{"title":"DIII-D的最新结果和未来计划","authors":"T. Simonen","doi":"10.1109/FUSION.1991.218686","DOIUrl":null,"url":null,"abstract":"Recent DIII-D tokamak experimental results are summarized, new hardware being implemented to carry out the DIII-D 1990s tokamak research program is described, and their implications for engineering designs for next-generation tokamaks, such as ITER (International Thermonuclear Experimental Reactor), are discussed. DIII-D is presently investigating several new and alternative methods to address key ITER design issues: divertor, disruption, and current profile control. DIII-D is also demonstrating improved tokamak performance regimes such as high beta second stability and high confinement such as VH-mode. On a more basic and broader research front, DIII-D is exploring innovative tokamak engineering and physics concepts, solidifying fundamental plasma physics understanding, and demonstrating essential engineering technologies with the goal of developing a safe and environmentally and commercially attractive fusion reactor concept.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"72 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"1","resultStr":"{\"title\":\"Recent results from DIII-D and future plans\",\"authors\":\"T. Simonen\",\"doi\":\"10.1109/FUSION.1991.218686\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"Recent DIII-D tokamak experimental results are summarized, new hardware being implemented to carry out the DIII-D 1990s tokamak research program is described, and their implications for engineering designs for next-generation tokamaks, such as ITER (International Thermonuclear Experimental Reactor), are discussed. DIII-D is presently investigating several new and alternative methods to address key ITER design issues: divertor, disruption, and current profile control. DIII-D is also demonstrating improved tokamak performance regimes such as high beta second stability and high confinement such as VH-mode. On a more basic and broader research front, DIII-D is exploring innovative tokamak engineering and physics concepts, solidifying fundamental plasma physics understanding, and demonstrating essential engineering technologies with the goal of developing a safe and environmentally and commercially attractive fusion reactor concept.<<ETX>>\",\"PeriodicalId\":318951,\"journal\":{\"name\":\"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering\",\"volume\":\"72 1\",\"pages\":\"0\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"1991-09-30\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"1\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.1109/FUSION.1991.218686\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1109/FUSION.1991.218686","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
Recent DIII-D tokamak experimental results are summarized, new hardware being implemented to carry out the DIII-D 1990s tokamak research program is described, and their implications for engineering designs for next-generation tokamaks, such as ITER (International Thermonuclear Experimental Reactor), are discussed. DIII-D is presently investigating several new and alternative methods to address key ITER design issues: divertor, disruption, and current profile control. DIII-D is also demonstrating improved tokamak performance regimes such as high beta second stability and high confinement such as VH-mode. On a more basic and broader research front, DIII-D is exploring innovative tokamak engineering and physics concepts, solidifying fundamental plasma physics understanding, and demonstrating essential engineering technologies with the goal of developing a safe and environmentally and commercially attractive fusion reactor concept.<>
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