Preliminary thermo-structural analyses of the new DTT bolometric camera

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
V. D'Agostino , A. Belpane , S. Palomba , E. Peluso , I. Wyss , B. Spolaore , I. Regoli , L. Gabellieri , A. Murari , G. Apruzzese , M. Gelfusa
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引用次数: 0

Abstract

The Divertor Tokamak Test (DTT) facility is currently under construction at the ENEA Frascati Research Centre, Italy, with the aim of studying divertor configurations in support to the design and construction of ITER and DEMO. In the context of monitoring the radiated power, it is crucial to measure the entire spectrum of electromagnetic radiation emitted by the plasma. This need is particularly relevant in the divertor region, especially in the specific case of DTT scientific programme. This work presents the preliminary thermal and structural analyses of the bolometric camera foreseen to be implemented in the tomographic diagnostic system, aimed at monitoring the emissivity of the plasma total radiated power. First, the design has been optimised, minimising the space occupied in the port by the arrays of metal foil bolometers, still ensuring the best possible coverage of the lines of sight (LoS) in the vessel and at the same time avoiding interferences with other devices. Then, the devised layout has been validated with thermo-mechanical simulations, focusing on the design of the active cooling system of the bolometers themselves, necessary to manage the thermal conditions of the wall, particularly baking, and the intense loads during machine operations. The results confirmed that, under the specific conditions of mirror polishing of components, the currently proposed layout is promising, but needs further optimisation.
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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