{"title":"Neutral beam stopping and shine-through calculations for fusion neutron source DEMO-FNS","authors":"E. Dlougach, B. Kuteev","doi":"10.1063/1.5135477","DOIUrl":null,"url":null,"abstract":"BTR code, which is generally used for NBI beamlines design and optimizations, is applied to calculate beam stopping and shine-through power in a fusion neutron source DEMO-FNS tokamak (R = 3.2m, a = 1m, k = 2, B = 5T, ED = 500keV, PNBI ≈ 30MW). Beam-plasma model applies the available cross-section fits and reproduces the detailed beam spatial and angular distributions (BTR standard beam) for different operation scenarios and calculates atomic power decay 3D-profiles, beam footprints and ions source distributions. The model is used to study the effect of injected beam geometry on the beam capture and shine-through power deposition.BTR code, which is generally used for NBI beamlines design and optimizations, is applied to calculate beam stopping and shine-through power in a fusion neutron source DEMO-FNS tokamak (R = 3.2m, a = 1m, k = 2, B = 5T, ED = 500keV, PNBI ≈ 30MW). Beam-plasma model applies the available cross-section fits and reproduces the detailed beam spatial and angular distributions (BTR standard beam) for different operation scenarios and calculates atomic power decay 3D-profiles, beam footprints and ions source distributions. The model is used to study the effect of injected beam geometry on the beam capture and shine-through power deposition.","PeriodicalId":176911,"journal":{"name":"PROCEEDINGS OF THE INTERNATIONAL CONFERENCE ON ADVANCES AND APPLICATIONS IN PLASMA PHYSICS (AAPP 2019)","volume":"13 2","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"2019-11-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"1","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"PROCEEDINGS OF THE INTERNATIONAL CONFERENCE ON ADVANCES AND APPLICATIONS IN PLASMA PHYSICS (AAPP 2019)","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1063/1.5135477","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
BTR code, which is generally used for NBI beamlines design and optimizations, is applied to calculate beam stopping and shine-through power in a fusion neutron source DEMO-FNS tokamak (R = 3.2m, a = 1m, k = 2, B = 5T, ED = 500keV, PNBI ≈ 30MW). Beam-plasma model applies the available cross-section fits and reproduces the detailed beam spatial and angular distributions (BTR standard beam) for different operation scenarios and calculates atomic power decay 3D-profiles, beam footprints and ions source distributions. The model is used to study the effect of injected beam geometry on the beam capture and shine-through power deposition.BTR code, which is generally used for NBI beamlines design and optimizations, is applied to calculate beam stopping and shine-through power in a fusion neutron source DEMO-FNS tokamak (R = 3.2m, a = 1m, k = 2, B = 5T, ED = 500keV, PNBI ≈ 30MW). Beam-plasma model applies the available cross-section fits and reproduces the detailed beam spatial and angular distributions (BTR standard beam) for different operation scenarios and calculates atomic power decay 3D-profiles, beam footprints and ions source distributions. The model is used to study the effect of injected beam geometry on the beam capture and shine-through power deposition.
应用一般用于NBI束流线设计和优化的BTR代码,计算了聚变中子源demo_fns托卡马克(R = 3.2m, a = 1m, k = 2, B = 5T, ED = 500keV, PNBI≈30MW)束流的停束和透光功率。光束-等离子体模型应用可用的截面拟合,重现了不同操作场景下的详细光束空间和角度分布(BTR标准光束),并计算了原子功率衰减3d轮廓、光束足迹和离子源分布。利用该模型研究了注入光束几何形状对光束捕获和通光功率沉积的影响。应用一般用于NBI束流线设计和优化的BTR代码,计算了聚变中子源demo_fns托卡马克(R = 3.2m, a = 1m, k = 2, B = 5T, ED = 500keV, PNBI≈30MW)束流的停束和透光功率。光束-等离子体模型应用可用的截面拟合,重现了不同操作场景下的详细光束空间和角度分布(BTR标准光束),并计算了原子功率衰减3d轮廓、光束足迹和离子源分布。利用该模型研究了注入光束几何形状对光束捕获和通光功率沉积的影响。