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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 |
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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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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.</creator><creatorcontrib>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. ; Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)</creatorcontrib><description><![CDATA[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 (<inline-formula> <tex-math notation="LaTeX">D </tex-math></inline-formula>) and impurities (<inline-formula> <tex-math notation="LaTeX">W </tex-math></inline-formula>, <inline-formula> <tex-math notation="LaTeX">O </tex-math></inline-formula>, and <inline-formula> <tex-math notation="LaTeX">C </tex-math></inline-formula>) 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 (<inline-formula> <tex-math notation="LaTeX">n_{e} </tex-math></inline-formula> and <inline-formula> <tex-math notation="LaTeX">T_{e} </tex-math></inline-formula>) 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.]]></description><identifier>ISSN: 0093-3813</identifier><identifier>EISSN: 1939-9375</identifier><identifier>DOI: 10.1109/TPS.2022.3187619</identifier><identifier>CODEN: ITPSBD</identifier><language>eng</language><publisher>New York: IEEE</publisher><subject>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</subject><ispartof>IEEE transactions on plasma science, 2022-11, Vol.50 (11), p.4251-4256</ispartof><rights>Copyright The Institute of Electrical and Electronics Engineers, Inc. (IEEE) 2022</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c360t-488bf2cc8a8e014460fd991e5472ff200c154a85ceb4de5d2eb60dd847ebbcfa3</citedby><cites>FETCH-LOGICAL-c360t-488bf2cc8a8e014460fd991e5472ff200c154a85ceb4de5d2eb60dd847ebbcfa3</cites><orcidid>0000-0003-1353-8865 ; 0000-0001-7123-7433 ; 0000-0002-0961-9139 ; 0000-0001-8118-8719 ; 0000-0001-8615-6812 ; 0000-0001-9107-8337 ; 0000-0002-5640-5854 ; 0000-0002-2166-5621 ; 0000-0001-7662-5961 ; 0000000256405854 ; 0000000221665621 ; 0000000181188719 ; 0000000186156812 ; 0000000171237433 ; 0000000209619139 ; 0000000191078337 ; 0000000176625961 ; 0000000313538865</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://ieeexplore.ieee.org/document/9844654$$EHTML$$P50$$Gieee$$H</linktohtml><link.rule.ids>230,314,780,784,885,27924,27925,54796</link.rule.ids><backlink>$$Uhttps://www.osti.gov/servlets/purl/1881067$$D View this record in Osti.gov$$Hfree_for_read</backlink></links><search><creatorcontrib>Grosjean, Alex</creatorcontrib><creatorcontrib>Radenac, T.</creatorcontrib><creatorcontrib>Fedorczak, N.</creatorcontrib><creatorcontrib>Donovan, D. C.</creatorcontrib><creatorcontrib>Guillemaut, C.</creatorcontrib><creatorcontrib>Johnson, C. A.</creatorcontrib><creatorcontrib>Gunn, J. P.</creatorcontrib><creatorcontrib>Ardizzone, P. L.</creatorcontrib><creatorcontrib>Clairet, F.</creatorcontrib><creatorcontrib>Easley, D. C.</creatorcontrib><creatorcontrib>Gil, C.</creatorcontrib><creatorcontrib>Klepper, C. C.</creatorcontrib><creatorcontrib>Kosslow, S. R.</creatorcontrib><creatorcontrib>Unterberg, E. A.</creatorcontrib><creatorcontrib>Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)</creatorcontrib><title>Development of an Integrated Multidiagnostic to Assess the High-Z Impurity Fluxes in the Metallic Environment of WEST Using IMAS</title><title>IEEE transactions on plasma science</title><addtitle>TPS</addtitle><description><![CDATA[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 (<inline-formula> <tex-math notation="LaTeX">D </tex-math></inline-formula>) and impurities (<inline-formula> <tex-math notation="LaTeX">W </tex-math></inline-formula>, <inline-formula> <tex-math notation="LaTeX">O </tex-math></inline-formula>, and <inline-formula> <tex-math notation="LaTeX">C </tex-math></inline-formula>) 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 (<inline-formula> <tex-math notation="LaTeX">n_{e} </tex-math></inline-formula> and <inline-formula> <tex-math notation="LaTeX">T_{e} </tex-math></inline-formula>) 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.]]></description><subject>70 PLASMA PHYSICS AND FUSION TECHNOLOGY</subject><subject>Bars</subject><subject>Data flow analysis</subject><subject>diagnostic expert systems</subject><subject>Durability</subject><subject>Fluxes</subject><subject>fusion reactors</subject><subject>Impurities</subject><subject>Magnetic separation</subject><subject>Modelling</subject><subject>Plasma</subject><subject>Plasma measurements</subject><subject>Plasmas</subject><subject>Probes</subject><subject>Spectroscopy</subject><subject>tokamaks</subject><subject>Tungsten</subject><subject>Workflow</subject><issn>0093-3813</issn><issn>1939-9375</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2022</creationdate><recordtype>article</recordtype><recordid>eNo9kc1rGzEQxUVpoG7Se6EX0ZzX0dfuSkeTOI0hpgU7FHoRWu2srbCWXElrklv_9KzjpKc5zO_NvMdD6CslU0qJulr_Wk0ZYWzKqawrqj6gCVVcFYrX5Uc0IUTxgkvKP6HPKT0SQkVJ2AT9u4ED9GG_A59x6LDxeOEzbKLJ0OLl0GfXOrPxIWVncQ54lhKkhPMW8J3bbIs_eLHbD9HlZ3zbD0-QsPOv2yVk0_ejaO4PLgb__uH3fLXGD8n5DV4sZ6sLdNaZPsGXt3mOHm7n6-u74v7nj8X17L6wvCK5EFI2HbNWGgmjd1GRrlWKQilq1nWMEEtLYWRpoREtlC2DpiJtK0UNTWM7w8_R99PdYxKdrMtgtzZ4DzZrKiUlVT1ClydoH8PfAVLWj2GIfvSlWS1YTYQUfKTIibIxpBSh0_vodiY-a0r0sQw9lqGPZei3MkbJt5PEAcB_XMkxSCn4C6vJhig</recordid><startdate>20221101</startdate><enddate>20221101</enddate><creator>Grosjean, Alex</creator><creator>Radenac, T.</creator><creator>Fedorczak, N.</creator><creator>Donovan, D. 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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. 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C.</creatorcontrib><creatorcontrib>Guillemaut, C.</creatorcontrib><creatorcontrib>Johnson, C. A.</creatorcontrib><creatorcontrib>Gunn, J. P.</creatorcontrib><creatorcontrib>Ardizzone, P. L.</creatorcontrib><creatorcontrib>Clairet, F.</creatorcontrib><creatorcontrib>Easley, D. C.</creatorcontrib><creatorcontrib>Gil, C.</creatorcontrib><creatorcontrib>Klepper, C. C.</creatorcontrib><creatorcontrib>Kosslow, S. R.</creatorcontrib><creatorcontrib>Unterberg, E. A.</creatorcontrib><creatorcontrib>Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)</creatorcontrib><collection>IEEE All-Society Periodicals Package (ASPP) 2005-present</collection><collection>IEEE All-Society Periodicals Package (ASPP) 1998–Present</collection><collection>IEL</collection><collection>CrossRef</collection><collection>Electronics & Communications Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>Technology Research Database</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>OSTI.GOV - Hybrid</collection><collection>OSTI.GOV</collection><jtitle>IEEE transactions on plasma science</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Grosjean, Alex</au><au>Radenac, T.</au><au>Fedorczak, N.</au><au>Donovan, D. C.</au><au>Guillemaut, C.</au><au>Johnson, C. A.</au><au>Gunn, J. P.</au><au>Ardizzone, P. L.</au><au>Clairet, F.</au><au>Easley, D. C.</au><au>Gil, C.</au><au>Klepper, C. C.</au><au>Kosslow, S. R.</au><au>Unterberg, E. A.</au><aucorp>Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Development of an Integrated Multidiagnostic to Assess the High-Z Impurity Fluxes in the Metallic Environment of WEST Using IMAS</atitle><jtitle>IEEE transactions on plasma science</jtitle><stitle>TPS</stitle><date>2022-11-01</date><risdate>2022</risdate><volume>50</volume><issue>11</issue><spage>4251</spage><epage>4256</epage><pages>4251-4256</pages><issn>0093-3813</issn><eissn>1939-9375</eissn><coden>ITPSBD</coden><abstract><![CDATA[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 (<inline-formula> <tex-math notation="LaTeX">D </tex-math></inline-formula>) and impurities (<inline-formula> <tex-math notation="LaTeX">W </tex-math></inline-formula>, <inline-formula> <tex-math notation="LaTeX">O </tex-math></inline-formula>, and <inline-formula> <tex-math notation="LaTeX">C </tex-math></inline-formula>) 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 (<inline-formula> <tex-math notation="LaTeX">n_{e} </tex-math></inline-formula> and <inline-formula> <tex-math notation="LaTeX">T_{e} </tex-math></inline-formula>) 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.]]></abstract><cop>New York</cop><pub>IEEE</pub><doi>10.1109/TPS.2022.3187619</doi><tpages>6</tpages><orcidid>https://orcid.org/0000-0003-1353-8865</orcidid><orcidid>https://orcid.org/0000-0001-7123-7433</orcidid><orcidid>https://orcid.org/0000-0002-0961-9139</orcidid><orcidid>https://orcid.org/0000-0001-8118-8719</orcidid><orcidid>https://orcid.org/0000-0001-8615-6812</orcidid><orcidid>https://orcid.org/0000-0001-9107-8337</orcidid><orcidid>https://orcid.org/0000-0002-5640-5854</orcidid><orcidid>https://orcid.org/0000-0002-2166-5621</orcidid><orcidid>https://orcid.org/0000-0001-7662-5961</orcidid><orcidid>https://orcid.org/0000000256405854</orcidid><orcidid>https://orcid.org/0000000221665621</orcidid><orcidid>https://orcid.org/0000000181188719</orcidid><orcidid>https://orcid.org/0000000186156812</orcidid><orcidid>https://orcid.org/0000000171237433</orcidid><orcidid>https://orcid.org/0000000209619139</orcidid><orcidid>https://orcid.org/0000000191078337</orcidid><orcidid>https://orcid.org/0000000176625961</orcidid><orcidid>https://orcid.org/0000000313538865</orcidid><oa>free_for_read</oa></addata></record> |
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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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