Several hundreds of magnetic sensors will be located within the ITER vacuum vessel, in a hostile environment characterized by severe neutron irradiation and plasma heat loads that represent a concern for the reliability and durability of the sensors. The in-vessel magnetic sensors are therefore conceived to be attached to the inner surface of the vacuum vessel through a connection system which allows a potential replacement by means of a suitable Remote Handling (RH) system. This paper presents the preliminary design of the "In-Vessel Magnetic platform", which represents a subsystem of the magnetic diagnostics formed by all the components necessary for guaranteeing the thermo-mechanical interface of the actual magnetic sensors with the vacuum vessel, their protection and the electrical connection to the in-vessel wiring for the transmission of the detected signal with a minimum level of noise. The design has been developed in order to comply with several functional requirements: the mechanical attachment to vacuum vessel; the electrical connection to the in-vessel wiring; an efficient heat transfer to vacuum vessel; the installation and replacement by means of RH system; the housing of metrology features for post-installation control; the ECH radiation shielding. Significant effort has been dedicated to investigate and develop a proper CAD model, integrated within the ITER In-Vessel configuration model, caring for the geometrical compliance with the Blanket modules (modified in order to accommodate the magnetic sensors in suitable grooves) and the RH compatibility. Thorough thermo-mechanical and electro-magnetic fem analyses have been performed to demonstrate the reliability of the system in standard and off-normal operating conditions.

Electro-Mechanical Connection System for ITER In-vessel Magnetic Sensors

Brombin Matteo;
2015

Abstract

Several hundreds of magnetic sensors will be located within the ITER vacuum vessel, in a hostile environment characterized by severe neutron irradiation and plasma heat loads that represent a concern for the reliability and durability of the sensors. The in-vessel magnetic sensors are therefore conceived to be attached to the inner surface of the vacuum vessel through a connection system which allows a potential replacement by means of a suitable Remote Handling (RH) system. This paper presents the preliminary design of the "In-Vessel Magnetic platform", which represents a subsystem of the magnetic diagnostics formed by all the components necessary for guaranteeing the thermo-mechanical interface of the actual magnetic sensors with the vacuum vessel, their protection and the electrical connection to the in-vessel wiring for the transmission of the detected signal with a minimum level of noise. The design has been developed in order to comply with several functional requirements: the mechanical attachment to vacuum vessel; the electrical connection to the in-vessel wiring; an efficient heat transfer to vacuum vessel; the installation and replacement by means of RH system; the housing of metrology features for post-installation control; the ECH radiation shielding. Significant effort has been dedicated to investigate and develop a proper CAD model, integrated within the ITER In-Vessel configuration model, caring for the geometrical compliance with the Blanket modules (modified in order to accommodate the magnetic sensors in suitable grooves) and the RH compatibility. Thorough thermo-mechanical and electro-magnetic fem analyses have been performed to demonstrate the reliability of the system in standard and off-normal operating conditions.
2015
Istituto gas ionizzati - IGI - Sede Padova
Inglese
ISFNT-12 International Symposium on Fusion Nuclear Technology
http://www.isfnt-12.org/downfile/programbook.pdf
September 14 - 18, 2015
Jeju Island, Korea
Electrical connection
Magnetic diagnostics
Remote maintenance
P1.184; http://www.isfnt-12.org/sub01
none
info:eu-repo/semantics/conferenceObject
Rizzolo Andrea; Brombin Matteo; Gonzalez Winder; Marconato Nicolò; Peruzzo Simone; Arshad Shakeib; Ma Yunxing; Vayakis George
275
04 Contributo in convegno::04.03 Poster in Atti di convegno
1
   EU Fusion for ITER Applications
   EUFORIA
   FP7
   211804
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/304417
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