Valerio Tomarchio , Francesca Cau , José Lorenzo , María Mercedes Parody Guzmán , Damien Furfaro , Christine Hoa , Jacek Kosek , Qiu Lilong , Junjun Li , Alexandre Louzguiti , Thierry Schild , Ana Veleiro
{"title":"ITER环形场线圈在磁体冷试验台冷却过程中的热结构分析","authors":"Valerio Tomarchio , Francesca Cau , José Lorenzo , María Mercedes Parody Guzmán , Damien Furfaro , Christine Hoa , Jacek Kosek , Qiu Lilong , Junjun Li , Alexandre Louzguiti , Thierry Schild , Ana Veleiro","doi":"10.1016/j.fusengdes.2025.115017","DOIUrl":null,"url":null,"abstract":"<div><div>A Magnet Cold Test Bench is being built in ITER to test some of the Toroidal Field Coils (TFC) and the Poloidal Field Coil PF1, before they will be assembled and installed in the tokamak. The purpose is to test the performance of the superconducting magnet in cryogenic conditions and with current.</div><div>The TF coil and its structures weigh about 300 tons and will be cooled down from 300 K to 4.5 K, with helium flow supplied by one of the three refrigeration cold boxes of the ITER cryogenic system, with a capacity of 25 kW at 4 K. The helium flows in the winding packs of the coil, through the bundle and central channel of the superconducting cables, and it also extracts heat through the numerous cooling pipes of the Casing.</div><div>From 300 K to 100 K, one major concern is the thermal stresses due to the different thermal contraction coefficients of the materials in the coil and its structure: superconducting cables composed of Nb<sub>3</sub>Sn and Copper strands, Stainless Steel for the conductor jacket, the radial plates and the casing, electrical insulation materials such as Glass Kapton Glass and epoxy resin.</div><div>The usual cool down process requirement is to control the temperature difference between helium outlet and inlet and to ensure that it does not exceed 50 K. For the Magnet Cold Test Bench (MCTB), a selected cool down scenario was simulated to comply with the thermal hydraulic criteria and to check the resulting thermal stresses are acceptable for the coil, insulation material, structure and supports.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115017"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Thermal structural analyses during cool down of the ITER toroidal field coil in the magnet cold test bench\",\"authors\":\"Valerio Tomarchio , Francesca Cau , José Lorenzo , María Mercedes Parody Guzmán , Damien Furfaro , Christine Hoa , Jacek Kosek , Qiu Lilong , Junjun Li , Alexandre Louzguiti , Thierry Schild , Ana Veleiro\",\"doi\":\"10.1016/j.fusengdes.2025.115017\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>A Magnet Cold Test Bench is being built in ITER to test some of the Toroidal Field Coils (TFC) and the Poloidal Field Coil PF1, before they will be assembled and installed in the tokamak. The purpose is to test the performance of the superconducting magnet in cryogenic conditions and with current.</div><div>The TF coil and its structures weigh about 300 tons and will be cooled down from 300 K to 4.5 K, with helium flow supplied by one of the three refrigeration cold boxes of the ITER cryogenic system, with a capacity of 25 kW at 4 K. The helium flows in the winding packs of the coil, through the bundle and central channel of the superconducting cables, and it also extracts heat through the numerous cooling pipes of the Casing.</div><div>From 300 K to 100 K, one major concern is the thermal stresses due to the different thermal contraction coefficients of the materials in the coil and its structure: superconducting cables composed of Nb<sub>3</sub>Sn and Copper strands, Stainless Steel for the conductor jacket, the radial plates and the casing, electrical insulation materials such as Glass Kapton Glass and epoxy resin.</div><div>The usual cool down process requirement is to control the temperature difference between helium outlet and inlet and to ensure that it does not exceed 50 K. For the Magnet Cold Test Bench (MCTB), a selected cool down scenario was simulated to comply with the thermal hydraulic criteria and to check the resulting thermal stresses are acceptable for the coil, insulation material, structure and supports.</div></div>\",\"PeriodicalId\":55133,\"journal\":{\"name\":\"Fusion Engineering and Design\",\"volume\":\"216 \",\"pages\":\"Article 115017\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-04-11\",\"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/S0920379625002170\",\"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/S0920379625002170","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}
Thermal structural analyses during cool down of the ITER toroidal field coil in the magnet cold test bench
A Magnet Cold Test Bench is being built in ITER to test some of the Toroidal Field Coils (TFC) and the Poloidal Field Coil PF1, before they will be assembled and installed in the tokamak. The purpose is to test the performance of the superconducting magnet in cryogenic conditions and with current.
The TF coil and its structures weigh about 300 tons and will be cooled down from 300 K to 4.5 K, with helium flow supplied by one of the three refrigeration cold boxes of the ITER cryogenic system, with a capacity of 25 kW at 4 K. The helium flows in the winding packs of the coil, through the bundle and central channel of the superconducting cables, and it also extracts heat through the numerous cooling pipes of the Casing.
From 300 K to 100 K, one major concern is the thermal stresses due to the different thermal contraction coefficients of the materials in the coil and its structure: superconducting cables composed of Nb3Sn and Copper strands, Stainless Steel for the conductor jacket, the radial plates and the casing, electrical insulation materials such as Glass Kapton Glass and epoxy resin.
The usual cool down process requirement is to control the temperature difference between helium outlet and inlet and to ensure that it does not exceed 50 K. For the Magnet Cold Test Bench (MCTB), a selected cool down scenario was simulated to comply with the thermal hydraulic criteria and to check the resulting thermal stresses are acceptable for the coil, insulation material, structure and supports.
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.