{"title":"Controlled central fueling for ARIES-III by compact-toroid injection","authors":"S. K. Ho","doi":"10.1109/FUSION.1991.218916","DOIUrl":null,"url":null,"abstract":"An alternative fueling scheme for ARIES-III using accelerated compact-toroids (CT) is studied. The methodology of L.J. Perkins et al. (1988) for modeling CT penetration and deposition is followed. The calculations are performed using a self-consistent, radial-zoning scheme which includes several interrelated constraints such as CT ring decay, tilting, field-line reconnection, deceleration in the external field gradient, and ring expansion/contraction. The CT injection parameters optimized for fueling of ARIES-III are presented. Advantages of CT fueling with respect to other aspects of tokamak operations and uncertainties in the CT injection modeling are also discussed. From the conservative upper-limit estimation, CTs of 40 mg with 40 cm diameter can deposit fuel directly into the center and half-way of the plasma, requiring 49 MW and 14 MW, respectively.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"142 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.1991.218916","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 1
Abstract
An alternative fueling scheme for ARIES-III using accelerated compact-toroids (CT) is studied. The methodology of L.J. Perkins et al. (1988) for modeling CT penetration and deposition is followed. The calculations are performed using a self-consistent, radial-zoning scheme which includes several interrelated constraints such as CT ring decay, tilting, field-line reconnection, deceleration in the external field gradient, and ring expansion/contraction. The CT injection parameters optimized for fueling of ARIES-III are presented. Advantages of CT fueling with respect to other aspects of tokamak operations and uncertainties in the CT injection modeling are also discussed. From the conservative upper-limit estimation, CTs of 40 mg with 40 cm diameter can deposit fuel directly into the center and half-way of the plasma, requiring 49 MW and 14 MW, respectively.<>