Source for the production of ions of deuterium extracted from a radio frequency plasma (SPIDER) is a full-size negative ion source and a multibeamlet 100-kV accelerator, operational since 2018. It serves as the test bed for the full development of the heating neutral beam system for megavolt ITER injector and concept advancement (ITER). In 2020, the third grounded grid segment broke at the electrodeposited copper layer near one of the four feeders causing leakage. This article reports the redesign development of the SPIDER GG segment. In the first part of the article, several design configurations are proposed and compared to each other. The comparison serves to identify a suitable redesign configuration. A set of coupled analyses, including computational fluid dynamic (CFD) and finite-element method (FEM) analyses, is then performed to finally evaluate the redesigned component in accordance with the ITER structural design criteria for in-vessel components (ITER SDC-IC) criteria.

Optimization of Spider Grounded Grid Segment Design

Zaccaria P;Agostinetti P;
2022

Abstract

Source for the production of ions of deuterium extracted from a radio frequency plasma (SPIDER) is a full-size negative ion source and a multibeamlet 100-kV accelerator, operational since 2018. It serves as the test bed for the full development of the heating neutral beam system for megavolt ITER injector and concept advancement (ITER). In 2020, the third grounded grid segment broke at the electrodeposited copper layer near one of the four feeders causing leakage. This article reports the redesign development of the SPIDER GG segment. In the first part of the article, several design configurations are proposed and compared to each other. The comparison serves to identify a suitable redesign configuration. A set of coupled analyses, including computational fluid dynamic (CFD) and finite-element method (FEM) analyses, is then performed to finally evaluate the redesigned component in accordance with the ITER structural design criteria for in-vessel components (ITER SDC-IC) criteria.
2022
Istituto per la Scienza e Tecnologia dei Plasmi - ISTP
Inglese
50
11
3952
3958
7
https://ieeexplore.ieee.org/document/9777869
Sì, ma tipo non specificato
Computational fluid dynamics (CFDs)
finite- element method (FEM)
Neutral Beam Test Facility (NBTF)
neutral beam injector
source for the production of ions of deuterium extracted from a radio frequency plasma (SPIDER)
Electronic ISSN: 1939-9375, http://www.scopus.com/inward/record.url?eid=2-s2.0-85130438052&partnerID=q2rCbXpz - This work has been carried out within the framework of the megavolt ITER injector and concept advancement (ITER)-RFX Neutral Beam Testing Facility (NBTF) Agreement and has received funding from the ITER Organization. This work has been carried out within the framework of the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No. 101052200--EUROfusion).
2
info:eu-repo/semantics/article
262
Tomsic P.; Berton G.; Zaccaria P.; Agostinetti P.; Pavei M.; Marcuzzi D.
01 Contributo su Rivista::01.01 Articolo in rivista
none
   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/20.500.14243/432408
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