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

M. Furno Palumbo; M. Dalla Palma; R. De Luca; G. De Sano; G. Dose; F. Giorgetti; G. M. Polli; B. Riccardi; S. Roccella; R. Neu

doi:10.1109/TPS.2024.3378386

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

M. Furno Palumbo, M. Dalla Palma, R. De Luca, G. De Sano, G. Dose, F. Giorgetti, G. M. Polli, B. Riccardi, S. Roccella, R. Neu

Research output: Contribution to journal › Article › peer-review

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).

Original language	English
Pages (from-to)	1-0
Number of pages	2
Journal	IEEE Transactions on Plasma Science
DOIs	https://doi.org/10.1109/TPS.2024.3378386
State	Accepted/In press - 2024
Externally published	Yes

Keywords

Disruptions
Fasteners
Iron
Load modeling
Plasmas
Stress
Tokamak devices
Welding
divertor tokamak test facility (DTT)
first wall (FW)
plasma-facing components
support

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10.1109/TPS.2024.3378386

Cite this

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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).",

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AU - Palumbo, M. Furno

AU - Palma, M. Dalla

AU - Luca, R. De

AU - Sano, G. De

AU - Dose, G.

AU - Giorgetti, F.

AU - Polli, G. M.

AU - Riccardi, B.

AU - Roccella, S.

AU - Neu, R.

N1 - Publisher Copyright: IEEE

PY - 2024

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N2 - 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).

AB - 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).

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KW - Fasteners

KW - Iron

KW - Load modeling

KW - Plasmas

KW - Stress

KW - Tokamak devices

KW - Welding

KW - divertor tokamak test facility (DTT)

KW - first wall (FW)

KW - plasma-facing components

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

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Keywords

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