RF discharge mirror cleaning system development for ITER diagnostics

Autor: Shigin, Pavel ^*, Babinov, Nikita, De Temmerman, Gregory, Danisi, Alessandro, Dmitriev, Artem, Larsen, Jens, Madsen, Rene, Marot, Laurent, Moser, Lucas, Mukhin, Eugene, Kochergin, Mikhail, Ortiz, Rafael, Razdobarin, Alexey, Reichle, Roger, Pitts, Richard, Samsonov, Dmitry, Tsalas, Maximos, Udintsev, Victor, Vayakis, George, Walsh, Michael

Publikováno v: In Fusion Engineering and Design March 2021 164

MINT, an ITER Tool for Interactive Visualization of Data

Autor: Abadie, Lana, Carannante, Giuseppe, Kalsi, Sukhmeet Singh, Makowski, Dariusz, Mazur, Piotr, Neto, Andre, Nunes, Isabel, Panchumarti, Jaswant, Perek, Piotr, Pinches, Simon, Simrock, Stefan, Tsalas, Maximos

ITER will produce large volumes of data that need to be visualized and analyzed. This paper describes the development of a graphical data visualization and exploration tool, MINT (Make Informative and Nice Trends), for plant engineers, operators and

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::78d53b9a293371725b8453a7c8f27c60

Modelling of combined ICRF and NBI heating in JET hybrid plasmas

Autor: Gallart Dani, Mantsinen Mervi, Challis Clive, Frigione Domenico, Graves Jonathan, Hobirk Joerg, Belonohy Eva, Czarnecka Agata, Eriksson Jacob, Goniche Marc, Hellesen Carl, Jacquet Philippe, Joffrin Emmanuel, Krawczyk Natalia, King Damian, Lennholm Morten, Lerche Ernesto, Pawelec Ewa, Sips George, Solano Emilia, Tsalas Maximos, Valisa Marco

Publikováno v: EPJ Web of Conferences, Vol 157, p 03015 (2017)

During the 2015-2016 JET campaigns many efforts have been devoted to the exploration of high performance plasma scenarios envisaged for ITER operation. In this paper we model the combined ICRF+NBI heating in selected key hybrid discharges using PION.

Externí odkaz: https://doaj.org/article/00273138205f4167a3a30b7b60526587

A first analysis of JET plasma profile based indicators for disruption prediction and avoidance

Autor: Pau Alessandro, Fanni Alessandra, Murari Andrea, Cannas Barbara, Rimini Fernanda, Pisano Gianluca, Sias Giuliana, JET Contributors, Baruzzo Matteo, Tsalas Maximos, Sparapani Paolo, de Vries Peter

Publikováno v: 27th IEEE Symposium on Fusion Engineering-SOFE 2017, Shanghai, China, June 4-8, 2017
info:cnr-pdr/source/autori:Pau Alessandro; Fanni Alessandra; Murari Andrea; Cannas Barbara; Rimini Fernanda; Pisano Gianluca; Sias Giuliana; JET Contributors; Baruzzo Matteo; Tsalas Maximos; Sparapani Paolo; de Vries Peter/congresso_nome:27th IEEE Symposium on Fusion Engineering-SOFE 2017/congresso_luogo:Shanghai, China/congresso_data:June 4-8, 2017/anno:2017/pagina_da:/pagina_a:/intervallo_pagine

Disruptive events still pose a serious problem for the protection of in-vessel components of large size tokamak devices, representing therefore a key aspect to be considered for the design of next step fusion devices such as ITER and DEMO. If an effi

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=cnr_________::4a2fe4dae1898070e527e775a2430c3e
https://publications.cnr.it/doc/375665