After 10 years of operation since its major modification, an upgrade of the RFX-mod experiment is presently under design. The scientific objective is the improvement of 3D physics studies through a more robust transition to higher confinement regimes in both Reversed Field Pinch (RFP) and Tokamak configuration obtained thanks to an advanced system for the active control of MHD instabilities. The main design driver requirements for this machine upgrade are the removal of the present resistive vacuum vessel and the enhancement of the 'shell-plasma proximity', to reduce the deformation of the last close magnetic surface and to improve the self-organized helical plasma regimes. The fulfillment of these requirements implies a major change of the internal components of the machine such as the replacement of the whole first wall, the change of the support system of the stabilizing shell and the modification of the present toroidal support structure to provide the function of vacuum barrier. In combination, other components of the machine will be upgraded, such as magnets and power supply, diagnostic systems and a NBI will be integrated. The paper presents an overview of the engineering design of the new components and highlights the critical aspects of the new torus assembly.

Design concepts of machine upgrades for the RFX-mod experiment

Agostini Matteo;Agostinetti Piero;Carraro Lorella;Dalla Palma Mauro;De Masi Gianluca;Grando Luca;Innocente Paolo;Marchiori Giuseppe;Marrelli Lionello;Puiatti Maria Ester;Scarin Paolo;Spolaore Monica;Valisa Marco;Vincenzi Pietro;
2017

Abstract

After 10 years of operation since its major modification, an upgrade of the RFX-mod experiment is presently under design. The scientific objective is the improvement of 3D physics studies through a more robust transition to higher confinement regimes in both Reversed Field Pinch (RFP) and Tokamak configuration obtained thanks to an advanced system for the active control of MHD instabilities. The main design driver requirements for this machine upgrade are the removal of the present resistive vacuum vessel and the enhancement of the 'shell-plasma proximity', to reduce the deformation of the last close magnetic surface and to improve the self-organized helical plasma regimes. The fulfillment of these requirements implies a major change of the internal components of the machine such as the replacement of the whole first wall, the change of the support system of the stabilizing shell and the modification of the present toroidal support structure to provide the function of vacuum barrier. In combination, other components of the machine will be upgraded, such as magnets and power supply, diagnostic systems and a NBI will be integrated. The paper presents an overview of the engineering design of the new components and highlights the critical aspects of the new torus assembly.
2017
Istituto gas ionizzati - IGI - Sede Padova
Inglese
123
59
62
4
https://www.sciencedirect.com/science/article/pii/S0920379617302788
Sì, ma tipo non specificato
Fusion devices
RFP configuration
Vacuum sealing
Ceramic-metal brazing
Electronic ISSN: 1873-7196 / https://biblioproxy.cnr.it:2562/S0920379617302788/1-s2.0-S0920379617302788-main.pdf?_tid=71738fa8-1714-11e8-898e-00000aab0f01&acdnat=1519223901_853ce197b5a08d01cb4d5d322cc7a18c
32
info:eu-repo/semantics/article
262
Peruzzo, Simone; Agostini, Matteo; Agostinetti, Piero; Bernardi, Marco; Bettini, Paolo; Bolzonella, Tommaso; Canton, Alessandra; Carraro, Lorella; Cav...espandi
01 Contributo su Rivista::01.01 Articolo in rivista
restricted
   Implementation of activities described in the Roadmap to Fusion during Horizon 2020 through a Joint programme of the members of the EUROfusion consortium
   EUROfusion
   H2020
   633053
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/348366
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