Boundary condition effects on runaway electron mitigation coil modeling for the SPARC and DIII-D tokamaks.

Autor: Izzo, V.A., Battey, A., Tinguely, R.A., Sweeney, R., Hansen, C.

Publikováno v: Nuclear Fusion; Jun2024, Vol. 64 Issue 6, p1-12, 12p

Plasma–surface interactions during tokamak disruptions and rapid shutdowns

Autor: Hollmann, E.M., Arnoux, G., Commaux, N., Eidietis, N.W., Evans, T.E., Granetz, R.S., Huber, A., Humphreys, D.A., Izzo, V.A., James, A.N., Jernigan, T.C., Lehnen, M., Maddaluno, G., Paccagnella, R., Parks, P.B., Philipps, V., Reinke, M.L., Rudakov, D.L., Saint-Laurent, F., Sizyuk, V., Strait, E.J., Wesley, J.C., Wong, C.P.C., Yu, J.H.

Publikováno v: In Journal of Nuclear Materials 1 August 2011 415(1) Supplement:S27-S34

Theory & Modelling activities in support of the ITER Disruption Mitigation System

Autor: Nardon E., Matsuyama A., Lehnen M., Aleynikov P., Artola F.J., Bandaru V.K., Bardsley O., Beidler M., Bonfiglio D., Boozer A., Breizman B., Brennan D., Decker J., Del Castillo-Negrete D., Embreus O., Ferraro N., Garland N., Harvey R.W., Hoelzl M., Hu D., Huijsmans G., Izzo V.A., Jardin S., Kim C., Konovalov S., Lao L., Lee S.J., Liu C., Liu Y., Lyons B., Martin-Solis J.R., McClenaghan J., McDevitt C., Papp G., Parks P., Paz-Soldan C., Peysson Y., Reux C., Samulyak R., Sommariva C., Spong D., Strauss H., Tang X., JET Contributors

Publikováno v: FEC 2020-28th IAEA Fusion Energy Conference, Virtual Event Europe/Vienna timezone, 10-15 May 2021
info:cnr-pdr/source/autori:Nardon E.; Matsuyama A.; Lehnen M.; Aleynikov P.; Artola F.J.; Bandaru V.K.; Bardsley O.; Beidler M.; Bonfiglio D.; Boozer A.; Breizman B.; Brennan D.; Decker J.; Del Castillo-Negrete D.; Embreus O.; Ferraro N.; Garland N.; Harvey R.W.; Hoelzl M.; Hu D.; Huijsmans G.; Izzo V.A.; Jardin S.; Kim C.; Konovalov S.; Lao L.; Lee S.J.; Liu C.; Liu Y.; Lyons B.; Martin-Solis J.R.; McClenaghan J.; McDevitt C.; Papp G.; Parks P.; Paz-Soldan C.; Peysson Y.; Reux C.; Samulyak R.; Sommariva C.; Spong D.; Strauss H.; Tang X.; JET Contributors/congresso_nome:FEC 2020-28th IAEA Fusion Energy Conference/congresso_luogo:Virtual Event Europe%2FVienna timezone/congresso_data:10-15 May 2021/anno:2021/pagina_da:/pagina_a:/intervallo_pagine

The ITER Disruption Mitigation System (DMS) should ensure that heat loads, ElectroMagnetic (EM) loads, and Runaway Electron (RE) impacts remain tolerable during ITER disruptions. The design of the Baseline ITER DMS, which shall be available from the

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=cnr_________::86af1457f115d0ea97b76417cf53b842
https://publications.cnr.it/doc/453939

Interpretive MHD modeling of dispersive shell pellet injection for rapid shutdown in tokamaks.

Autor: Izzo, V.A.

Publikováno v: Nuclear Fusion; Jun2020, Vol. 60 Issue 6, p1-10, 10p

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