{"title":"超级线圈:托卡马克计算设计模型","authors":"K. Borrass, M. Söll","doi":"10.1016/0167-899X(86)90009-1","DOIUrl":null,"url":null,"abstract":"<div><p>SUPERCOIL is a code for the computational design of tokamaks, including in particular ignited next-generation devices. It takes into account all physical, technical and geometrical constraints relevant to the basic design of a tokamak. Among the solutions of the model equations that meet all constraints the one optimized with respect to a prescribed figure of merit (typically capital cost) is determined. The main components modelled are the plasma, blanket and shield, the TF system and the PF system. The main characteristics of the component models are summarized and a detailed description of the solution method is given. A typical NET study point is given as an illustrative example. The validity of the code is assessed by applying it to the ASDEX Upgrade tokamak.</p></div>","PeriodicalId":82205,"journal":{"name":"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy","volume":"4 1","pages":"Pages 21-35"},"PeriodicalIF":0.0000,"publicationDate":"1986-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0167-899X(86)90009-1","citationCount":"7","resultStr":"{\"title\":\"Supercoil: A model for the computational design of tokamaks\",\"authors\":\"K. Borrass, M. Söll\",\"doi\":\"10.1016/0167-899X(86)90009-1\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>SUPERCOIL is a code for the computational design of tokamaks, including in particular ignited next-generation devices. It takes into account all physical, technical and geometrical constraints relevant to the basic design of a tokamak. Among the solutions of the model equations that meet all constraints the one optimized with respect to a prescribed figure of merit (typically capital cost) is determined. The main components modelled are the plasma, blanket and shield, the TF system and the PF system. The main characteristics of the component models are summarized and a detailed description of the solution method is given. A typical NET study point is given as an illustrative example. The validity of the code is assessed by applying it to the ASDEX Upgrade tokamak.</p></div>\",\"PeriodicalId\":82205,\"journal\":{\"name\":\"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy\",\"volume\":\"4 1\",\"pages\":\"Pages 21-35\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"1986-01-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"https://sci-hub-pdf.com/10.1016/0167-899X(86)90009-1\",\"citationCount\":\"7\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/0167899X86900091\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy","FirstCategoryId":"1085","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/0167899X86900091","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
Supercoil: A model for the computational design of tokamaks
SUPERCOIL is a code for the computational design of tokamaks, including in particular ignited next-generation devices. It takes into account all physical, technical and geometrical constraints relevant to the basic design of a tokamak. Among the solutions of the model equations that meet all constraints the one optimized with respect to a prescribed figure of merit (typically capital cost) is determined. The main components modelled are the plasma, blanket and shield, the TF system and the PF system. The main characteristics of the component models are summarized and a detailed description of the solution method is given. A typical NET study point is given as an illustrative example. The validity of the code is assessed by applying it to the ASDEX Upgrade tokamak.
求助内容：
应助结果提醒方式：
京公网安备 11010802042870号
