This article describes the solutions investigated for the design of the support and fixation systems of the first wall (FW) to the vacuum vessel (VV) at both inboard and outboard sides, in order to define their engineering design in compliance with the other involved systems of the divertor tokamak test (DTT) facility: VV, diagnostics, remote handling (RH), and plasma physics. The aim is to engineer them to cope with the electromagnetic (EM) loads resulting from disruption events (VDE and MD) or from discharges occurring in the coils (i.e., toroidal field coils fast discharge).

Status of Design of the First Wall Supports of the Divertor Tokamak Test Facility

De Luca R.;Roccella S.;
2024-01-01

Abstract

This article describes the solutions investigated for the design of the support and fixation systems of the first wall (FW) to the vacuum vessel (VV) at both inboard and outboard sides, in order to define their engineering design in compliance with the other involved systems of the divertor tokamak test (DTT) facility: VV, diagnostics, remote handling (RH), and plasma physics. The aim is to engineer them to cope with the electromagnetic (EM) loads resulting from disruption events (VDE and MD) or from discharges occurring in the coils (i.e., toroidal field coils fast discharge).
2024
Disruptions
divertor tokamak test facility (DTT)
first wall (FW)
plasma-facing components
support
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/84390
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