{"title":"Alcator C-MOD的启动和早期结果","authors":"S. Fairfax","doi":"10.1109/FUSION.1993.518449","DOIUrl":null,"url":null,"abstract":"Alcator C-MOD is a compact, high performance tokamak designed to address reactor-relevant issues including diverter operation, confinement, and auxiliary heating. It incorporates flexible shaping of non-circular, diverted plasmas, strong ICRF heating, and many innovative engineering features to achieve high performance in a compact device with modest cost. Like its predecessors, Alcator A and Alcator C, Alcator C-MOD uses cryogenically cooled copper magnets to produce high toroidal fields (9 Tesla at 0.67 m) and strong ohmic heating (up to 3 MA.) The thick wall of the vacuum vessel, while complicating the normal problems of plasma initiation and control, are relevant to virtually all next-generation designs. The facility operated briefly in late 1991 and again in early 1992, when a terminal failed on one of the PF magnets. The experiment resumed operations in May 1993. This report describes the start-up and early operational experience, comparing with both design scenarios and previous experience on Alcator A and C. Results from operations during the summer of 1993 are presented.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":"19 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"2","resultStr":"{\"title\":\"Start-up and early results from Alcator C-MOD\",\"authors\":\"S. Fairfax\",\"doi\":\"10.1109/FUSION.1993.518449\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"Alcator C-MOD is a compact, high performance tokamak designed to address reactor-relevant issues including diverter operation, confinement, and auxiliary heating. It incorporates flexible shaping of non-circular, diverted plasmas, strong ICRF heating, and many innovative engineering features to achieve high performance in a compact device with modest cost. Like its predecessors, Alcator A and Alcator C, Alcator C-MOD uses cryogenically cooled copper magnets to produce high toroidal fields (9 Tesla at 0.67 m) and strong ohmic heating (up to 3 MA.) The thick wall of the vacuum vessel, while complicating the normal problems of plasma initiation and control, are relevant to virtually all next-generation designs. The facility operated briefly in late 1991 and again in early 1992, when a terminal failed on one of the PF magnets. The experiment resumed operations in May 1993. This report describes the start-up and early operational experience, comparing with both design scenarios and previous experience on Alcator A and C. Results from operations during the summer of 1993 are presented.\",\"PeriodicalId\":365814,\"journal\":{\"name\":\"15th IEEE/NPSS Symposium. Fusion Engineering\",\"volume\":\"19 1\",\"pages\":\"0\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"1993-10-11\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"2\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"15th IEEE/NPSS Symposium. Fusion Engineering\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.1109/FUSION.1993.518449\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"15th IEEE/NPSS Symposium. Fusion Engineering","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1109/FUSION.1993.518449","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
Alcator C-MOD is a compact, high performance tokamak designed to address reactor-relevant issues including diverter operation, confinement, and auxiliary heating. It incorporates flexible shaping of non-circular, diverted plasmas, strong ICRF heating, and many innovative engineering features to achieve high performance in a compact device with modest cost. Like its predecessors, Alcator A and Alcator C, Alcator C-MOD uses cryogenically cooled copper magnets to produce high toroidal fields (9 Tesla at 0.67 m) and strong ohmic heating (up to 3 MA.) The thick wall of the vacuum vessel, while complicating the normal problems of plasma initiation and control, are relevant to virtually all next-generation designs. The facility operated briefly in late 1991 and again in early 1992, when a terminal failed on one of the PF magnets. The experiment resumed operations in May 1993. This report describes the start-up and early operational experience, comparing with both design scenarios and previous experience on Alcator A and C. Results from operations during the summer of 1993 are presented.