Results 11 to 20 of about 150 (75)

Modelling study of divertor W leakage for different divertor conditions with Ne seeding in EAST tokamak [PDF]

Nuclear Fusion
Sequential SOLPS-ITER and DIVIMP simulations are carried out for tungsten (W) edge transport during neon (Ne) injection in EAST, elucidating the pathway of W impurity leakage from the divertor to the core plasma under different dissipative divertor ...
Guoliang Xu, Hui Wang, Rui Ding, Hang Si, Guozhang Jia, Jin Guo, Hai Xie, Rong Yan, Ran Hai, Dahuan Zhu, Junling Chen   +10 more
doaj   +2 more sources

Impurity transport modelling in the scrape off layer of the MAST tokamak using DIVIMP-OSM-EIRENE and carbon injection [PDF]

, 2016
Non-hydrogenic impurities play a significant role in the performance of magnetically confined fusion devices, causing increased radiation and dilution of the Deuterium-Tritium fuel isotopes. Impurities are generated at the plasma wall interfaces as well as being deliberately introduced into the plasma in order to reduce heat loads to the vessel walls ...
Leggate, Huw J.
openaire   +2 more sources

First Monte‐Carlo modelling of global beryllium migration in ITER using ERO2.0

Contributions to Plasma Physics, Volume 60, Issue 5-6, June-July 2020., 2020
Abstract ERO2.0 is a recently developed Monte‐Carlo code for modelling global erosion and redeposition in fusion devices. We report here on the code's application to ITER for studying the erosion of the beryllium (Be) first wall armour under burning plasma steady state diverted conditions.
Juri Romazanov, Sebastijan Brezinsek, Andreas Kirschner, Dmitriy Borodin, Alina Eksaeva, Richard A. Pitts, Steven W. Lisgo, Himank Anand, Evgeny Veshchev, Vlad S. Neverov, Alexander B. Kukushkin, Andrey G. Alekseev, Christian Linsmeier   +12 more
wiley   +1 more source

Deposition of 13C tracer in the JET MkII-HD divertor [PDF]

, 2011
Migration of 13C has been investigated at JET by injecting 13C-labelled methane at the outer divertor base at the end of the 2009 campaign. The 13C deposition profiles on carbon fibre composite divertor tiles were measured by secondary ion mass ...
Brezinsek, S., Hakola, Antti; id_orcid, Koivuranta, Seppo, Widdowson, A., Coad, J.P., contributors, JET- EFDA, Grünhagen, S., Likonen, Jari; id_orcid, Airila, Markus; id_orcid, Strachan, J., Stamp, M., Rubel, M.   +11 more
core   +5 more sources

Refining light impurity content estimates at the lower divertor based on experimental data in WEST

Nuclear Materials and Energy, 2023
WEST is an actively cooled, long-pulse tokamak with nearly all plasma-facing components (PFC) made of tungsten (W). One of the aims of WEST is to study plasma operation with W PFCs in preparation for long-pulse operation on W divertor devices like ITER ...
A. Grosjean, D.C. Donovan, C.A. Johnson, J.P. Gunn, C. Guillemaut, N. Fedorczak, C.C. Klepper, E.A. Unterberg   +7 more
doaj   +1 more source

Recent DIII-D progress toward validating models of tungsten erosion, re-deposition, and migration for application to next-step fusion devices

Materials Research Express, 2023
Fundamental mechanisms governing the erosion and prompt re-deposition of tungsten impurities in tokamak divertors are identified and analyzed to inform the lifetime of tungsten plasma-facing components in ITER and other future devices.
T Abrams, J G Guterl, S Abe, D C Donovan, I Bykov, C A Johnson, J H Nichols, J D Elder, D A Ennis, S D Loch, D L Rudakov, G Sinclair, C H Skinner, P C Stangeby, D M Thomas, E A Unterberg, W R Wampler   +16 more
doaj   +1 more source

Development and Applications of 3D-DIVIMP(HC) Monte Carlo Impurity Modeling Code [PDF]

, 2010
A self-contained gas injection system for the Divertor Material Evaluation System (DiMES) on DIII-D, the Porous Plug Injector (PPI), has been employed by A.
Mu, Yarong
core   +3 more sources

Detachment evolution on the TCV tokamak

Nuclear Materials and Energy, 2017
Divertor detachment in the TCV tokamak has been investigated through experiments and modelling. Density ramp experiments were carried out in ohmic heated L-mode pulses with the ion ∇B drift directed away from the primary X-point, similar to previous ...
J.R. Harrison, W.A.J. Vijvers, C. Theiler, B.P. Duval, S. Elmore, B. Labit, B. Lipschultz, S.H.M. van Limpt, S.W. Lisgo, C.K. Tsui, H. Reimerdes, U. Sheikh, K.H.A. Verhaegh, M. Wischmeier   +13 more
doaj   +1 more source

3D global impurity transport modeling with WallDYN and EMC3-Eirene

Nuclear Materials and Energy, 2018
The global impurity migration code WallDYN was coupled to the 3D scrape off layer plasma solver EMC3-Eirene in order to make WallDYN applicable to 3D, non-toroidally symmetric, geometries.
K. Schmid, T. Lunt
doaj   +1 more source

Implementation into DIVIMP of a drift-kinetic model derived from the Fokker-Planck equation to examine the parallel-to-B velocity component of impurity ions in divertor-Tokamak plasmas [PDF]

, 2001
grantor: University of TorontoDirk Reiser's drift-kinetic (DK) model is compared to the existing fluid approximation (FA) model of the DIVIMP (DIVertor IMPurity) algorithm. The DK model provides a more general equation of impurity ion transport
Schwanke, Peter
core   +2 more sources