D.K. Sharma , J. Joshi , S. Pillai , U. Dethe , K. Joshi , D. Parmar , H. Shishangiya , S. Shah , A. Jha , M.J. Singh , A.K. Chakraborty
{"title":"用于 INTF ITER DNB 原型的瓷基 100kV 贯穿件","authors":"D.K. Sharma , J. Joshi , S. Pillai , U. Dethe , K. Joshi , D. Parmar , H. Shishangiya , S. Shah , A. Jha , M.J. Singh , A.K. Chakraborty","doi":"10.1016/j.fusengdes.2024.114609","DOIUrl":null,"url":null,"abstract":"<div><p>High Voltage Bushing (HVB) of the Indian Test Facility (INTF) of ITER Diagnostic Neutral Beam (DNB) is a porcelain-based 100 kV vacuum feedthrough. This will be used to feed the High Voltage (HV) supplies, coming from the HV deck to the Beam Source (BS) for the production of 100 kV H<sup>-</sup> beam under high vacuum, therefore, it has two major functions: 1. Isolate 100 kV feedlines from grounded vessel and 2. Forms vacuum boundary with 25 feedline penetrations of different kinds. INTF HVB has been designed with rigorous iterations of design optimization for vacuum, mechanical, and electrical requirements. After design, the development of INTF HVB required several prototyping activities to address the challenges in establishing the appropriate bonding methodology with high vacuum compatibility, handling procedure of large size (∼800 mm diameter and 530 mm height) insulator, prior assessments of tolerances due to as-built ovality in insulator and testing & qualification at various steps, to establish the implementation plan for manufacturing and assembly. As a result, techniques, based on prototyping, manifest to solve the challenges were utilized in the manufacturing, leading to the successful development of the HVB.</p></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-07-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Porcelain based 100kV feedthrough for prototype ITER DNB at INTF\",\"authors\":\"D.K. Sharma , J. Joshi , S. Pillai , U. Dethe , K. Joshi , D. Parmar , H. Shishangiya , S. Shah , A. Jha , M.J. Singh , A.K. Chakraborty\",\"doi\":\"10.1016/j.fusengdes.2024.114609\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>High Voltage Bushing (HVB) of the Indian Test Facility (INTF) of ITER Diagnostic Neutral Beam (DNB) is a porcelain-based 100 kV vacuum feedthrough. This will be used to feed the High Voltage (HV) supplies, coming from the HV deck to the Beam Source (BS) for the production of 100 kV H<sup>-</sup> beam under high vacuum, therefore, it has two major functions: 1. Isolate 100 kV feedlines from grounded vessel and 2. Forms vacuum boundary with 25 feedline penetrations of different kinds. INTF HVB has been designed with rigorous iterations of design optimization for vacuum, mechanical, and electrical requirements. After design, the development of INTF HVB required several prototyping activities to address the challenges in establishing the appropriate bonding methodology with high vacuum compatibility, handling procedure of large size (∼800 mm diameter and 530 mm height) insulator, prior assessments of tolerances due to as-built ovality in insulator and testing & qualification at various steps, to establish the implementation plan for manufacturing and assembly. As a result, techniques, based on prototyping, manifest to solve the challenges were utilized in the manufacturing, leading to the successful development of the HVB.</p></div>\",\"PeriodicalId\":55133,\"journal\":{\"name\":\"Fusion Engineering and Design\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2024-07-30\",\"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/S0920379624004605\",\"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/S0920379624004605","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}
Porcelain based 100kV feedthrough for prototype ITER DNB at INTF
High Voltage Bushing (HVB) of the Indian Test Facility (INTF) of ITER Diagnostic Neutral Beam (DNB) is a porcelain-based 100 kV vacuum feedthrough. This will be used to feed the High Voltage (HV) supplies, coming from the HV deck to the Beam Source (BS) for the production of 100 kV H- beam under high vacuum, therefore, it has two major functions: 1. Isolate 100 kV feedlines from grounded vessel and 2. Forms vacuum boundary with 25 feedline penetrations of different kinds. INTF HVB has been designed with rigorous iterations of design optimization for vacuum, mechanical, and electrical requirements. After design, the development of INTF HVB required several prototyping activities to address the challenges in establishing the appropriate bonding methodology with high vacuum compatibility, handling procedure of large size (∼800 mm diameter and 530 mm height) insulator, prior assessments of tolerances due to as-built ovality in insulator and testing & qualification at various steps, to establish the implementation plan for manufacturing and assembly. As a result, techniques, based on prototyping, manifest to solve the challenges were utilized in the manufacturing, leading to the successful development of the HVB.
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.