
Full tungsten divertor is employed for ITER, and the tungsten will be the most potential candidate for the surface material of plasma facing components in fusion reactor after DEMO.
福本, 正勝, 713594, 福本 正勝, 朝倉, 勇貴, 中里, 直史, 713596, 岸本, 弘立, 713595, 713598, 713597   +9 more
core  

Multiscale numerical study of the ELM-induced sputtering on the tungsten castellated divertor gap

Nuclear Fusion
Material sputtering and erosion are key issue in fusion science. In the steady state, tungsten sputtering can be maintained at a low level. However, tungsten is seriously sputtered by the hot plasma from edge localized mode (ELM) bursts.
Guo-jian Niu, Gakushi Kawamura, Shu-yu Dai, Zhong-shi Yang, Fang Ding, Qian Xu, Rong Wang, Tao He, Guang-Nan Luo   +8 more
doaj   +1 more source

Molecular dynamics simulation of tungsten surface sputtering under low–energy neon irradiation for radiative divertor scenarios

Nuclear Materials and Energy
Neon (Ne) is a key candidate impurity for radiative divertor operation in tokamaks, aiming to reduce the thermal load on the divertor targets. However, its injection can simultaneously enhance tungsten surface erosion.
Xianglong Liu, Zhongshi Yang, Guojian Niu, Xiaochun Li, Yilang Mai, Jing Liang, Yilin Zhou, Kedong Li, Haishan Zhou, Guang-Nan Luo   +9 more
doaj   +1 more source