{"title":"托卡马克聚变反应堆准稳态运行对环形场线圈倾覆力引起的循环应力疲劳的减小","authors":"Satoshi Nishio, Masayoshi Sugihara","doi":"10.1016/0167-899X(85)90034-5","DOIUrl":null,"url":null,"abstract":"<div><p>It is shown that the cyclic stress fatigue due to the over-turning force on the toroidal field coils in a tokamak fusion reactor can be greatly reduced by appropriately changing the plasma current in the recharging phase of the quasi-steady operation scenario with the use of lower hybrid wave current drive. This substantial reduction is made possible, if the characteristics of required variation of the equilbrium magnetic field for the dee-shaped divertor plasma is properly taken into account in adjusting the plasma current, in which the necessary equilibrium field becomes larger in low beta phase than in high beta phase for the same plasma current.</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":"3 1","pages":"Pages 59-62"},"PeriodicalIF":0.0000,"publicationDate":"1985-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0167-899X(85)90034-5","citationCount":"0","resultStr":"{\"title\":\"Reduction of the cyclic stress fatigue due to the over-turning force on the toroidal field coils by quasi-steady operation in a tokamak fusion reactor\",\"authors\":\"Satoshi Nishio, Masayoshi Sugihara\",\"doi\":\"10.1016/0167-899X(85)90034-5\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>It is shown that the cyclic stress fatigue due to the over-turning force on the toroidal field coils in a tokamak fusion reactor can be greatly reduced by appropriately changing the plasma current in the recharging phase of the quasi-steady operation scenario with the use of lower hybrid wave current drive. This substantial reduction is made possible, if the characteristics of required variation of the equilbrium magnetic field for the dee-shaped divertor plasma is properly taken into account in adjusting the plasma current, in which the necessary equilibrium field becomes larger in low beta phase than in high beta phase for the same plasma current.</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\":\"3 1\",\"pages\":\"Pages 59-62\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"1985-01-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"https://sci-hub-pdf.com/10.1016/0167-899X(85)90034-5\",\"citationCount\":\"0\",\"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/0167899X85900345\",\"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/0167899X85900345","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
Reduction of the cyclic stress fatigue due to the over-turning force on the toroidal field coils by quasi-steady operation in a tokamak fusion reactor
It is shown that the cyclic stress fatigue due to the over-turning force on the toroidal field coils in a tokamak fusion reactor can be greatly reduced by appropriately changing the plasma current in the recharging phase of the quasi-steady operation scenario with the use of lower hybrid wave current drive. This substantial reduction is made possible, if the characteristics of required variation of the equilbrium magnetic field for the dee-shaped divertor plasma is properly taken into account in adjusting the plasma current, in which the necessary equilibrium field becomes larger in low beta phase than in high beta phase for the same plasma current.