Physics basis for the first ITER tungsten divertor

Pitts, R. A.; Bonnin, X.; Escourbiac, F.; Frerichs, H.; Gunn, J. P.; Hirai, T.; Kukushkin, A. S.; Kaveeva, E.; Miller, M. A.; Moulton, D.; Rozhansky, V.; Senichenkov, I.; Sytova, E.; Schmitz, O.; Stangeby, P. C.; De Temmerman, G.; Veselova, I.; Wiesen, S.

doi:10.1016/j.nme.2019.100696

Title: Physics basis for the first ITER tungsten divertor

Journal Article · 18 July 2019 · Nuclear Materials and Energy

DOI: https://doi.org/10.1016/j.nme.2019.100696 · OSTI ID:1560688

Pitts, R. A. ^[1]; Bonnin, X. ^[1]; Escourbiac, F. ^[1]; Frerichs, H. ^[2]; Gunn, J. P. ^[3]; Hirai, T. ^[1]; Kukushkin, A. S. ^[4]; Kaveeva, E. ^[5]; Miller, M. A. ^[6]; Moulton, D. ^[7]; Rozhansky, V. ^[5]; Senichenkov, I. ^[5]; Sytova, E. ^[8]; Schmitz, O. ^[2]; Stangeby, P. C. ^[9]; De Temmerman, G. ^[1]; Veselova, I. ^[5]; Wiesen, S. ^[10]

ITER Organization, St. Paul Lez Durance (France)
Univ. of Wisconsin, Madison, WI (United States)
Alternative Energies and Atomic Energy Commission (CEA), St. Paul Lez Durance (France)
National Research Centre, Moscow (Russian Federation). Kurchatov Inst.; Moscow Engineering Physics Univ., Moscow (Russian Federation)
Peter the Great St. Petersburg Polytechnique Univ. (Russia)
Columbia Univ., New York, NY (United States)
Culham Science Centre, Abingdon (United Kingdom). Culham Centre for Fusion Energy (CCFE)
ITER Organization, St. Paul Lez Durance (France); Peter the Great St. Petersburg Polytechnique Univ. (Russia); Max Planck Inst. fur Plasmaphysik, Garching (Germany)
Univ. of Toronto, ON (Canada)
Forschungszentrum Juelich (Germany)

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 accompanying the new “staged approach” to ITER nuclear operations which fixes the overall divertor lifetime constraint. The principal focus is on the main design driver, steady state power fluxes in the DT phases, obtained from simulations using the 2-D SOLPS-4.3 and SOLPS-ITER plasma boundary codes, assuming the use of the low Z seeding impurities nitrogen (N) and neon (Ne). A new perspective on the simulation database is adopted, concentrating purely on the divertor physics aspects rather than on the core-edge integration, which has been studied extensively in the course of the divertor design evolution and is published elsewhere. Emphasis is placed on factors which may increase the peak steady state loads: divertor target shaping for component misalignment protection, the influence of fluid drifts, and the consequences of narrow scrape-off layer heat flux channels. All tend to push the divertor into an operating space at higher sub-divertor neutral pressure in order to remain at power flux densities acceptable for the target material. However, a revised criterion for the maximum tolerable loads based on avoidance of W recrystallization, sets an upper limit potentially ~50% higher than the previously accepted value of ~10 MW m-2, a consequence both of the choice of material and the finalized component design. Although the simulation database is currently restricted to the 2-D toroidally symmetric situation, considerable progress is now also being made using the EMC3-Eirene 3-D code suite for the assessment of power loading in the presence of magnetic perturbations for ELM control. Some new results for low input power corresponding to the early H-mode operation phases are reported, showing that even if realistic plasma screening is taken into account, significant asymmetric divertor heat fluxes may arise far from the unperturbed strike point. The issue of tolerable limits for transient heat pulses is an open and key question. A new scaling for ELM power deposition has shown that whilst there may be more latitude for operation at higher current without ELM control, the ultimate limit is likely to be set more by material fatigue under large numbers of sub-threshold melting events.

View Journal Article

Cite

Export

Save

Research Organization:: Univ. of Wisconsin, Madison, WI (United States)

Sponsoring Organization:: USDOE Office of Science (SC); Russian Science Foundation; USDOE

Grant/Contract Number:: SC0012315; SC0013911; 17-12-01020

OSTI ID:: 1560688

Alternate ID(s):: OSTI ID: 1611763

Journal Information:: Nuclear Materials and Energy, Vol. 20, Issue C; ISSN 2352-1791

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

Citation Metrics:

Cited by: 366 works

Citation information provided by
Web of Science

References (111)

The pattern of parallel edge plasma flows due to pressure gradients, recycling, and resonant magnetic perturbations in DIII-D Frerichs, H.; Schmitz, O.; Evans, T. Physics of Plasmas, Vol. 22, Issue 7 https://doi.org/10.1063/1.4926524	journal	July 2015
Integrated simulations of H-mode operation in ITER including core fuelling, divertor detachment and ELM control Polevoi, A. R.; Loarte, A.; Dux, R. Nuclear Fusion, Vol. 58, Issue 5 https://doi.org/10.1088/1741-4326/aab4ad	journal	March 2018
Ballooning Instability Effect on the Profiles of Power Deposition on Divertor Targets Kukushkin, A. S.; Loarte, A.; Neuhauser, J. Contributions to Plasma Physics, Vol. 40, Issue 3-4 https://doi.org/10.1002/1521-3986(200006)40:3/4<233::AID-CTPP233>3.0.CO;2-9	journal	June 2000
Globus-M plasma edge modeling with B2SOLPS5.2 code Vekshina, E.; Senichenkov, I.; Rozhansky, V. Plasma Physics and Controlled Fusion, Vol. 58, Issue 8 https://doi.org/10.1088/0741-3335/58/8/085007	journal	July 2016
Operating window of ITER from consistent core–pedestal–SOL modelling with modified MMM transport and carbon Pacher, G. W.; Pacher, H. D.; Janeschitz, G. Plasma Physics and Controlled Fusion, Vol. 46, Issue 5A https://doi.org/10.1088/0741-3335/46/5A/028	journal	April 2004
Impurity seeding and scaling of edge parameters in ITER Pacher, H. D.; Kukushkin, A. S.; Pacher, G. W. Journal of Nuclear Materials, Vol. 390-391 https://doi.org/10.1016/j.jnucmat.2009.01.089	journal	June 2009
Use of tungsten material for the ITER divertor Hirai, T.; Panayotis, S.; Barabash, V. Nuclear Materials and Energy, Vol. 9 https://doi.org/10.1016/j.nme.2016.07.003	journal	December 2016
Scaling of ITER divertor parameters – interpolation from 2D modelling and extrapolation Pacher, H. D.; Kukushkin, A. S.; Pacher, G. W. Journal of Nuclear Materials, Vol. 313-316 https://doi.org/10.1016/S0022-3115(02)01374-0	journal	March 2003
Consequences of a reduction of the upstream power SOL width in ITER Kukushkin, A. S.; Pacher, H. D.; Pacher, G. W. Journal of Nuclear Materials, Vol. 438 https://doi.org/10.1016/j.jnucmat.2013.01.027	journal	July 2013
Assessment of critical heat flux margins on tungsten monoblocks of the ITER divertor vertical targets Escourbiac, F.; Durocher, A.; Fedosov, A. Fusion Engineering and Design, Vol. 146 https://doi.org/10.1016/j.fusengdes.2019.03.094	journal	September 2019
Effect of conditions for gas recirculation on divertor operation in ITER Kukushkin, A. S.; Pacher, H. D.; Kotov, V. Nuclear Fusion, Vol. 47, Issue 7 https://doi.org/10.1088/0029-5515/47/7/021	journal	June 2007
Simulations with current constraints of ELM-induced tungsten melt motion in ASDEX Upgrade Thorén, E.; Bazylev, B.; Ratynskaia, S. Physica Scripta, Vol. T170 https://doi.org/10.1088/1402-4896/aa8855	journal	September 2017
Stability and control of iterated non-linear transport solvers for fusion edge plasmas Frerichs, H.; Reiter, D. Computer Physics Communications, Vol. 188 https://doi.org/10.1016/j.cpc.2014.11.007	journal	March 2015
Divertor modelling and extrapolation to reactor conditions Kukushkin, A. S.; Pacher, H. D. Plasma Physics and Controlled Fusion, Vol. 44, Issue 6 https://doi.org/10.1088/0741-3335/44/6/320	journal	May 2002
Modelling of transitions between L- and H-mode in JET high plasma current plasmas and application to ITER scenarios including tungsten behaviour Koechl, F.; Loarte, A.; Parail, V. Nuclear Fusion, Vol. 57, Issue 8 https://doi.org/10.1088/1741-4326/aa7539	journal	June 2017
Disruptions in ITER and strategies for their control and mitigation Lehnen, M.; Aleynikova, K.; Aleynikov, P. B. Journal of Nuclear Materials, Vol. 463 https://doi.org/10.1016/j.jnucmat.2014.10.075	journal	August 2015
Non-linear MHD simulation of ELM energy deposition Huijsmans, G. T. A.; Loarte, A. Nuclear Fusion, Vol. 53, Issue 12 https://doi.org/10.1088/0029-5515/53/12/123023	journal	November 2013
Effect of the dome on divertor performance in ITER Kukushkin, A. S.; Pacher, H. D.; Kotov, V. Journal of Nuclear Materials, Vol. 363-365 https://doi.org/10.1016/j.jnucmat.2007.01.094	journal	June 2007
Qualification and post-mortem characterization of tungsten mock-ups exposed to cyclic high heat flux loading Pintsuk, G.; Bobin-Vastra, I.; Constans, S. Fusion Engineering and Design, Vol. 88, Issue 9-10 https://doi.org/10.1016/j.fusengdes.2013.05.091	journal	October 2013
Self-castellation of tungsten monoblock under high heat flux loading and impact of material properties Panayotis, S.; Hirai, T.; Barabash, V. Nuclear Materials and Energy, Vol. 12 https://doi.org/10.1016/j.nme.2016.10.025	journal	August 2017
Divertor Physics Research on Alcator C-Mod Lipschultz, B.; LaBombard, B.; Terry, J. L. Fusion Science and Technology, Vol. 51, Issue 3 https://doi.org/10.13182/FST07-A1428	journal	April 2007
ITER operation window determined from mutually consistent core–SOL–divertor simulations: definition and application Pacher, G. W.; Pacher, H. D.; Janeschitz, G. Nuclear Fusion, Vol. 48, Issue 10 https://doi.org/10.1088/0029-5515/48/10/105003	journal	September 2008
ITER full tungsten divertor qualification program and progress Hirai, T.; Escourbiac, F.; Carpentier-Chouchana, S. Physica Scripta, Vol. T159 https://doi.org/10.1088/0031-8949/2014/T159/014006	journal	April 2014
Chapter 1: Overview and summary Shimada, M.; Campbell, D. J.; Mukhovatov, V. Nuclear Fusion, Vol. 47, Issue 6 https://doi.org/10.1088/0029-5515/47/6/S01	journal	June 2007
Observation of a Multimode Plasma Response and its Relationship to Density Pumpout and Edge-Localized Mode Suppression Paz-Soldan, C.; Nazikian, R.; Haskey, S. R. Physical Review Letters, Vol. 114, Issue 10 https://doi.org/10.1103/PhysRevLett.114.105001	journal	March 2015
Pedestal Bifurcation and Resonant Field Penetration at the Threshold of Edge-Localized Mode Suppression in the DIII-D Tokamak Nazikian, R.; Paz-Soldan, C.; Callen, J. D. Physical Review Letters, Vol. 114, Issue 10 https://doi.org/10.1103/PhysRevLett.114.105002	journal	March 2015
Enhanced understanding of non-axisymmetric intrinsic and controlled field impacts in tokamaks In, Y.; Park, J. -K.; Jeon, Y. M. Nuclear Fusion, Vol. 57, Issue 11 https://doi.org/10.1088/1741-4326/aa791c	journal	August 2017
Basic physical processes and reduced models for plasma detachment Stangeby, P. C. Plasma Physics and Controlled Fusion, Vol. 60, Issue 4 https://doi.org/10.1088/1361-6587/aaacf6	journal	March 2018
Divertor design and its integration into ITER Janeschitz, G.; Antipenkov, A.; Federici, G. Nuclear Fusion, Vol. 42, Issue 1 https://doi.org/10.1088/0029-5515/42/1/303	journal	January 2002
Progress in extrapolating divertor heat fluxes towards large fusion devices Sieglin, B.; Faitsch, M.; Eich, T. Physica Scripta, Vol. T170 https://doi.org/10.1088/1402-4896/aa9670	journal	November 2017
Overview and status of ITER internal components Merola, Mario; Escourbiac, Frederic; Raffray, René Fusion Engineering and Design, Vol. 89, Issue 7-8 https://doi.org/10.1016/j.fusengdes.2014.01.055	journal	October 2014
Physics basis and design of the ITER plasma-facing components Pitts, R. A.; Carpentier, S.; Escourbiac, F. Journal of Nuclear Materials, Vol. 415, Issue 1 https://doi.org/10.1016/j.jnucmat.2011.01.114	journal	August 2011
Grid resolution study for B2-EIRENE simulation of partially detached ITER divertor plasma Ghoos, K.; Börner, P.; Dekeyser, W. Nuclear Fusion, Vol. 59, Issue 2 https://doi.org/10.1088/1741-4326/aaf30f	journal	December 2018
Experiments on transient melting of tungsten by ELMs in ASDEX Upgrade Krieger, K.; Balden, M.; Coenen, J. W. Nuclear Fusion, Vol. 58, Issue 2 https://doi.org/10.1088/1741-4326/aa9a05	journal	January 2018
Fuel retention studies with the ITER-Like Wall in JET Brezinsek, S.; Loarer, T.; Philipps, V. Nuclear Fusion, Vol. 53, Issue 8 https://doi.org/10.1088/0029-5515/53/8/083023	journal	July 2013
Gyrokinetic projection of the divertor heat-flux width from present tokamaks to ITER Chang, C. S.; Ku, S.; Loarte, A. Nuclear Fusion, Vol. 57, Issue 11 https://doi.org/10.1088/1741-4326/aa7efb	journal	August 2017
Structure of the classical scrape-off layer of a tokamak Rozhansky, V.; Kaveeva, E.; Senichenkov, I. Plasma Physics and Controlled Fusion, Vol. 60, Issue 3 https://doi.org/10.1088/1361-6587/aaa11a	journal	January 2018
Transient heat load challenges for plasma-facing materials during long-term operation Wirtz, M.; Linke, J.; Loewenhoff, Th. Nuclear Materials and Energy, Vol. 12 https://doi.org/10.1016/j.nme.2016.12.024	journal	August 2017
Simulation of divertor targets shielding during transients in ITER Pestchanyi, Sergey; Pitts, Richard; Lehnen, Michael Fusion Engineering and Design, Vol. 109-111 https://doi.org/10.1016/j.fusengdes.2016.02.105	journal	November 2016
Power exhaust by SOL and pedestal radiation at ASDEX Upgrade and JET Bernert, M.; Wischmeier, M.; Huber, A. Nuclear Materials and Energy, Vol. 12 https://doi.org/10.1016/j.nme.2016.12.029	journal	August 2017
Presentation of the New SOLPS-ITER Code Package for Tokamak Plasma Edge Modelling Bonnin, Xavier; Dekeyser, Wouter; Pitts, Richard Plasma and Fusion Research, Vol. 11, Issue 0 https://doi.org/10.1585/pfr.11.1403102	journal	January 2016
Modelling of the ITER reference divertor plasma Pacher, H. D.; Kukushkin, A. S.; Pacher, G. W. Journal of Nuclear Materials, Vol. 415, Issue 1 https://doi.org/10.1016/j.jnucmat.2010.10.083	journal	August 2011
Partial detachment of high power discharges in ASDEX Upgrade Kallenbach, A.; Bernert, M.; Beurskens, M. Nuclear Fusion, Vol. 55, Issue 5 https://doi.org/10.1088/0029-5515/55/5/053026	journal	April 2015
ELM-induced transient tungsten melting in the JET divertor Coenen, J. W.; Arnoux, G.; Bazylev, B. Nuclear Fusion, Vol. 55, Issue 2 https://doi.org/10.1088/0029-5515/55/2/023010	journal	January 2015
Effect of 3D magnetic perturbations on divertor conditions and detachment in tokamak and stellarator Ahn, J-W; Briesemester, A. R.; Kobayashi, M. Plasma Physics and Controlled Fusion, Vol. 59, Issue 8 https://doi.org/10.1088/1361-6587/aa73ea	journal	June 2017
Tungsten and CFC degradation under combined high cycle transient and steady state heat loads Loewenhoff, Th.; Linke, J.; Pintsuk, G. Fusion Engineering and Design, Vol. 87, Issue 7-8 https://doi.org/10.1016/j.fusengdes.2012.02.106	journal	August 2012
Effect of magnetic perturbations for ELM control on divertor power loads, detachment and consequences of field penetration in ASDEX Upgrade Faitsch, M.; Sieglin, B.; Brida, D. Plasma Physics and Controlled Fusion, Vol. 61, Issue 1 https://doi.org/10.1088/1361-6587/aae2d2	journal	November 2018
Neutral recirculation—the key to control of divertor operation Kukushkin, A. S.; Pacher, H. D. Nuclear Fusion, Vol. 56, Issue 12 https://doi.org/10.1088/0029-5515/56/12/126012	journal	September 2016
Heat loads on poloidal and toroidal edges of castellated plasma-facing components in COMPASS Dejarnac, R.; Corre, Y.; Vondracek, P. Nuclear Fusion, Vol. 58, Issue 6 https://doi.org/10.1088/1741-4326/aab973	journal	April 2018
Status of technology R&D for the ITER tungsten divertor monoblock Hirai, T.; Escourbiac, F.; Barabash, V. Journal of Nuclear Materials, Vol. 463 https://doi.org/10.1016/j.jnucmat.2014.12.027	journal	August 2015
Effect of the tokamak size in edge transport modelling and implications for DEMO Pacher, H. D.; Kukushkin, A. S.; Pacher, G. W. Journal of Nuclear Materials, Vol. 363-365 https://doi.org/10.1016/j.jnucmat.2007.01.034	journal	June 2007
Analysis of performance of the optimized divertor in ITER Kukushkin, A. S.; Pacher, H. D.; Loarte, A. Nuclear Fusion, Vol. 49, Issue 7 https://doi.org/10.1088/0029-5515/49/7/075008	journal	May 2009
Edge and divertor physics with reversed toroidal field in JET Pitts, R. A.; Andrew, P.; Bonnin, X. Journal of Nuclear Materials, Vol. 337-339 https://doi.org/10.1016/j.jnucmat.2004.10.111	journal	March 2005
WALLDYN simulations of global impurity migration in JET and extrapolations to ITER Schmid, K.; Krieger, K.; Lisgo, S. W. Nuclear Fusion, Vol. 55, Issue 5 https://doi.org/10.1088/0029-5515/55/5/053015	journal	April 2015
Divertor studies in nitrogen induced completely detached H-modes in full tungsten ASDEX Upgrade Reimold, F.; Wischmeier, M.; Bernert, M. Nuclear Fusion, Vol. 55, Issue 3 https://doi.org/10.1088/0029-5515/55/3/033004	journal	February 2015
Effect of strike point displacements on the ITER tungsten divertor heat loads Carli, S.; Pitts, R. A.; Bonnin, X. Nuclear Fusion, Vol. 58, Issue 12 https://doi.org/10.1088/1741-4326/aae43f	journal	October 2018
The new SOLPS-ITER code package Wiesen, S.; Reiter, D.; Kotov, V. Journal of Nuclear Materials, Vol. 463 https://doi.org/10.1016/j.jnucmat.2014.10.012	journal	August 2015
Critical issues in divertor optimisation for ITER–FEAT Kukushkin, A. S.; Janeschitz, G.; Loarte, A. Journal of Nuclear Materials, Vol. 290-293 https://doi.org/10.1016/S0022-3115(00)00457-8	journal	March 2001
Characterization of ITER tungsten qualification mock-ups exposed to high cyclic thermal loads Pintsuk, Gerald; Bednarek, Maja; Gavila, Pierre Fusion Engineering and Design, Vol. 98-99 https://doi.org/10.1016/j.fusengdes.2015.01.037	journal	October 2015
Design optimization of the ITER tungsten divertor vertical targets Hirai, T.; Carpentier-Chouchana, S.; Escourbiac, F. Fusion Engineering and Design, Vol. 127 https://doi.org/10.1016/j.fusengdes.2017.12.007	journal	February 2018
ELM pacing and the ITER operating window: mutual constraints Pacher, G. W.; Pacher, H. D.; Kukushkin, A. S. Nuclear Fusion, Vol. 51, Issue 8 https://doi.org/10.1088/0029-5515/51/8/083004	journal	June 2011
Evolution of nitrogen concentration and ammonia production in N ₂ -seeded H-mode discharges at ASDEX Upgrade Drenik, A.; Laguardia, L.; McDermott, R. Nuclear Fusion, Vol. 59, Issue 4 https://doi.org/10.1088/1741-4326/aafe23	journal	February 2019
Strong correlation between D ₂ density and electron temperature at the target of divertors found in SOLPS analysis Stangeby, P. C.; Sang, Chaofeng Nuclear Fusion, Vol. 57, Issue 5 https://doi.org/10.1088/1741-4326/aa5e27	journal	March 2017
Surface heat loads on the ITER divertor vertical targets Gunn, J. P.; Carpentier-Chouchana, S.; Escourbiac, F. Nuclear Fusion, Vol. 57, Issue 4 https://doi.org/10.1088/1741-4326/aa5e2a	journal	March 2017
The effects of field reversal on the Alcator C-Mod divertor Hutchinson, I. H.; LaBombard, B.; Goetz, J. A. Plasma Physics and Controlled Fusion, Vol. 37, Issue 12 https://doi.org/10.1088/0741-3335/37/12/004	journal	December 1995
The Role of “Momentum Removal” in Divertor Detachment: The Role of “Momentum Removal” in Divertor Detachment Kukushkin, A. S.; Pacher, H. D. Contributions to Plasma Physics, Vol. 56, Issue 6-8 https://doi.org/10.1002/ctpp.201610048	journal	July 2016
High confinement/high radiated power H-mode experiments in Alcator C-Mod and consequences for International Thermonuclear Experimental Reactor (ITER) Q _DT = 10 operation Loarte, A.; Hughes, J. W.; Reinke, M. L. Physics of Plasmas, Vol. 18, Issue 5 https://doi.org/10.1063/1.3567547	journal	May 2011
ITER divertor performance in conditions of carbon re-erosion Kukushkin, A. S.; Pacher, H. D.; Coster, D. P. Journal of Nuclear Materials, Vol. 337-339 https://doi.org/10.1016/j.jnucmat.2004.10.006	journal	March 2005
AMMONX: A kinetic ammonia production scheme for EIRENE implementation Touchard, S.; Mougenot, J.; Rond, C. Nuclear Materials and Energy, Vol. 18 https://doi.org/10.1016/j.nme.2018.11.020	journal	January 2019
Physics requirements on fuel throughput in ITER Kukushkin, A. S.; Polevoi, A. R.; Pacher, H. D. Journal of Nuclear Materials, Vol. 415, Issue 1 https://doi.org/10.1016/j.jnucmat.2010.08.050	journal	August 2011
Stabilization of EMC3-EIRENE for detachment conditions and comparison to SOLPS-ITER Frerichs, H.; Bonnin, X.; Feng, Y. Nuclear Materials and Energy, Vol. 18 https://doi.org/10.1016/j.nme.2018.11.022	journal	January 2019
Scaling laws for edge plasma parameters in ITER from two-dimensional edge modelling Kukushkin, A. S.; Pacher, H. D.; Pacher, G. W. Nuclear Fusion, Vol. 43, Issue 8 https://doi.org/10.1088/0029-5515/43/8/312	journal	August 2003
Design and first applications of the ITER integrated modelling & analysis suite Imbeaux, F.; Pinches, S. D.; Lister, J. B. Nuclear Fusion, Vol. 55, Issue 12 https://doi.org/10.1088/0029-5515/55/12/123006	journal	October 2015
ELM divertor peak energy fluence scaling to ITER with data from JET, MAST and ASDEX upgrade Eich, T.; Sieglin, B.; Thornton, A. J. Nuclear Materials and Energy, Vol. 12 https://doi.org/10.1016/j.nme.2017.04.014	journal	August 2017
Speed-up of SOLPS-ITER code for tokamak edge modeling Kaveeva, E.; Rozhansky, V.; Senichenkov, I. Nuclear Fusion, Vol. 58, Issue 12 https://doi.org/10.1088/1741-4326/aae162	journal	October 2018
Impurity seeding in ITER DT plasmas in a carbon-free environment Pacher, H. D.; Kukushkin, A. S.; Pacher, G. W. Journal of Nuclear Materials, Vol. 463 https://doi.org/10.1016/j.jnucmat.2014.11.104	journal	August 2015
The influence of plasma-surface interaction on the performance of tungsten at the ITER divertor vertical targets De Temmerman, G.; Hirai, T.; Pitts, R. A. Plasma Physics and Controlled Fusion, Vol. 60, Issue 4 https://doi.org/10.1088/1361-6587/aaaf62	journal	March 2018
Finalizing the ITER divertor design: The key role of SOLPS modeling Kukushkin, A. S.; Pacher, H. D.; Kotov, V. Fusion Engineering and Design, Vol. 86, Issue 12 https://doi.org/10.1016/j.fusengdes.2011.06.009	journal	December 2011
Basic divertor operation in ITER-FEAT Kukushkin, A. S.; Pacher, H. D.; Janeschitz, G. Nuclear Fusion, Vol. 42, Issue 2 https://doi.org/10.1088/0029-5515/42/2/310	journal	February 2002
ITER divertor plasma response to time-dependent impurity injection Bonnin, X.; Pitts, R. A.; Komarov, V. Nuclear Materials and Energy, Vol. 12 https://doi.org/10.1016/j.nme.2017.03.010	journal	August 2017
Interpretation of the deep cracking phenomenon of tungsten monoblock targets observed in high-heat-flux fatigue tests at 20 MW/m 2 Li, Muyuan; You, Jeong-Ha Fusion Engineering and Design, Vol. 101 https://doi.org/10.1016/j.fusengdes.2015.09.008	journal	December 2015
On detachment asymmetry and stability Pshenov, A. A.; Kukushkin, A. S.; Krasheninnikov, S. I. Physics of Plasmas, Vol. 24, Issue 7 https://doi.org/10.1063/1.4991402	journal	July 2017
Comparing N versus Ne as divertor radiators in ASDEX-upgrade and ITER Sytova, Elizaveta; Pitts, Richard A.; Kaveeva, Elizaveta Nuclear Materials and Energy, Vol. 19 https://doi.org/10.1016/j.nme.2019.02.019	journal	May 2019
Correlation of the tokamak H-mode density limit with ballooning stability at the separatrix Eich, T.; Goldston, R. J.; Kallenbach, A. Nuclear Fusion, Vol. 58, Issue 3 https://doi.org/10.1088/1741-4326/aaa340	journal	January 2018
Effect of island overlap on edge localized mode suppression by resonant magnetic perturbations in DIII-D Fenstermacher, M. E.; Evans, T. E.; Osborne, T. H. Physics of Plasmas, Vol. 15, Issue 5 https://doi.org/10.1063/1.2901064	journal	May 2008
The interplay of controlling the power exhaust and the tungsten content in ITER Dux, R.; Loarte, A.; Angioni, C. Nuclear Materials and Energy, Vol. 12 https://doi.org/10.1016/j.nme.2016.10.013	journal	August 2017
Neutral pressure and separatrix density related models for seed impurity divertor radiation in ASDEX Upgrade Kallenbach, A.; Bernert, M.; Dux, R. Nuclear Materials and Energy, Vol. 18 https://doi.org/10.1016/j.nme.2018.12.021	journal	January 2019
EU R&D on divertor components Merola, M.; Dänner, W.; Pick, M. Fusion Engineering and Design, Vol. 75-79 https://doi.org/10.1016/j.fusengdes.2005.06.139	journal	November 2005
Fracture modes of ITER tungsten divertor monoblock under stationary thermal loads Panayotis, S.; Hirai, T.; Barabash, V. Fusion Engineering and Design, Vol. 125 https://doi.org/10.1016/j.fusengdes.2017.08.009	journal	December 2017
Numerical modelling of high density JET divertor plasma with the SOLPS4.2 (B2-EIRENE) code Kotov, V.; Reiter, D.; Pitts, R. A. Plasma Physics and Controlled Fusion, Vol. 50, Issue 10 https://doi.org/10.1088/0741-3335/50/10/105012	journal	September 2008
Experimental conditions to suppress edge localised modes by magnetic perturbations in the ASDEX Upgrade tokamak Suttrop, W.; Kirk, A.; Bobkov, V. Nuclear Fusion, Vol. 58, Issue 9 https://doi.org/10.1088/1741-4326/aace93	journal	July 2018
Investigation of the role of pedestal pressure and collisionality on type-I ELM divertor heat loads in DIII-D Knolker, M.; Bortolon, A.; Canal, G. P. Nuclear Fusion, Vol. 58, Issue 9 https://doi.org/10.1088/1741-4326/aace92	journal	July 2018
Modelling of ITER improved H-mode operation with the integrated core pedestal SOL model Pacher, G. W.; Pacher, H. D.; Janeschitz, G. Nuclear Fusion, Vol. 45, Issue 7 https://doi.org/10.1088/0029-5515/45/7/005	journal	June 2005
Heuristic drift-based model of the power scrape-off width in low-gas-puff H-mode tokamaks Goldston, R. J. Nuclear Fusion, Vol. 52, Issue 1 https://doi.org/10.1088/0029-5515/52/1/013009	journal	December 2011
Effect of neutral transport on ITER divertor performance Kukushkin, A. S.; Pacher, H. D.; Kotov, V. Nuclear Fusion, Vol. 45, Issue 7 https://doi.org/10.1088/0029-5515/45/7/008	journal	June 2005
Physics conclusions in support of ITER W divertor monoblock shaping Pitts, R. A.; Bardin, S.; Bazylev, B. Nuclear Materials and Energy, Vol. 12 https://doi.org/10.1016/j.nme.2017.03.005	journal	August 2017
On mechanisms of impurity leakage and retention in the tokamak divertor Senichenkov, I. Yu; Kaveeva, E. G.; Sytova, E. A. Plasma Physics and Controlled Fusion, Vol. 61, Issue 4 https://doi.org/10.1088/1361-6587/ab04d0	journal	March 2019
Recrystallization kinetics of warm-rolled tungsten in the temperature range 1150–1350 °C Alfonso, A.; Juul Jensen, D.; Luo, G. -N. Journal of Nuclear Materials, Vol. 455, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.08.037	journal	December 2014
A full tungsten divertor for ITER: Physics issues and design status Pitts, R. A.; Carpentier, S.; Escourbiac, F. Journal of Nuclear Materials, Vol. 438 https://doi.org/10.1016/j.jnucmat.2013.01.008	journal	July 2013
Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER Eich, T.; Leonard, A. W.; Pitts, R. A. Nuclear Fusion, Vol. 53, Issue 9 https://doi.org/10.1088/0029-5515/53/9/093031	journal	August 2013
MEMOS 3D modelling of ELM-induced transient melt damage on an inclined tungsten surface in the ASDEX Upgrade outer divertor Thorén, E.; Ratynskaia, S.; Tolias, P. Nuclear Materials and Energy, Vol. 17 https://doi.org/10.1016/j.nme.2018.11.006	journal	December 2018
Recent Improvements in the EMC3-Eirene Code: Recent Improvements in the EMC3-Eirene Code Feng, Y.; Frerichs, H.; Kobayashi, M. Contributions to Plasma Physics, Vol. 54, Issue 4-6 https://doi.org/10.1002/ctpp.201410092	journal	June 2014
A study of planar toroidal–poloidal beveling of monoblocks on the ITER divertor outer vertical target Gunn, J. P.; Hirai, T.; Corre, Y. Nuclear Fusion, Vol. 59, Issue 12 https://doi.org/10.1088/1741-4326/ab4071	journal	October 2019
Laser re-melting of tungsten damaged by transient heat loads Loewenhoff, Th.; Linke, J.; Matějíček, J. Nuclear Materials and Energy, Vol. 9 https://doi.org/10.1016/j.nme.2016.04.004	journal	December 2016
Physics of ultimate detachment of a tokamak divertor plasma Krasheninnikov, S. I.; Kukushkin, A. S. Journal of Plasma Physics, Vol. 83, Issue 5 https://doi.org/10.1017/S0022377817000654	journal	September 2017
Ion orbit modelling of ELM heat loads on ITER divertor vertical targets Gunn, J. P.; Carpentier-Chouchana, S.; Dejarnac, R. Nuclear Materials and Energy, Vol. 12 https://doi.org/10.1016/j.nme.2016.10.005	journal	August 2017
A long-pulse high-confinement plasma regime in the Experimental Advanced Superconducting Tokamak Li, J.; Guo, H. Y.; Wan, B. N. Nature Physics, Vol. 9, Issue 12 https://doi.org/10.1038/nphys2795	journal	November 2013
Two-point analysis of the numerical modelling of detached divertor plasmas Kotov, V.; Reiter, D. Plasma Physics and Controlled Fusion, Vol. 51, Issue 11 https://doi.org/10.1088/0741-3335/51/11/115002	journal	October 2009
Validation of TOKES vapor shield simulations against experiments in the 2MK-200 facility Pestchanyi, S.; Pitts, R. A.; Safronov, V. Fusion Engineering and Design, Vol. 124 https://doi.org/10.1016/j.fusengdes.2017.02.048	journal	November 2017
MHD stability of the ITER pedestal and SOL plasma and its influence on the heat flux width Loarte, A.; Liu, F.; Huijsmans, G. T. A. Journal of Nuclear Materials, Vol. 463 https://doi.org/10.1016/j.jnucmat.2014.11.122	journal	August 2015
Status and physics basis of the ITER divertor Pitts, R. A.; Kukushkin, A.; Loarte, A. Physica Scripta, Vol. T138 https://doi.org/10.1088/0031-8949/2009/T138/014001	journal	December 2009

Cited By (3)

Simulations of tokamak boundary plasma turbulence transport in setting the divertor heat flux width Xu, X. Q.; Li, N. M.; Li, Z. Y. Nuclear Fusion, Vol. 59, Issue 12 https://doi.org/10.1088/1741-4326/ab430d	journal	October 2019
Simulations of divertor heat flux width using transport code with cross-field drifts under the BOUT++ framework Li, N. M.; Xu, X. Q.; Hughes, J. W. AIP Advances, Vol. 10, Issue 1 https://doi.org/10.1063/1.5126884	journal	January 2020
A study of planar toroidal–poloidal beveling of monoblocks on the ITER divertor outer vertical target Gunn, J. P.; Hirai, T.; Corre, Y. Nuclear Fusion, Vol. 59, Issue 12 https://doi.org/10.1088/1741-4326/ab4071	journal	October 2019

Similar Records

Plasma Wall Interaction with 3-D Plasma Boundaries

Technical Report · 2022 · OSTI ID:1844041

Schmitz, Oliver

Stabilization of EMC3-EIRENE for detachment conditions and comparison to SOLPS-ITER

Journal Article · 2018 · Nuclear Materials and Energy · OSTI ID:1485337

Frerichs, H.; Bonnin, X.; Feng, Y.; +4 more

Exploration of magnetic perturbation effects on advanced divertor configurations in NSTX-U

Journal Article · 2016 · Physics of Plasmas · OSTI ID:1399721

Frerichs, H.; Schmitz, O.; Waters, I.; +4 more

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
nuclear science & technology
ITER
tungsten
divertor
heat fluxes
SOLPS

Title: Physics basis for the first ITER tungsten divertor

Citation Formats

References (111)

Cited By (3)

Similar Records

Related Subjects