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Title: Developing and validating advanced divertor solutions on DIII-D for next-step fusion devices

Journal Article · · Nuclear Fusion
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  1. General Atomics, San Diego, CA (United States)
  2. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  3. Univ. of Toronto, ON (Canada)
  4. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  5. Univ. of California, San Diego, La Jolla CA (United States)
  6. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  7. Univ. of Texas, Austin, TX (United States)
  8. Univ. of Tennessee, Knoxville, TN (United States)
  9. Dalian Univ. of Technology, Liaoning (China)
  10. Princeton Univ., Princeton, NJ (United States)
  11. Aalto Univ., Espoo (Finland)
  12. Univ. of Wisconsin, Madison, WI (United States)
  13. Univ. of California, San Diego, La Jolla, CA (United States)
  14. Institute of Plasma Physics, Anhui (China)
+ Show Author Affiliations

A major challenge facing the design and operation of next-step high-power steady-state fusion devices is to develop a viable divertor solution with order-of-magnitude increases in power handling capability relative to present experience, while having acceptable divertor target plate erosion and being compatible with maintaining good core plasma confinement. A new initiative has been launched on DIII-D to develop the scientific basis for design, installation, and operation of an advanced divertor to evaluate boundary plasma solutions applicable to next step fusion experiments beyond ITER. Developing the scientific basis for fusion reactor divertor solutions must necessarily follow three lines of research, which we plan to pursue in DIII-D: (1) Advance scientific understanding and predictive capability through development and comparison between state-of-the art computational models and enhanced measurements using targeted parametric scans; (2) Develop and validate key divertor design concepts and codes through innovative variations in physical structure and magnetic geometry; (3) Assess candidate materials, determining the implications for core plasma operation and control, and develop mitigation techniques for any deleterious effects, incorporating development of plasma-material interaction models. These efforts will lead to design, installation, and evaluation of an advanced divertor for DIII-D to enable highly dissipative divertor operation at core density (n e/n GW), neutral fueling and impurity influx most compatible with high performance plasma scenarios and reactor relevant plasma facing components (PFCs). In conclusion, this paper highlights the current progress and near-term strategies of boundary/PMI research on DIII-D.

Research Organization:
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States); Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); General Atomics, San Diego, CA (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA); USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Grant/Contract Number:
AC52-07NA27344; AC02-09CH11466; AC04-94AL85000; AC05-00OR22725; FC02-04ER54698; FG02-07ER54917; AC52-07NA273441
OSTI ID:
1890827
Alternate ID(s):
OSTI ID: 1324473; OSTI ID: 1325161; OSTI ID: 1325501; OSTI ID: 1371903
Report Number(s):
LLNL-JRNL-737385; SAND-2016-4859J; 890066; TRN: US2310091
Journal Information:
Nuclear Fusion, Vol. 56, Issue 12; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 20 works
Citation information provided by
Web of Science

References (19)

Geometrical properties of a “snowflake” divertor journal June 2007
Tungsten divertor erosion in all metal devices: Lessons from the ITER like wall of JET journal July 2013
ADX: a high field, high power density, advanced divertor and RF tokamak journal April 2015
The ‘churning mode’ of plasma convection in the tokamak divertor region journal July 2014
Plasma-wall interaction and plasma behaviour in the non-boronised all tungsten ASDEX Upgrade journal June 2009
Effects of divertor geometry on tokamak plasmas journal May 2001
DIII-D research to address key challenges for ITER and fusion energy journal July 2015
Compact DEMO, SlimCS: design progress and issues journal July 2009
Influence of cross-field drifts and chemical sputtering on simulations of divertor particle and heat loads in ohmic and L-mode plasmas in DIII-D, AUG, and JET using UEDGE journal August 2011
Super-X divertors and high power density fusion devices journal May 2009
A Fusion Nuclear Science Facility for a fast-track path to DEMO journal October 2014
Simulation of gross and net erosion of high- Z materials in the DIII-D divertor journal December 2015
Simulation study for divertor design to handle huge exhaust power in the SlimCS DEMO reactor journal May 2009
Finalizing the ITER divertor design: The key role of SOLPS modeling journal December 2011
Modeling of detachment experiments at DIII-D journal August 2015
Heat flux management via advanced magnetic divertor configurations and divertor detachment journal August 2015
Scrape-off layer radiation and heat load to the ASDEX Upgrade LYRA divertor journal July 1999
Evaluation of CFETR as a Fusion Nuclear Science Facility using multiple system codes journal January 2015
Overview of the results on divertor heat loads in RMP controlled H-mode plasmas on DIII-D journal August 2009

Cited By (2)

Physics of ultimate detachment of a tokamak divertor plasma journal September 2017
Erosion dynamics of tungsten fuzz during ELM-like heat loading journal April 2018

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Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
divertor concept
plasma-material interactions
DIII-D
advanced tokamak
fusion reactor