Accès ouvert
2019
article
OpenAlex
E. Joffrin, S. Abduallev, M. Abhangi, P. Abreu et autres
Abstract For the past several years, the JET scientific programme (Pamela et al 2007 Fusion Eng. Des. 82 590) has been engaged in a multi-campaign effort, including experiments in D, H and T, leading up to 2020 and the first experiments with …
fr, de, in, pt, ru, gb, fi, jp, it, gr, se, ro, es, us, hu, lv, pl, ua, cz, ch
(code pays fourni par la source)
Accès ouvert
2018
article
OpenAlex
M. Valentinuzzi, Y. Marandet, H. Bufferand, Giuseppe Ciraolo et autres
A new hybrid fluid-kinetic code for the atoms has been developed and implemented in Soledge2D. The new code package is able to simulate the evolution of ions, electrons, molecules and two different populations (or phases) of atoms in realistic 2D geometry. Simulations …
fr
(code pays fourni par la source)
Accès ouvert
2018
article
OpenAlex
F. Nespoli, H. Bufferand, M. Valentinuzzi, N. Fedorczak et autres
The edge and scrape-off layer (SOL) plasma of the inter-ELM phase of an H-mode discharge from the TCV tokamak is modeled with the transport code SolEdge2D-EIRENE (Bufferand et al. Nuclear Fusion 55 (2015)). The numerical simulations, in presence and in absence of …
fr, ch, cz, de, gb
(code pays fourni par la source)
2018
article
OpenAlex
M. Valentinuzzi, Giorgio Giorgiani, Y. Marandet, H. Bufferand et autres
fr
(code pays fourni par la source)
Accès ouvert
2018
article
OpenAlex
M. Valentinuzzi, Giorgio Giorgiani, Y. Marandet, H. Bufferand et autres
A new neutral fluid code has been developed as a necessary step towards a hybrid fluid/kinetic neutral model, to be used in ITER or DEMO simulations, where part of the divertor will be very collisional for neutrals. The neutral fluid code, which …
fr
(code pays fourni par la source)
Accès ouvert
2018
article
OpenAlex
Guido Ciraolo, H. Bufferand, Pierfrancesco Di Cintio, Ph. Ghendrih et autres
In order to improve the presently used ad hoc flux limiter treatment of parallel heat flux transport in edge plasma fluid codes, here, we consider a generalized version of the Fourier law implementing a non‐local kernel for the heat flux computation. The …
fr, it
(code pays fourni par la source)
Accès ouvert
2017
article
OpenAlex
A. Gallo, N. Fedorczak, S. Elmore, R. Maurizio et autres
Abstract A deep understanding of plasma transport at the edge of magnetically confined fusion plasmas is needed for the handling and control of heat loads on the machine first wall. Experimental observations collected on a number of tokamaks over the last three …
fr, gb, ch, us, de
(code pays fourni par la source)
Accès ouvert
2017
article
OpenAlex
X. Litaudon, S. Abduallev, M. Abhangi, P. Abreu et autres
Documento escrito por un elevado número de autores/as, sólo se referencia el/la que aparece en primer lugar y los/as autores/as pertenecientes a la UC3M.
gb, de, in, pt, fi, fr, jp, it, es, ru, se, ro, us, lv, pl, cz
(code pays fourni par la source)
Accès ouvert
2017
article
OpenAlex
Y. Marandet, H. Bufferand, N. Nace, M. Valentinuzzi et autres
Transport codes are the main workhorses for global edge studies and modern divertor design. These tools do not resolve turbulent fluctuations responsible for the bulk of cross-field transport in the Scrape-off Layer (SOL), and solve mean field equations instead. Turbulent fluxes are …
fr
(code pays fourni par la source)
Accès ouvert
2017
article
OpenAlex
Giuseppe Ciraolo, H. Bufferand, J. Bucalossi, Ph. Ghendrih et autres
Simulations of WEST H-mode divertor scenarios have been performed with SOLEDGE2D-EIRENE edge plasma transport code, both for pure deuterium and nitrogen seeded discharge. In the pure deuterium case, a target heat flux of 8 MW/m2 is reached, but misalignment between heat and …
fr
(code pays fourni par la source)
Accès ouvert
2017
article
OpenAlex
H. Bufferand, C. Baudoin, J. Bucalossi, Giuseppe Ciraolo et autres
In order to improve cross-field transport description, drifts and currents have been implemented in SOLEDGE2D–EIRENE. The derivation of an equation for the electric potential is recalled. The resolution of current equation is tested in a simple slab case. WEST divertor simulations in …
fr, ch
(code pays fourni par la source)
2017
conference-paper
OpenAlex
Y. Marandet, H. Bufferand, Giuseppe Ciraolo, N. Nace et autres
An overview of issues related to the interplay between atomic process and turbulence in the peripheral regions of magnetically confined fusion devices is presented. Both atomic processes and turbulence play key roles for fusion, but have most of the time been treated …
fr
(code pays fourni par la source)