UEDGE modelling of detached divertor operation for long-leg divertor geometries in ARC

Wigram, M.; LaBombard, B.; Umansky, M. V.; Kuang, A. Q.; Brunner, D.; Terry, J. L.; Golfinopoulos, T.; Rensink, M. E.; Whyte, D. G.

doi:10.1002/ctpp.201700178

UEDGE modelling of detached divertor operation for long-leg divertor geometries in ARC

Journal Article · Fri Mar 02 00:00:00 EST 2018 · Contributions to Plasma Physics

DOI:https://doi.org/10.1002/ctpp.201700178· OSTI ID:1822620

^[1]; LaBombard, B. ^[2]; Umansky, M. V. ^[3]; Kuang, A. Q. ^[2]; Brunner, D. ^[2]; Terry, J. L. ^[2]; Golfinopoulos, T. ^[2]; Rensink, M. E. ^[3]; Whyte, D. G. ^[2]

Univ. of York (United Kingdom)
Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). Plasma Science and Fusion Center
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

In this work, simulations of the ARC scrape-off layer and divertor configuration are carried out using UEDGE to perform the first power-handling assessment for the divertor design. A convective–diffusive anomalous transport model is implemented in the code to reproduce the radial plasma profiles anticipated for the device at the outer mid-plane. Levels of exhaust power from the core are varied, and a 0.5% fixed fraction neon impurity seeding is included in investigations to find steady-state detached solutions. Initial studies employing a super-X divertor configuration have shown that a stable detached divertor-operational window exists for reactor exhaust powers in the range of 72–92 MW, which is close to projected levels of exhaust power of 105 MW across the separatrix anticipated for ARC. Under these conditions, the divertor heat flux is fully dissipated by radiation and radial losses to the sidewalls of the divertor channel, leading to acceptable levels of power flux density on plasma-facing components. Simulations are being extended to study the performance of the X-point target geometry and to explore the sensitivity to the physics model and input parameters.

View Accepted Manuscript (DOE)

Research Organization:: Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)

Sponsoring Organization:: Engineering and Physical Sciences Research Council (EPSRC); USDOE National Nuclear Security Administration (NNSA)

Grant/Contract Number:: AC52-07NA27344

OSTI ID:: 1822620

Alternate ID(s):: OSTI ID: 22747250

Report Number(s):: LLNL-JRNL--777445; 969847

Journal Information:: Contributions to Plasma Physics, Journal Name: Contributions to Plasma Physics Journal Issue: 6-8 Vol. 58; ISSN 0863-1042

Publisher:: WileyCopyright Statement

Country of Publication:: United States

Language:: English

References (21)

Simulation of Detachment in ITER-Geometry Using the UEDGE Code and a Fluid Neutral Model Wising, F.; Knoll, D. A.; Krasheninnikov, S. I. Contributions to Plasma Physics, Vol. 36, Issue 2-3 https://doi.org/10.1002/ctpp.2150360238	journal	January 1996
A fully implicit, time dependent 2-D fluid code for modeling tokamak edge plasmas Rognlien, T. D.; Milovich, J. L.; Rensink, M. E. Journal of Nuclear Materials, Vol. 196-198 https://doi.org/10.1016/S0022-3115(06)80058-9	journal	December 1992
Edge-plasma models and characteristics for magnetic fusion energy devices Rognlien, T. D.; Rensink, M. E. Fusion Engineering and Design, Vol. 60, Issue 4 https://doi.org/10.1016/S0920-3796(02)00005-4	journal	July 2002
An initial study of demountable high-temperature superconducting toroidal field magnets for the Vulcan tokamak conceptual design Hartwig, Z. S.; Haakonsen, C. B.; Mumgaard, R. T. Fusion Engineering and Design, Vol. 87, Issue 3 https://doi.org/10.1016/j.fusengdes.2011.10.002	journal	March 2012
Assessing the feasibility of a high-temperature, helium-cooled vacuum vessel and first wall for the Vulcan tokamak conceptual design Barnard, H. S.; Hartwig, Z. S.; Olynyk, G. M. Fusion Engineering and Design, Vol. 87, Issue 3 https://doi.org/10.1016/j.fusengdes.2011.12.018	journal	March 2012
ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets Sorbom, B. N.; Ball, J.; Palmer, T. R. Fusion Engineering and Design, Vol. 100 https://doi.org/10.1016/j.fusengdes.2015.07.008	journal	November 2015
Simulation of main-chamber recycling in DIII-D with the UEDGE code Rensink, M. E.; Groth, M.; Porter, G. D. Journal of Nuclear Materials, Vol. 363-365 https://doi.org/10.1016/j.jnucmat.2007.01.252	journal	June 2007
Attainment of a stable, fully detached plasma state in innovative divertor configurations Umansky, M. V.; LaBombard, B.; Brunner, D. Physics of Plasmas, Vol. 24, Issue 5 https://doi.org/10.1063/1.4979193	journal	May 2017
Thermal bifurcation of scrape‐off layer plasma and divertor detachment Krasheninnikov, S. I.; Catto, P. J.; Helander, P. Physics of Plasmas, Vol. 2, Issue 7 https://doi.org/10.1063/1.871236	journal	August 1995
Comments on particle and energy balance in the edge plasma of Alcator C-Mod Umansky, M. V.; Krasheninnikov, S. I.; LaBombard, B. Physics of Plasmas, Vol. 5, Issue 9 https://doi.org/10.1063/1.873051	journal	September 1998
Modeling of particle and energy transport in the edge plasma of Alcator C-Mod Umansky, M. V.; Krasheninnikov, S. I.; LaBombard, B. Physics of Plasmas, Vol. 6, Issue 7 https://doi.org/10.1063/1.873236	journal	July 1999
Two-dimensional electric fields and drifts near the magnetic separatrix in divertor tokamaks Rognlien, T. D.; Ryutov, D. D.; Mattor, N. Physics of Plasmas, Vol. 6, Issue 5 https://doi.org/10.1063/1.873488	journal	May 1999
Heat transport in the JET scrape-off layer Erents, S. K.; Stangeby, P. C. Nuclear Fusion, Vol. 38, Issue 11 https://doi.org/10.1088/0029-5515/38/11/304	journal	November 1998
Transport-driven Scrape-Off-Layer flows and the boundary conditions imposed at the magnetic separatrix in a tokamak plasma LaBombard, B.; Rice, J. E.; Hubbard, A. E. Nuclear Fusion, Vol. 44, Issue 10 https://doi.org/10.1088/0029-5515/44/10/001	journal	September 2004
Analysis of geometric variations in high-power tokamak divertors Umansky, M. V.; Bulmer, R. H.; Cohen, R. H. Nuclear Fusion, Vol. 49, Issue 7 https://doi.org/10.1088/0029-5515/49/7/075005	journal	May 2009
I-mode: an H-mode energy confinement regime with L-mode particle transport in Alcator C-Mod Whyte, D. G.; Hubbard, A. E.; Hughes, J. W. Nuclear Fusion, Vol. 50, Issue 10 https://doi.org/10.1088/0029-5515/50/10/105005	journal	August 2010
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
ELM characteristics in MAST Kirk, A.; Counsell, G. F.; Wilson, H. R. Plasma Physics and Controlled Fusion, Vol. 46, Issue 3 https://doi.org/10.1088/0741-3335/46/3/009	journal	February 2004
Exploring drift effects in TCV single-null plasmas with the UEDGE code Christen, N.; Theiler, C.; Rognlien, Td Plasma Physics and Controlled Fusion, Vol. 59, Issue 10 https://doi.org/10.1088/1361-6587/aa7c8e	journal	August 2017
Results from recent detachment experiments in alternative divertor configurations on TCV Theiler, C.; Lipschultz, B.; Harrison, J. Nuclear Fusion, Vol. 57, Issue 7 https://doi.org/10.1088/1741-4326/aa5fb7	journal	March 2017
ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets Sorbom, B. N.; Ball, J.; Palmer, T. R. arXiv https://doi.org/10.48550/arxiv.1409.3540	text	January 2014

Cited By (1)

Performance assessment of long-legged tightly-baffled divertor geometries in the ARC reactor concept Wigram, M. R. K.; LaBombard, B.; Umansky, M. V. Nuclear Fusion, Vol. 59, Issue 10 https://doi.org/10.1088/1741-4326/ab394f	journal	September 2019

Similar Records

Performance assessment of long-legged tightly-baffled divertor geometries in the ARC reactor concept

Dataset · Wed Jun 03 00:00:00 EDT 2020 · OSTI ID:1881477

Performance assessment of long-legged tightly-baffled divertor geometries in the ARC reactor concept

Journal Article · Wed Sep 11 20:00:00 EDT 2019 · Nuclear Fusion · OSTI ID:1564344

UEDGE modeling of plasma detachment of CFETR with ITER ‐like divertor geometry by external impurity seeding

Journal Article · Thu Jan 04 19:00:00 EST 2024 · Contributions to Plasma Physics · OSTI ID:2280708

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ARC
UEDGE
detached
divertor
power handling

UEDGE modelling of detached divertor operation for long-leg divertor geometries in ARC

Citation Formats

References (21)

Cited By (1)

Similar Records

Related Subjects