{"title":"ITER高压氦冷却罩/包层的热水力分析","authors":"R. Bourque, C. Wong","doi":"10.1109/FUSION.1993.518329","DOIUrl":null,"url":null,"abstract":"A helium-cooled blanket/shield for ITER is presented that can provide high-grade heat and tritium self-sufficiency. It consists of narrow and relatively simple canisters filled with static liquid metal which is cooled by high pressure helium flowing through small double-walled tubes immersed in the liquid metal. The gaps between the tubes are also filled with static liquid metal. There are therefore three barriers between high-pressure helium and vacuum. Thermal-hydraulic analyses are presented that show the concept to be viable with both ferritic steel and vanadium alloy and with lithium and NaK liquid metal.","PeriodicalId":365814,"journal":{"name":"15th IEEE/NPSS Symposium. Fusion Engineering","volume":"75 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"1993-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"1","resultStr":"{\"title\":\"Thermal-hydraulic analysis of a high-pressure helium-cooled shield/blanket for ITER\",\"authors\":\"R. Bourque, C. Wong\",\"doi\":\"10.1109/FUSION.1993.518329\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"A helium-cooled blanket/shield for ITER is presented that can provide high-grade heat and tritium self-sufficiency. It consists of narrow and relatively simple canisters filled with static liquid metal which is cooled by high pressure helium flowing through small double-walled tubes immersed in the liquid metal. The gaps between the tubes are also filled with static liquid metal. There are therefore three barriers between high-pressure helium and vacuum. Thermal-hydraulic analyses are presented that show the concept to be viable with both ferritic steel and vanadium alloy and with lithium and NaK liquid metal.\",\"PeriodicalId\":365814,\"journal\":{\"name\":\"15th IEEE/NPSS Symposium. Fusion Engineering\",\"volume\":\"75 1\",\"pages\":\"0\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"1993-10-11\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"1\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"15th IEEE/NPSS Symposium. Fusion Engineering\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.1109/FUSION.1993.518329\",\"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.1993.518329","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
Thermal-hydraulic analysis of a high-pressure helium-cooled shield/blanket for ITER
A helium-cooled blanket/shield for ITER is presented that can provide high-grade heat and tritium self-sufficiency. It consists of narrow and relatively simple canisters filled with static liquid metal which is cooled by high pressure helium flowing through small double-walled tubes immersed in the liquid metal. The gaps between the tubes are also filled with static liquid metal. There are therefore three barriers between high-pressure helium and vacuum. Thermal-hydraulic analyses are presented that show the concept to be viable with both ferritic steel and vanadium alloy and with lithium and NaK liquid metal.
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