Access and sustainment of ELMy H-mode operation for ITER pre-fusion power operation plasmas using JINTRAC
In the initial stages of ITER operation, ELM mitigation systems need to be commissioned. This requires controlled flat-top operation in type-I ELMy H-mode regimes. Hydrogen or helium plasma discharges are used exclusively in these stages to ensure negligible production of neutrons from fusion reacti...
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IOP Publishing
2025-01-01
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| Series: | Nuclear Fusion |
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| Online Access: | https://doi.org/10.1088/1741-4326/adaf3f |
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| author | E. Tholerus L. Garzotti V. Parail Y. Baranov X. Bonnin G. Corrigan F. Eriksson D. Farina L. Figini D.M. Harting S.H. Kim F. Koechl A. Loarte E. Militello Asp H. Nordman S.D. Pinches A.R. Polevoi P. Strand |
| author_facet | E. Tholerus L. Garzotti V. Parail Y. Baranov X. Bonnin G. Corrigan F. Eriksson D. Farina L. Figini D.M. Harting S.H. Kim F. Koechl A. Loarte E. Militello Asp H. Nordman S.D. Pinches A.R. Polevoi P. Strand |
| author_sort | E. Tholerus |
| collection | DOAJ |
| description | In the initial stages of ITER operation, ELM mitigation systems need to be commissioned. This requires controlled flat-top operation in type-I ELMy H-mode regimes. Hydrogen or helium plasma discharges are used exclusively in these stages to ensure negligible production of neutrons from fusion reactions. With the expected higher L–H power threshold of hydrogen and helium plasmas compared to corresponding D and D/T plasmas, it is uncertain whether available auxiliary power systems are sufficient to operate in stable type-I ELMy H-mode. This has been investigated using integrated core and edge/SOL/divertor modelling with JINTRAC. Assuming that the L–H power threshold is well captured by the Martin08 scaling law, the presented simulations have found that 30 MW of ECRH power is likely required for the investigated hydrogen plasma scenarios, rather than the originally planned 20 MW in the 2016 Staged Approach ITER Baseline. However, past experiments have shown that a small helium fraction (∼10%) can considerably reduce the hydrogen plasma L–H power threshold. Assuming that these results extrapolate to ITER operation regimes, the 7.5 MA/2.65 T hydrogen plasma scenario is likely to access stable type-I ELMy H-mode operation also at 20 MW of ECRH. |
| format | Article |
| id | doaj-art-4d86b490ae904e93aad3d8ee97ace9a7 |
| institution | Kabale University |
| issn | 0029-5515 |
| language | English |
| publishDate | 2025-01-01 |
| publisher | IOP Publishing |
| record_format | Article |
| series | Nuclear Fusion |
| spelling | doaj-art-4d86b490ae904e93aad3d8ee97ace9a72025-02-10T09:03:34ZengIOP PublishingNuclear Fusion0029-55152025-01-0165303600610.1088/1741-4326/adaf3fAccess and sustainment of ELMy H-mode operation for ITER pre-fusion power operation plasmas using JINTRACE. Tholerus0https://orcid.org/0000-0002-3262-1958L. Garzotti1https://orcid.org/0000-0002-3796-9814V. Parail2Y. Baranov3X. Bonnin4G. Corrigan5F. Eriksson6https://orcid.org/0000-0002-2740-7738D. Farina7https://orcid.org/0000-0003-0795-3632L. Figini8https://orcid.org/0000-0002-0034-4028D.M. Harting9S.H. Kim10F. Koechl11A. Loarte12https://orcid.org/0000-0001-9592-1117E. Militello Asp13https://orcid.org/0000-0001-8183-8734H. Nordman14S.D. Pinches15https://orcid.org/0000-0003-0132-945XA.R. Polevoi16P. Strand17https://orcid.org/0000-0002-8899-2598UKAEA (United Kingdom Atomic Energy Authority) , Culham Campus, Abingdon, Oxfordshire OX14 3DB, United Kingdom of Great Britain and Northern IrelandUKAEA (United Kingdom Atomic Energy Authority) , Culham Campus, Abingdon, Oxfordshire OX14 3DB, United Kingdom of Great Britain and Northern IrelandUKAEA (United Kingdom Atomic Energy Authority) , Culham Campus, Abingdon, Oxfordshire OX14 3DB, United Kingdom of Great Britain and Northern IrelandUKAEA (United Kingdom Atomic Energy Authority) , Culham Campus, Abingdon, Oxfordshire OX14 3DB, United Kingdom of Great Britain and Northern IrelandITER Organization , Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex, FranceUKAEA (United Kingdom Atomic Energy Authority) , Culham Campus, Abingdon, Oxfordshire OX14 3DB, United Kingdom of Great Britain and Northern IrelandUKAEA (United Kingdom Atomic Energy Authority) , Culham Campus, Abingdon, Oxfordshire OX14 3DB, United Kingdom of Great Britain and Northern IrelandIstituto per la Scienza e Tecnologia dei Plasmi, CNR , Milan, ItalyIstituto per la Scienza e Tecnologia dei Plasmi, CNR , Milan, ItalyInstitut für Energie- und Klimaforschung IEK-4 , FZJ, TEC, 52425 Jülich, GermanyITER Organization , Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex, FranceUKAEA (United Kingdom Atomic Energy Authority) , Culham Campus, Abingdon, Oxfordshire OX14 3DB, United Kingdom of Great Britain and Northern IrelandITER Organization , Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex, FranceUKAEA (United Kingdom Atomic Energy Authority) , Culham Campus, Abingdon, Oxfordshire OX14 3DB, United Kingdom of Great Britain and Northern IrelandAssociation EURATOM-VR, Chalmers University of Technology , Göteborg, SwedenITER Organization , Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex, FranceITER Organization , Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex, FranceAssociation EURATOM-VR, Chalmers University of Technology , Göteborg, SwedenIn the initial stages of ITER operation, ELM mitigation systems need to be commissioned. This requires controlled flat-top operation in type-I ELMy H-mode regimes. Hydrogen or helium plasma discharges are used exclusively in these stages to ensure negligible production of neutrons from fusion reactions. With the expected higher L–H power threshold of hydrogen and helium plasmas compared to corresponding D and D/T plasmas, it is uncertain whether available auxiliary power systems are sufficient to operate in stable type-I ELMy H-mode. This has been investigated using integrated core and edge/SOL/divertor modelling with JINTRAC. Assuming that the L–H power threshold is well captured by the Martin08 scaling law, the presented simulations have found that 30 MW of ECRH power is likely required for the investigated hydrogen plasma scenarios, rather than the originally planned 20 MW in the 2016 Staged Approach ITER Baseline. However, past experiments have shown that a small helium fraction (∼10%) can considerably reduce the hydrogen plasma L–H power threshold. Assuming that these results extrapolate to ITER operation regimes, the 7.5 MA/2.65 T hydrogen plasma scenario is likely to access stable type-I ELMy H-mode operation also at 20 MW of ECRH.https://doi.org/10.1088/1741-4326/adaf3fITERPFPOscenario developmentintegrated modellingJINTRAC |
| spellingShingle | E. Tholerus L. Garzotti V. Parail Y. Baranov X. Bonnin G. Corrigan F. Eriksson D. Farina L. Figini D.M. Harting S.H. Kim F. Koechl A. Loarte E. Militello Asp H. Nordman S.D. Pinches A.R. Polevoi P. Strand Access and sustainment of ELMy H-mode operation for ITER pre-fusion power operation plasmas using JINTRAC Nuclear Fusion ITER PFPO scenario development integrated modelling JINTRAC |
| title | Access and sustainment of ELMy H-mode operation for ITER pre-fusion power operation plasmas using JINTRAC |
| title_full | Access and sustainment of ELMy H-mode operation for ITER pre-fusion power operation plasmas using JINTRAC |
| title_fullStr | Access and sustainment of ELMy H-mode operation for ITER pre-fusion power operation plasmas using JINTRAC |
| title_full_unstemmed | Access and sustainment of ELMy H-mode operation for ITER pre-fusion power operation plasmas using JINTRAC |
| title_short | Access and sustainment of ELMy H-mode operation for ITER pre-fusion power operation plasmas using JINTRAC |
| title_sort | access and sustainment of elmy h mode operation for iter pre fusion power operation plasmas using jintrac |
| topic | ITER PFPO scenario development integrated modelling JINTRAC |
| url | https://doi.org/10.1088/1741-4326/adaf3f |
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