Alfredo Pagliaro , Francesco Braghin , Alessandro Bruschi , Daniele Busi , Eliana De Marchi , Francesco Fanale , Gustavo Granucci , Afra Romano , Fabio Zanon
{"title":"DTT可操纵ECRH反射镜变深度互补螺旋冷却通道设计","authors":"Alfredo Pagliaro , Francesco Braghin , Alessandro Bruschi , Daniele Busi , Eliana De Marchi , Francesco Fanale , Gustavo Granucci , Afra Romano , Fabio Zanon","doi":"10.1016/j.fusengdes.2025.115276","DOIUrl":null,"url":null,"abstract":"<div><div>The steerable launching mirrors, essential for directing microwave beams into the plasma, play a pivotal role in the Electron Cyclotron Resonance Heating (ECRH) system for the Divertor Tokamak Test (DTT) facility, currently under construction in Frascati, Italy. Due to the substantial heat and electromagnetic induced loads acting on the mirrors, implementing internal channels for active water cooling, together with a proper choice of the materials, is necessary to keep temperature and deformation under control. Three different channel configurations are studied. First, the single-channel spiral cooling path with a constant cross-section, defined in a previous design stage, has been examined. Then, a constant-depth complementary spiral geometry that increases heat exchange area has been defined and analyzed. Finally, a variable-depth complementary spiral channel is proposed and optimized to increase heat exchange efficiency. In all cases, single-channel geometries are considered to enhance safety and malfunctioning detectability. The study is based on Computational Fluid Dynamics simulations. In order to reduce electromagnetic loads on the mirrors in case of plasma disruption to a tolerable extent, a reduced electrical conductivity of the mirror bulk material with respect to pure copper is necessary: this requires the use of material different than copper alloys, which have in turn a lower thermal conductivity. In this case, high cooling efficiency is mandatory. With this goal in mind, first, the performances of the different configurations in terms of mirror temperature and pressure drop are compared considering a reference material with 100 W/(m⋅K) thermal conductivity. Then, the variable-depth configuration is tested for different and more realistic mirror materials. Finally, a comparison between the developed geometry and previous solutions is provided.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115276"},"PeriodicalIF":1.9000,"publicationDate":"2025-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Variable-Depth Complementary Spiral cooling channel design for the steerable ECRH mirrors of DTT\",\"authors\":\"Alfredo Pagliaro , Francesco Braghin , Alessandro Bruschi , Daniele Busi , Eliana De Marchi , Francesco Fanale , Gustavo Granucci , Afra Romano , Fabio Zanon\",\"doi\":\"10.1016/j.fusengdes.2025.115276\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The steerable launching mirrors, essential for directing microwave beams into the plasma, play a pivotal role in the Electron Cyclotron Resonance Heating (ECRH) system for the Divertor Tokamak Test (DTT) facility, currently under construction in Frascati, Italy. Due to the substantial heat and electromagnetic induced loads acting on the mirrors, implementing internal channels for active water cooling, together with a proper choice of the materials, is necessary to keep temperature and deformation under control. Three different channel configurations are studied. First, the single-channel spiral cooling path with a constant cross-section, defined in a previous design stage, has been examined. Then, a constant-depth complementary spiral geometry that increases heat exchange area has been defined and analyzed. Finally, a variable-depth complementary spiral channel is proposed and optimized to increase heat exchange efficiency. In all cases, single-channel geometries are considered to enhance safety and malfunctioning detectability. The study is based on Computational Fluid Dynamics simulations. In order to reduce electromagnetic loads on the mirrors in case of plasma disruption to a tolerable extent, a reduced electrical conductivity of the mirror bulk material with respect to pure copper is necessary: this requires the use of material different than copper alloys, which have in turn a lower thermal conductivity. In this case, high cooling efficiency is mandatory. With this goal in mind, first, the performances of the different configurations in terms of mirror temperature and pressure drop are compared considering a reference material with 100 W/(m⋅K) thermal conductivity. Then, the variable-depth configuration is tested for different and more realistic mirror materials. Finally, a comparison between the developed geometry and previous solutions is provided.</div></div>\",\"PeriodicalId\":55133,\"journal\":{\"name\":\"Fusion Engineering and Design\",\"volume\":\"219 \",\"pages\":\"Article 115276\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-06-26\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Fusion Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0920379625004727\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625004727","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Variable-Depth Complementary Spiral cooling channel design for the steerable ECRH mirrors of DTT
The steerable launching mirrors, essential for directing microwave beams into the plasma, play a pivotal role in the Electron Cyclotron Resonance Heating (ECRH) system for the Divertor Tokamak Test (DTT) facility, currently under construction in Frascati, Italy. Due to the substantial heat and electromagnetic induced loads acting on the mirrors, implementing internal channels for active water cooling, together with a proper choice of the materials, is necessary to keep temperature and deformation under control. Three different channel configurations are studied. First, the single-channel spiral cooling path with a constant cross-section, defined in a previous design stage, has been examined. Then, a constant-depth complementary spiral geometry that increases heat exchange area has been defined and analyzed. Finally, a variable-depth complementary spiral channel is proposed and optimized to increase heat exchange efficiency. In all cases, single-channel geometries are considered to enhance safety and malfunctioning detectability. The study is based on Computational Fluid Dynamics simulations. In order to reduce electromagnetic loads on the mirrors in case of plasma disruption to a tolerable extent, a reduced electrical conductivity of the mirror bulk material with respect to pure copper is necessary: this requires the use of material different than copper alloys, which have in turn a lower thermal conductivity. In this case, high cooling efficiency is mandatory. With this goal in mind, first, the performances of the different configurations in terms of mirror temperature and pressure drop are compared considering a reference material with 100 W/(m⋅K) thermal conductivity. Then, the variable-depth configuration is tested for different and more realistic mirror materials. Finally, a comparison between the developed geometry and previous solutions is provided.
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.