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Simulations of NSTX with a Liquid Lithium Divertor Module

Journal Article · · Contributions to Plasma Physics
 [1];  [2];  [1];  [1];  [3];  [4];  [4]
  1. Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
  2. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
  3. University of California, San Diego, CA (United States)
  4. Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
+ Show Author Affiliations
Here, a strategy to develop self-consistent simulations of the behavior of lithium in the Liquid Lithium Divertor (LLD) module to be installed in NSTX is described. In this initial stage of the plan, the UEDGE edge plasma transport code is used to simulate an existing NSTX shot, with UEDGE's transport coefficients set using midplane and divertor diagnostic data. The LLD is incorporated into the simulations as a reduction in the recycling coefficient over the outer divertor. Heat transfer calculations performed using the resulting heat flux profiles provide preliminary estimates on operating limits for the LLD as well as input data for subsequent steps in the LLD modeling effort.
Research Organization:
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC02-09CH11466; AC05-00OR22725; AC52-07NA27344; FG02-04ER54739
OSTI ID:
1898292
Alternate ID(s):
OSTI ID: 1170768
OSTI ID: 21330269
Report Number(s):
LLNL-JRNL-416343; 377688
Journal Information:
Contributions to Plasma Physics, Journal Name: Contributions to Plasma Physics Journal Issue: 3-5 Vol. 50; ISSN 0863-1042
Publisher:
WileyCopyright Statement
Country of Publication:
United States
Language:
English

References (13)

Multi-Fluid Modeling of Large Parallel Plasma Flows in the Tokamak Scrape-Off Layer journal September 2006
2-D Fluid Transport Simulations of Gaseous/Radiative Divertors journal January 1994
Neutral Gas Transport Modeling with DEGAS 2 journal January 1994
Divertor heat flux scaling with heating power and plasma current in H-mode discharges in the national spherical torus experiment journal June 2007
Simulation of large parallel plasma flows in the tokamak SOL driven by cross-field transport asymmetries journal June 2007
Transition to ELM-free improved H-mode by lithium deposition on NSTX graphite divertor surfaces journal June 2009
Evaporated lithium surface coatings in NSTX journal June 2009
Low recycling and high power density handling physics in the Current Drive Experiment-Upgrade with lithium plasma-facing components journal May 2007
The effect of lithium surface coatings on plasma performance in the National Spherical Torus Experiment journal May 2008
Exploration of spherical torus physics in the NSTX device journal March 2000
Recent liquid lithium limiter experiments in CDX-U journal May 2005
The Plasma Boundary of Magnetic Fusion Devices book January 2000
The Plasma Boundary of Magnetic Fusion Devices book January 2000

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Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
NSTX
UEDGE
lithium
recycling