Multi-code estimation of DTT edge transport parameters

[1]  F. Crisanti,et al.  Design of a multi-configurations divertor for the DTT facility , 2022, Nuclear Materials and Energy.

[2]  B. LaBombard,et al.  Cross-code comparison of the edge codes SOLPS-ITER, SOLEDGE2D and UEDGE in modelling a low-power scenario in the DTT , 2021, Nuclear Fusion.

[3]  G. Falchetto,et al.  Progress in edge plasma turbulence modelling—hierarchy of models from 2D transport application to 3D fluid simulations in realistic tokamak geometry , 2021, Nuclear Fusion.

[4]  B. Baiocchi,et al.  First principle-based multi-channel integrated modelling in support of the design of the Divertor Tokamak Test facility , 2021, Nuclear Fusion.

[5]  R. Ambrosino,et al.  DTT - Divertor Tokamak Test facility: A testbed for DEMO , 2021 .

[6]  P. Innocente,et al.  Development of DTT single null divertor scenario , 2021, Nuclear Materials and Energy.

[7]  Martine Baelmans,et al.  The new SOLPS-ITER code package , 2015 .

[8]  N. Fedorczak,et al.  Numerical modelling for divertor design of the WEST device with a focus on plasma–wall interactions , 2015 .

[9]  B. P. Duval,et al.  20 years of research on the Alcator C-Mod tokamak , 2014 .

[10]  Masahiro Kobayashi,et al.  Recent Improvements in the EMC3‐Eirene Code , 2014 .

[11]  J. Contributors,et al.  Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER , 2013 .

[12]  J. Bucalossi,et al.  Near wall plasma simulation using penalization technique with the transport code SolEdge2D-Eirene , 2013 .

[13]  T. Osborne,et al.  Spatial resolution of the JET Thomson scattering system. , 2012, The Review of scientific instruments.

[14]  W. Houlberg,et al.  Bootstrap current and neoclassical transport in tokamaks of arbitrary collisionality and aspect ratio , 1997 .

[15]  P. Stangeby,et al.  Experimental divertor physics , 1997 .

[16]  J. Milovich,et al.  A fully implicit, time dependent 2-D fluid code for modeling tokamak edge plasmas , 1992 .

[17]  G. Calabrò,et al.  Assessment of Scrape-Off Layer and divertor plasma conditions in JT-60SA with tungsten wall and nitrogen injection , 2019 .

[18]  M. Romanelli,et al.  Integrated modelling of H-mode pedestal and confinement in JET-ILW , 2017 .

[19]  R. Albanese,et al.  DTT: a divertor tokamak test facility for the study of the power exhaust issues in view of DEMO , 2016 .

[20]  Frederic Imbeaux,et al.  Core turbulent transport in tokamak plasmas: bridging theory and experiment with QuaLiKiz , 2015 .