F. Romano , V.F.B. Tanke , J.A. Schwartz , S. Brons , R.J. Goldston , T.W. Morgan
{"title":"用于研究线性等离子体发生器 Magnum-PSI 中蒸汽屏蔽性能和锂传输的锂蒸汽箱分流器模块设计","authors":"F. Romano , V.F.B. Tanke , J.A. Schwartz , S. Brons , R.J. Goldston , T.W. Morgan","doi":"10.1016/j.fusengdes.2024.114659","DOIUrl":null,"url":null,"abstract":"<div><div>The vapour box divertor concept aims to handle the tremendous high heat flux in a tokamak fusion power plant by strongly evaporating lithium with and into the plasma for cooling and using a closed divertor structure to limit lithium migration. To test this concept, a vapour box module (VBM) was designed for the first time for use with the Magnum-PSI linear plasma device, which is capable of producing plasma with divertor-relevant conditions. The goal was to reduce the total heat load from the plasma beam on the target of 3 kW by 50% and recapture lithium to minimize migration and protect diagnostics. The VBM consists of a heated central box with a lithium reservoir and two cold side boxes to promote recondensation. Simulations made with the direct simulation Monte Carlo code SPARTA determined optimal operating temperatures of 800–1000 K and highlighted the importance of the nozzle diameter and side box length in controlling lithium migration. Thermal modelling showed that a 2 kW conduction heater would efficiently reach the desired temperature. Based on these findings, an engineering design for the VBM was developed to evaluate the concept in Magnum-PSI, advancing the vapour box divertor towards practical use.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-09-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Lithium vapour-box divertor module design for investigating vapour shielding performance and lithium transport in linear plasma generator Magnum-PSI\",\"authors\":\"F. Romano , V.F.B. Tanke , J.A. Schwartz , S. Brons , R.J. Goldston , T.W. Morgan\",\"doi\":\"10.1016/j.fusengdes.2024.114659\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The vapour box divertor concept aims to handle the tremendous high heat flux in a tokamak fusion power plant by strongly evaporating lithium with and into the plasma for cooling and using a closed divertor structure to limit lithium migration. To test this concept, a vapour box module (VBM) was designed for the first time for use with the Magnum-PSI linear plasma device, which is capable of producing plasma with divertor-relevant conditions. The goal was to reduce the total heat load from the plasma beam on the target of 3 kW by 50% and recapture lithium to minimize migration and protect diagnostics. The VBM consists of a heated central box with a lithium reservoir and two cold side boxes to promote recondensation. Simulations made with the direct simulation Monte Carlo code SPARTA determined optimal operating temperatures of 800–1000 K and highlighted the importance of the nozzle diameter and side box length in controlling lithium migration. Thermal modelling showed that a 2 kW conduction heater would efficiently reach the desired temperature. Based on these findings, an engineering design for the VBM was developed to evaluate the concept in Magnum-PSI, advancing the vapour box divertor towards practical use.</div></div>\",\"PeriodicalId\":55133,\"journal\":{\"name\":\"Fusion Engineering and Design\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2024-09-27\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Fusion Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0920379624005106\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379624005106","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Lithium vapour-box divertor module design for investigating vapour shielding performance and lithium transport in linear plasma generator Magnum-PSI
The vapour box divertor concept aims to handle the tremendous high heat flux in a tokamak fusion power plant by strongly evaporating lithium with and into the plasma for cooling and using a closed divertor structure to limit lithium migration. To test this concept, a vapour box module (VBM) was designed for the first time for use with the Magnum-PSI linear plasma device, which is capable of producing plasma with divertor-relevant conditions. The goal was to reduce the total heat load from the plasma beam on the target of 3 kW by 50% and recapture lithium to minimize migration and protect diagnostics. The VBM consists of a heated central box with a lithium reservoir and two cold side boxes to promote recondensation. Simulations made with the direct simulation Monte Carlo code SPARTA determined optimal operating temperatures of 800–1000 K and highlighted the importance of the nozzle diameter and side box length in controlling lithium migration. Thermal modelling showed that a 2 kW conduction heater would efficiently reach the desired temperature. Based on these findings, an engineering design for the VBM was developed to evaluate the concept in Magnum-PSI, advancing the vapour box divertor towards practical use.
期刊介绍:
The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.