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Title: Scrape-off layer plasma and neutral characteristics and their interactions with walls for FNSF

Abstract

Simulations of the heat flux on plasma facing components from exhausting core plasma are reported for two possible Fusion Nuclear Science Facility (FNSF) divertor configurations. One configuration utilizes divertor plates strongly inclined with respect to the poloidal magnetic flux surfaces like that planned for ITER and results in a partially detached divertor-plasma. The second configuration has divertor plates orthogonal to the flux surfaces, which leads to a fully detached divertor-plasma if the width of the divertor region is sufficient. Both configurations use scrape-off layer impurity seeding to yield an acceptable peak heat flux of ~10 MW/m2 or smaller on the divertor plates and chamber walls. The roles of recycled hydrogenic atoms and molecules are investigated and distribution of sputtering tungsten throughout the edge region modeled. Furthermore, the simulations are performed with the UEDGE 2D transport code to model both plasma and neutral components with supplementary neutral modeling performed with the DEGAS 2 Monte Carlo code.

Authors:
 [1];  [1];  [2]
  1. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  2. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Publication Date:
Research Org.:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1476857
Report Number(s):
LLNL-JRNL-718388
Journal ID: ISSN 0920-3796; 862726
Grant/Contract Number:  
AC52-07NA27344
Resource Type:
Accepted Manuscript
Journal Name:
Fusion Engineering and Design
Additional Journal Information:
Journal Volume: 135; Journal Issue: PB; Journal ID: ISSN 0920-3796
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Divertor plasma; Heat flux; FNSF; Simulation

Citation Formats

Rognlien, T. D., Rensink, M. E., and Stotler, D. P. Scrape-off layer plasma and neutral characteristics and their interactions with walls for FNSF. United States: N. p., 2018. Web. https://doi.org/10.1016/j.fusengdes.2017.07.024.
Rognlien, T. D., Rensink, M. E., & Stotler, D. P. Scrape-off layer plasma and neutral characteristics and their interactions with walls for FNSF. United States. https://doi.org/10.1016/j.fusengdes.2017.07.024
Rognlien, T. D., Rensink, M. E., and Stotler, D. P. Sat . "Scrape-off layer plasma and neutral characteristics and their interactions with walls for FNSF". United States. https://doi.org/10.1016/j.fusengdes.2017.07.024. https://www.osti.gov/servlets/purl/1476857.
@article{osti_1476857,
title = {Scrape-off layer plasma and neutral characteristics and their interactions with walls for FNSF},
author = {Rognlien, T. D. and Rensink, M. E. and Stotler, D. P.},
abstractNote = {Simulations of the heat flux on plasma facing components from exhausting core plasma are reported for two possible Fusion Nuclear Science Facility (FNSF) divertor configurations. One configuration utilizes divertor plates strongly inclined with respect to the poloidal magnetic flux surfaces like that planned for ITER and results in a partially detached divertor-plasma. The second configuration has divertor plates orthogonal to the flux surfaces, which leads to a fully detached divertor-plasma if the width of the divertor region is sufficient. Both configurations use scrape-off layer impurity seeding to yield an acceptable peak heat flux of ~10 MW/m2 or smaller on the divertor plates and chamber walls. The roles of recycled hydrogenic atoms and molecules are investigated and distribution of sputtering tungsten throughout the edge region modeled. Furthermore, the simulations are performed with the UEDGE 2D transport code to model both plasma and neutral components with supplementary neutral modeling performed with the DEGAS 2 Monte Carlo code.},
doi = {10.1016/j.fusengdes.2017.07.024},
journal = {Fusion Engineering and Design},
number = PB,
volume = 135,
place = {United States},
year = {2018},
month = {10}
}

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Cited by: 6 works
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Figures / Tables:

Figure 1 Figure 1: Lower-half FNSF domain used for edge-region simulations.

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Works referenced in this record:

Characterization of a partially‐ionized, detached, divertor plasma
journal, September 1996

  • Knoll, D. A.; Krasheninnikov, S. I.; McHugh, P. R.
  • Physics of Plasmas, Vol. 3, Issue 9
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Simulation of dense recombining divertor plasmas with a Navier–Stokes neutral transport model
journal, January 1996

  • Knoll, D. A.; McHugh, P. R.; Krasheninnikov, S. I.
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A first-principles predictive model of the pedestal height and width: development, testing and ITER optimization with the EPED model
journal, August 2011


Analysis of performance of the optimized divertor in ITER
journal, May 2009


Effects of divertor geometry on tokamak plasmas
journal, May 2001


    Works referencing / citing this record:

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    journal, July 2019


    Integrated Liquid Metal Flowing First Wall and Open-Surface Divertor for Fusion Nuclear Science Facility: Concept, Design, and Analysis
    journal, May 2019


    Bifurcations and oscillations in divertor plasma
    journal, May 2019

    • Kukushkin, A. S.; Krasheninnikov, S. I.
    • Plasma Physics and Controlled Fusion, Vol. 61, Issue 7
    • DOI: 10.1088/1361-6587/ab1bba

    Critical Exploration of Liquid Metal Plasma-Facing Components in a Fusion Nuclear Science Facility
    journal, June 2019