Plasma Position Reflectometry (PPR) is taking an important role in next-generation fusion machines, such as DEMO, as a diagnostic to monitor the position and shape of the plasma, complementing magnetic diagnostics. The Divertor Test Tokamak (DTT) facility is the perfect machine to implement, develop, and test PPR systems. Important work is being done to evaluate the performance of a tentative PPR system in DTT, including assessment efforts integrated into the EUROfusion Enabling Research Project (ENR-TEC.01.IST). These efforts involve designing two- and three-dimensional synthetic diagnostics for the Low (LFS) and High Field Sides (HFS), using Finite-Difference Time-Domain codes. This simulation assessment works in parallel with the design of antennas for the LFS and HFS. Their integration in synthetic diagnostics is done through a CAD conversion pipeline. An overview of the progress achieved, together with future work planned, is provided in the present work devoted to the accuracy of the separatrix localisation at different positions around the vessel.

Overview of the studies towards a Plasma Position Reflectometry system for Divertor Test Tokamak (DTT)

Tudisco, O.
2025-01-01

Abstract

Plasma Position Reflectometry (PPR) is taking an important role in next-generation fusion machines, such as DEMO, as a diagnostic to monitor the position and shape of the plasma, complementing magnetic diagnostics. The Divertor Test Tokamak (DTT) facility is the perfect machine to implement, develop, and test PPR systems. Important work is being done to evaluate the performance of a tentative PPR system in DTT, including assessment efforts integrated into the EUROfusion Enabling Research Project (ENR-TEC.01.IST). These efforts involve designing two- and three-dimensional synthetic diagnostics for the Low (LFS) and High Field Sides (HFS), using Finite-Difference Time-Domain codes. This simulation assessment works in parallel with the design of antennas for the LFS and HFS. Their integration in synthetic diagnostics is done through a CAD conversion pipeline. An overview of the progress achieved, together with future work planned, is provided in the present work devoted to the accuracy of the separatrix localisation at different positions around the vessel.
2025
Nuclear instruments and methods for hot plasma diagnostics
Simulation methods and programs
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/87787
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