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

Journal Article · · Fusion Engineering and Design
 [1];  [1];  [2]
  1. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  2. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
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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.
Research Organization:
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC52-07NA27344
OSTI ID:
1476857
Alternate ID(s):
OSTI ID: 22850345
Report Number(s):
LLNL-JRNL--718388; 862726
Journal Information:
Fusion Engineering and Design, Journal Name: Fusion Engineering and Design Journal Issue: PB Vol. 135; ISSN 0920-3796
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

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Cited By (4)

Integrated Liquid Metal Flowing First Wall and Open-Surface Divertor for Fusion Nuclear Science Facility: Concept, Design, and Analysis journal May 2019
Critical Exploration of Liquid Metal Plasma-Facing Components in a Fusion Nuclear Science Facility journal June 2019
Potential Impacts of Liquid-Metal Plasma-Facing Components on Heating and Current Drive Actuators for a Fusion Nuclear Science Facility journal July 2019
Bifurcations and oscillations in divertor plasma journal May 2019

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Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Divertor plasma
FNSF
Heat flux
Simulation