{"title":"ITER给料器高温超导引线的电子束焊接","authors":"Jianguo Ma;Jia Tao;Zhenfei Liu;Chen Liu;Liming Peng;Wei Wen;Le Yang;Xiaowei Xia;Jiefeng Wu;Rui Wang;Zhihong Liu","doi":"10.1109/TPS.2024.3495636","DOIUrl":null,"url":null,"abstract":"The high-temperature superconducting (HTS) current lead is one of the core components of the International Thermonuclear Experimental Reactor (ITER) magnet feeder system. Due to high-quality requirements, electron beam welding (EBW) was chosen to weld the room temperature terminal, the finned heat exchanger, and the HTS segment. The short mock-up was created to assess the performance of the welded joints. The analysis of macroscopic morphology and microstructure indicates that the welded joint of the short mock-up appeared to be free of visible defects. The tensile strength of the welded samples ranges from 185 to 208 MPa, which is higher than the design requirement of 150 MPa. The side bending test also shows no open discontinuity of the samples. Additionally, the thermal shock test was carried out. The dye penetrant test and the ultrasonic test after thermal shock shows that there are no obvious defects inside or on the surface of the weld seam. Furthermore, the leakage rate of the welded sample measured in the helium tightness leak test was <inline-formula> <tex-math>$2.2\\times 10^{-10}$ </tex-math></inline-formula>Pa<inline-formula> <tex-math>$\\cdot $ </tex-math></inline-formula>m3/s, indicating no cracks detected in the joints in the joints. The same parameters were also used for the welding of the long mock-up equipped with fins. The maximum temperature during the welding process does not go over the prescribed limit. The actual HTS current lead was welded, and its performance was evaluated, based on the welding experiments of mock-ups. The welding quality of the HTS current lead was confirmed by all test results.","PeriodicalId":450,"journal":{"name":"IEEE Transactions on Plasma Science","volume":"52 11","pages":"5451-5456"},"PeriodicalIF":1.3000,"publicationDate":"2024-12-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Electron Beam Welding of the HTS Current Lead for the ITER Feeder\",\"authors\":\"Jianguo Ma;Jia Tao;Zhenfei Liu;Chen Liu;Liming Peng;Wei Wen;Le Yang;Xiaowei Xia;Jiefeng Wu;Rui Wang;Zhihong Liu\",\"doi\":\"10.1109/TPS.2024.3495636\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"The high-temperature superconducting (HTS) current lead is one of the core components of the International Thermonuclear Experimental Reactor (ITER) magnet feeder system. Due to high-quality requirements, electron beam welding (EBW) was chosen to weld the room temperature terminal, the finned heat exchanger, and the HTS segment. The short mock-up was created to assess the performance of the welded joints. The analysis of macroscopic morphology and microstructure indicates that the welded joint of the short mock-up appeared to be free of visible defects. The tensile strength of the welded samples ranges from 185 to 208 MPa, which is higher than the design requirement of 150 MPa. The side bending test also shows no open discontinuity of the samples. Additionally, the thermal shock test was carried out. The dye penetrant test and the ultrasonic test after thermal shock shows that there are no obvious defects inside or on the surface of the weld seam. Furthermore, the leakage rate of the welded sample measured in the helium tightness leak test was <inline-formula> <tex-math>$2.2\\\\times 10^{-10}$ </tex-math></inline-formula>Pa<inline-formula> <tex-math>$\\\\cdot $ </tex-math></inline-formula>m3/s, indicating no cracks detected in the joints in the joints. The same parameters were also used for the welding of the long mock-up equipped with fins. The maximum temperature during the welding process does not go over the prescribed limit. The actual HTS current lead was welded, and its performance was evaluated, based on the welding experiments of mock-ups. The welding quality of the HTS current lead was confirmed by all test results.\",\"PeriodicalId\":450,\"journal\":{\"name\":\"IEEE Transactions on Plasma Science\",\"volume\":\"52 11\",\"pages\":\"5451-5456\"},\"PeriodicalIF\":1.3000,\"publicationDate\":\"2024-12-09\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"IEEE Transactions on Plasma Science\",\"FirstCategoryId\":\"101\",\"ListUrlMain\":\"https://ieeexplore.ieee.org/document/10785565/\",\"RegionNum\":4,\"RegionCategory\":\"物理与天体物理\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q3\",\"JCRName\":\"PHYSICS, FLUIDS & PLASMAS\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"IEEE Transactions on Plasma Science","FirstCategoryId":"101","ListUrlMain":"https://ieeexplore.ieee.org/document/10785565/","RegionNum":4,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"PHYSICS, FLUIDS & PLASMAS","Score":null,"Total":0}
引用次数: 0
摘要
高温超导引线是国际热核实验反应堆(ITER)磁体给料系统的核心部件之一。出于对高质量的要求,选择了电子束焊接(EBW)来焊接室温端子、翅片式换热器和HTS段。创建了一个简短的模型来评估焊接接头的性能。宏观形貌和显微组织分析表明,短模型的焊接接头没有明显的缺陷。焊接试样的抗拉强度为185 ~ 208 MPa,高于设计要求的150 MPa。侧弯试验也显示样品没有开放的不连续。此外,还进行了热冲击试验。热冲击后的染料渗透试验和超声波试验表明,焊缝内部和表面均无明显缺陷。在氦密泄漏试验中,焊接试样的泄漏率为$2.2\乘以10^{-10}$ Pa $\cdot $ m3/s,表明接头中未检测到裂纹。同样的参数也用于焊接长模型配备翼片。焊接过程中的最高温度不超过规定的极限。在实物焊接实验的基础上,对实际的高温超导电流引线进行了焊接,并对其性能进行了评价。所有试验结果均证实了HTS电流引线的焊接质量。
Electron Beam Welding of the HTS Current Lead for the ITER Feeder
The high-temperature superconducting (HTS) current lead is one of the core components of the International Thermonuclear Experimental Reactor (ITER) magnet feeder system. Due to high-quality requirements, electron beam welding (EBW) was chosen to weld the room temperature terminal, the finned heat exchanger, and the HTS segment. The short mock-up was created to assess the performance of the welded joints. The analysis of macroscopic morphology and microstructure indicates that the welded joint of the short mock-up appeared to be free of visible defects. The tensile strength of the welded samples ranges from 185 to 208 MPa, which is higher than the design requirement of 150 MPa. The side bending test also shows no open discontinuity of the samples. Additionally, the thermal shock test was carried out. The dye penetrant test and the ultrasonic test after thermal shock shows that there are no obvious defects inside or on the surface of the weld seam. Furthermore, the leakage rate of the welded sample measured in the helium tightness leak test was $2.2\times 10^{-10}$ Pa$\cdot $ m3/s, indicating no cracks detected in the joints in the joints. The same parameters were also used for the welding of the long mock-up equipped with fins. The maximum temperature during the welding process does not go over the prescribed limit. The actual HTS current lead was welded, and its performance was evaluated, based on the welding experiments of mock-ups. The welding quality of the HTS current lead was confirmed by all test results.
期刊介绍:
The scope covers all aspects of the theory and application of plasma science. It includes the following areas: magnetohydrodynamics; thermionics and plasma diodes; basic plasma phenomena; gaseous electronics; microwave/plasma interaction; electron, ion, and plasma sources; space plasmas; intense electron and ion beams; laser-plasma interactions; plasma diagnostics; plasma chemistry and processing; solid-state plasmas; plasma heating; plasma for controlled fusion research; high energy density plasmas; industrial/commercial applications of plasma physics; plasma waves and instabilities; and high power microwave and submillimeter wave generation.