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Title: Tungsten dust impact on ITER-like plasma edge

Journal Article · · Physics of Plasmas
DOI:https://doi.org/10.1063/1.4905704· OSTI ID:1274048
 [1];  [1];  [1];  [2]
  1. Univ. of California San Diego, La Jolla, CA (United States)
  2. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

The impact of tungsten dust originating from divertor plates on the performance of edge plasma in ITER-like discharge is evaluated using computer modeling with the coupled dust-plasma transport code DUSTT-UEDGE. Different dust injection parameters, including dust size and mass injection rates, are surveyed. It is found that tungsten dust injection with rates as low as a few mg/s can lead to dangerously high tungsten impurity concentrations in the plasma core. Dust injections with rates of a few tens of mg/s are shown to have a significant effect on edge plasma parameters and dynamics in ITER scale tokamaks. The large impact of certain phenomena, such as dust shielding by an ablation cloud and the thermal force on tungsten ions, on dust/impurity transport in edge plasma and consequently on core tungsten contamination level is demonstrated. Lastly, it is also found that high-Z impurities provided by dust can induce macroscopic self-sustained plasma oscillations in plasma edge leading to large temporal variations of edge plasma parameters and heat load to divertor target plates.

Research Organization:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
AC52-07NA27344; FG02-06ER54852
OSTI ID:
1274048
Alternate ID(s):
OSTI ID: 1228486
Report Number(s):
LLNL-JRNL-678548; PHPAEN
Journal Information:
Physics of Plasmas, Vol. 22, Issue 1; ISSN 1070-664X
Publisher:
American Institute of Physics (AIP)Copyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 25 works
Citation information provided by
Web of Science

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Cited By (3)

Experimental and modeling study of chemical-based strategies for mitigating dust formation in fusion reactors journal February 2019
Survival and in-vessel redistribution of beryllium droplets after ITER disruptions journal May 2018
Pre-plasma remobilization of ferromagnetic dust in FTU and possible interference with tokamak operations journal September 2019

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