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Development of an Integrated Multidiagnostic to Assess the High-Z Impurity Fluxes in the Metallic Environment of WEST Using IMAS

WEST is an actively cooled, long-pulse tokamak with nearly all plasma-facing components (PFC) made of tungsten. One of the aims of WEST is to study plasma operations with tungsten PFCs in preparation for long-pulse operations on high-Z divertor devices, such as ITER. For long-pulse operation, the hi...

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Published in:IEEE transactions on plasma science 2022-11, Vol.50 (11), p.4251-4256
Main Authors: Grosjean, Alex, Radenac, T., Fedorczak, N., Donovan, D. C., Guillemaut, C., Johnson, C. A., Gunn, J. P., Ardizzone, P. L., Clairet, F., Easley, D. C., Gil, C., Klepper, C. C., Kosslow, S. R., Unterberg, E. A.
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cited_by cdi_FETCH-LOGICAL-c360t-488bf2cc8a8e014460fd991e5472ff200c154a85ceb4de5d2eb60dd847ebbcfa3
cites cdi_FETCH-LOGICAL-c360t-488bf2cc8a8e014460fd991e5472ff200c154a85ceb4de5d2eb60dd847ebbcfa3
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container_issue 11
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container_title IEEE transactions on plasma science
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creator Grosjean, Alex
Radenac, T.
Fedorczak, N.
Donovan, D. C.
Guillemaut, C.
Johnson, C. A.
Gunn, J. P.
Ardizzone, P. L.
Clairet, F.
Easley, D. C.
Gil, C.
Klepper, C. C.
Kosslow, S. R.
Unterberg, E. A.
description WEST is an actively cooled, long-pulse tokamak with nearly all plasma-facing components (PFC) made of tungsten. One of the aims of WEST is to study plasma operations with tungsten PFCs in preparation for long-pulse operations on high-Z divertor devices, such as ITER. For long-pulse operation, the high-Z impurity content and transport to the core plasma are critical concerns that require further measurement and interpretation to improve plasma performance and PFC durability. This work details the impurity influxes in WEST during a series of discharges in which the lower hybrid (LH) injected power was incrementally increased. An analysis has been performed of measurements collected from an array of edge diagnostics. Visible spectroscopy was utilized to measure the spectral radiances generated by fuel particles ( D ) and impurities ( W , O , and C ) at the divertor and at the antennas with a newly developed spectral peak-fitting tool used to analyze the data in WEST. The scrape-off layer (SOL) plasma conditions ( n_{e} and T_{e} ) measured at the divertor target with flush Langmuir probes and near the outer mid-plane (OMP) using reciprocating Langmuir probes (RCPs) are used to evaluate the number of ionizations per photons (S/XB) coefficients required to estimate the impurity fluxes obtained with the collisional-radiative model ColRadPy. The array of edge diagnostics discussed in this work, coupled with SOL plasma modeling tools, represents a multidiagnostic interpretative modeling workflow that will continue to be applied to upcoming experimental campaigns on the WEST experiment to assess high-Z impurity transport.
doi_str_mv 10.1109/TPS.2022.3187619
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source IEEE Electronic Library (IEL) Journals
subjects 70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Bars
Data flow analysis
diagnostic expert systems
Durability
Fluxes
fusion reactors
Impurities
Magnetic separation
Modelling
Plasma
Plasma measurements
Plasmas
Probes
Spectroscopy
tokamaks
Tungsten
Workflow
title Development of an Integrated Multidiagnostic to Assess the High-Z Impurity Fluxes in the Metallic Environment of WEST Using IMAS
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