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Integrated modelling of core and divertor plasmas for the DEMO Fusion Neutron Source hybrid facility

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dc.contributor.authorDnestrovskiy, A. Y.
dc.contributor.authorSergeev, V. V.
dc.contributor.authorKukushkin, A. S.
dc.contributor.authorKuteev, B. V.
dc.contributor.authorКутеев, Борис Васильевич
dc.date.accessioned2024-11-21T11:02:55Z
dc.date.available2024-11-21T11:02:55Z
dc.date.issued2019
dc.description.abstractA steady state regime for the tokamak-based DEMO Fusion Neutron Source (DEMO-FNS) with parameters R/a = 3.2 m/1.0 m, B = 5 T, I-pl = 4-5 MA, P-NBI = 30 MW and P-ECR = 6 MW is studied using coupled simulations of the central and divertor plasma. In our analysis, the divertor plasma state is determined by the values of the heat flux P-SOL, the pressure of the neutrals in the divertor p(n) and the total number of neon particles N-Ne outside the separatrix. As the boundary conditions for the core plasma, we use the values at the separatrix of the electron density, n(e_sep), and temperatures of the ions, T-i_sep, and electrons, T-e_sep the concentration of the neon impurity normalized to the electron density at the separatrix, C-Ne = Sigma n(Ne)/n(e_sep) and the hydrogen neutral influx into the core plasma, Gamma(0sep). In the divertor region, all the values are calculated using the SOLPS4.3 code for a number of operating points (similar to 150 in our case) with different values of P-SOL, p(n )and N-Ne. Then the calculation results are approximated by analytical formulas. Power balance in the core plasma is calculated using the ASTRA and NUBEAM codes. The hydrogen (deuterium and tritium) density is modelled taking into account the sources generated by the neutrals originating from the divertor region, as well as by injection of fast atoms and pellet injection. The neon density and radiation in the main plasma are simulated using the STRAHL code. As the result of the simulations, the operational regime of DEMO-FNS is determined, in which the heat loading onto the divertor targets remains at the acceptable level below 10 MW m(-2), the divertor plasma does not transit into the 'full detachment' mode and the plasma in a double-null separatrix configuration is kept up-down symmetric. Variations of these conditions versus the impurity level and confinement parameters are investigated and discussed.
dc.identifier.citationIntegrated modelling of core and divertor plasmas for the DEMO Fusion Neutron Source hybrid facility / Dnestrovskiy, AY [et al.] // Nuclear Fusion. - 2019. - 59. - № 9. - 10.1088/1741-4326/ab3075
dc.identifier.doi10.1088/1741-4326/ab3075
dc.identifier.urihttps://www.doi.org/10.1088/1741-4326/ab3075
dc.identifier.urihttps://www.scopus.com/record/display.uri?eid=2-s2.0-85072100409&origin=resultslist
dc.identifier.urihttp://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcAuth=Alerting&SrcApp=Alerting&DestApp=WOS_CPL&DestLinkType=FullRecord&UT=WOS:000480385900005
dc.identifier.urihttps://openrepository.mephi.ru/handle/123456789/18541
dc.relation.ispartofNuclear Fusion
dc.titleIntegrated modelling of core and divertor plasmas for the DEMO Fusion Neutron Source hybrid facility
dc.typeArticle
dspace.entity.typePublication
oaire.citation.issue9
oaire.citation.volume59
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relation.isAuthorOfPublication.latestForDiscovery01454d00-d028-4ca6-8523-61008ff8dbf8
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relation.isOrgUnitOfPublication.latestForDiscoverydcdb137c-0528-46a5-841b-780227a67cce
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