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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/m 2 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. doi: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. doi: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. doi: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 referencing / citing this record:

Potential Impacts of Liquid-Metal Plasma-Facing Components on Heating and Current Drive Actuators for a Fusion Nuclear Science Facility
journal, July 2019