Fusion Engineering and Design最新文献

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Influence of temperature gradients on helium diffusion and clustering in tungsten: A molecular dynamics study 温度梯度对钨中氦扩散和聚类的影响:分子动力学研究
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-10-13 DOI: 10.1016/j.fusengdes.2024.114687
Jingzhong Fang , Huiqiu Deng , Wangyu Hu , Ning Gao , Yonggang Tong , Yongle Hu , Shengjie Wang , Kaiming Wang
{"title":"Influence of temperature gradients on helium diffusion and clustering in tungsten: A molecular dynamics study","authors":"Jingzhong Fang ,&nbsp;Huiqiu Deng ,&nbsp;Wangyu Hu ,&nbsp;Ning Gao ,&nbsp;Yonggang Tong ,&nbsp;Yongle Hu ,&nbsp;Shengjie Wang ,&nbsp;Kaiming Wang","doi":"10.1016/j.fusengdes.2024.114687","DOIUrl":"10.1016/j.fusengdes.2024.114687","url":null,"abstract":"<div><div>Tungsten and its alloys, used as plasma-facing materials in fusion reactors, endure high-flux, low-energy helium ion irradiation and temperature gradients induced by thermal load and shocks. This study utilizes molecular dynamics (MD) simulations to explore the diffusion and clustering behavior of helium (He) in tungsten (W) under temperature gradients. The migration behavior of isolated helium atoms, small helium clusters, and helium self-interstitial atom (He-SIA) clusters within tungsten is analyzed. It is revealed that both helium and He-SIA clusters tend to migrate towards higher temperature regions, exhibiting negative thermophoresis. The nucleation of helium clusters, the formation of Frenkel pairs, and the interactions between self-interstitial clusters and helium clusters are also investigated. The results indicate that helium concentration significantly impacts He nucleation behavior. Directional diffusion may lead to areas of high concentration over time, potentially promoting the formation of He clusters and bubbles. These insights enhance the understanding of tungsten's performance and durability as a plasma-facing component in fusion reactors.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-10-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142434324","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Methodology for electromagnetic analysis using the finite element method for fusion reactor components 使用有限元法对聚变反应堆部件进行电磁分析的方法
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-10-13 DOI: 10.1016/j.fusengdes.2024.114686
A. Fernández , J. Martínez-Fernández , M. Medrano , S. Cabrera , P. Testoni , E. Rodríguez
{"title":"Methodology for electromagnetic analysis using the finite element method for fusion reactor components","authors":"A. Fernández ,&nbsp;J. Martínez-Fernández ,&nbsp;M. Medrano ,&nbsp;S. Cabrera ,&nbsp;P. Testoni ,&nbsp;E. Rodríguez","doi":"10.1016/j.fusengdes.2024.114686","DOIUrl":"10.1016/j.fusengdes.2024.114686","url":null,"abstract":"<div><div>Electromagnetic (EM) analyses are carried out when designing fusion reactor components to verify that they withstand the EM loads developed during transient plasma events, thus ensuring their proper functioning.</div><div>A complete methodology has been developed to conduct EM analyses by creating algorithms to guide the analyst during the decisions and actions to be taken, from the selection of the case events and the calculation method to the validation of the final results. This methodology has been applied to the EM analyses of the ex-vessel components of the ITER diagnostic Wide-Angle Viewing System (WAVS) in its final design stage. The calculation method selected is the Spheres-Worst instant method, implemented with a 3D finite element model. The paper includes a verification analysis of the simplifications made and a method to optimize the resources needed for the EM analysis.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-10-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142434325","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Improvement of plasma discharge performance at KTM tokamak 提高 KTM 托卡马克的等离子体放电性能
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-10-10 DOI: 10.1016/j.fusengdes.2024.114684
B. Chektybayev , I. Tazhibayeva , E. Batyrbekov , Ye. Kashikbayev , D. Olkhovik , D. Zarva , S. Zhunisbek , A. Duisen , A. Zhaksybayeva , A. Lee , V. Pavlov , V. Dokuka , R. Khayrutdinov
{"title":"Improvement of plasma discharge performance at KTM tokamak","authors":"B. Chektybayev ,&nbsp;I. Tazhibayeva ,&nbsp;E. Batyrbekov ,&nbsp;Ye. Kashikbayev ,&nbsp;D. Olkhovik ,&nbsp;D. Zarva ,&nbsp;S. Zhunisbek ,&nbsp;A. Duisen ,&nbsp;A. Zhaksybayeva ,&nbsp;A. Lee ,&nbsp;V. Pavlov ,&nbsp;V. Dokuka ,&nbsp;R. Khayrutdinov","doi":"10.1016/j.fusengdes.2024.114684","DOIUrl":"10.1016/j.fusengdes.2024.114684","url":null,"abstract":"<div><div>The paper presents the results of experimental campaigns conducted in 2022–2023 aimed at improving and enhancing plasma discharge parameters at the KTM tokamak. The experiments achieved a plasma current of approximately 500 kA in a limiter configuration, with a discharge duration of up to 2 s. Plasma discharges were obtained in the ohmic heating mode. The results described in the paper represent the next step toward achieving the plasma discharge design parameters for the KTM.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-10-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142426624","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Design and implementation of antenna control system for EAST ECRH 为 EAST ECRH 设计和实施天线控制系统
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-10-10 DOI: 10.1016/j.fusengdes.2024.114682
Yu Hua , Handong Xu , Liyuan Zhang , Weiye Xu , Dajun Wu , Xiaoguang Zhang , Long Huang
{"title":"Design and implementation of antenna control system for EAST ECRH","authors":"Yu Hua ,&nbsp;Handong Xu ,&nbsp;Liyuan Zhang ,&nbsp;Weiye Xu ,&nbsp;Dajun Wu ,&nbsp;Xiaoguang Zhang ,&nbsp;Long Huang","doi":"10.1016/j.fusengdes.2024.114682","DOIUrl":"10.1016/j.fusengdes.2024.114682","url":null,"abstract":"<div><div>The antenna system constitutes an essential component of the Electron Cyclotron Resonance Heating (ECRH) system, which is employed to inject high-power millimeter waves precisely to the specific internal resonance layer required for EAST experiments, realizing plasma heating, current driving, and magnetohydrodynamic (MHD) instability control. Therefore, an ECRH antenna control system was designed to fulfill the above requirements. The system employs the NI CompactRIO controller as the lower computer and utilizes LabVIEW as the programming language for software development. This paper decomposes the software architecture into functional modules and elaborates on the servo motor motion control module. Furthermore, the motor servo control system is modeled and simulated in MATLAB/Simulink. Then the response-time testing and position followability testing are carried out on the test bench. The measured response time of the small-angle scanning motion of the SM was less than 50 <span><math><mrow><mi>ms</mi><mo>/</mo><msup><mrow><mn>1</mn></mrow><mrow><mo>∘</mo></mrow></msup></mrow></math></span>, and the index values for tracking error of the light spots are within the range of 0.1 to 1. The test results demonstrate that the antenna control system exhibits high position control accuracy and excellent response performance, which holds significant application value for the investigation of Experimental Advanced Superconducting Tokamak (EAST) experiments, as well as providing a valuable reference for the development of similar control systems in the future fusion reactors.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-10-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142426623","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Harmonic Current Analysis of the PSM HVPS Modules under Voltage Distortion 电压畸变情况下 PSM HVPS 模块的谐波电流分析
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-10-08 DOI: 10.1016/j.fusengdes.2024.114680
Hejun Hu , Junjia Wang , Jian Zhang , Rui Guan , Hui Chen , Junchuo Luo , Yiyun Huang
{"title":"Harmonic Current Analysis of the PSM HVPS Modules under Voltage Distortion","authors":"Hejun Hu ,&nbsp;Junjia Wang ,&nbsp;Jian Zhang ,&nbsp;Rui Guan ,&nbsp;Hui Chen ,&nbsp;Junchuo Luo ,&nbsp;Yiyun Huang","doi":"10.1016/j.fusengdes.2024.114680","DOIUrl":"10.1016/j.fusengdes.2024.114680","url":null,"abstract":"<div><div>To reduce the errors caused by current superposition with many power modules in Pulse-step modulation (PSM) high-voltage power supply (HVPS), it is necessary to establish more accurate current models of the PSM power modules that are supplied by different windings. The electrical models of power modules connected by different windings (wye and delta) are established, and the current mathematical models in windings are deduced, respectively. The \"correlation function\" is introduced to establish the relation of the harmonic voltage among two power modules connected to different windings when calculating the harmonic superposition. The current mathematical models in windings of two power modules are verified by simulation, and the performance of the two methods of the correlation function proposed is compared to the result of the simulation. The research shows that the current waveform generated by the power module in the winding under the distorted voltage can be obtained by the mathematical models, and the more accurate current superposition by the correlation function which establishes the relationship between the mathematical models in the two windings. Besides, the current in the AC side of power modules is significantly affected by the different harmonic ratio of voltage and its phases.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-10-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142426622","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Development of a multi-spectral extreme ultraviolet imaging diagnostics on the Experimental Advanced Superconducting Tokamak 在先进超导实验托卡马克上开发多光谱极紫外成像诊断仪
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-10-07 DOI: 10.1016/j.fusengdes.2024.114681
Shanwei Hou , Tingfeng Ming , Haoxuan Si , Shengzhen Yi , QiQi Shi , Rongjing Deng , Wenmin Zhang , Yue Yu , Xiaoju Liu , Gongshun Li , Ling Zhang , Genfan Ding , Motoshi Goto , Tao Zhang , Zhe Zhang , Zhanshan Wang , Xiang Gao , Guoqiang Li
{"title":"Development of a multi-spectral extreme ultraviolet imaging diagnostics on the Experimental Advanced Superconducting Tokamak","authors":"Shanwei Hou ,&nbsp;Tingfeng Ming ,&nbsp;Haoxuan Si ,&nbsp;Shengzhen Yi ,&nbsp;QiQi Shi ,&nbsp;Rongjing Deng ,&nbsp;Wenmin Zhang ,&nbsp;Yue Yu ,&nbsp;Xiaoju Liu ,&nbsp;Gongshun Li ,&nbsp;Ling Zhang ,&nbsp;Genfan Ding ,&nbsp;Motoshi Goto ,&nbsp;Tao Zhang ,&nbsp;Zhe Zhang ,&nbsp;Zhanshan Wang ,&nbsp;Xiang Gao ,&nbsp;Guoqiang Li","doi":"10.1016/j.fusengdes.2024.114681","DOIUrl":"10.1016/j.fusengdes.2024.114681","url":null,"abstract":"<div><div>A multi-spectral extreme ultraviolet imaging (MEUVI) diagnostics to measure impurity line emissions on the Experimental Advanced Superconducting Tokamak (EAST) is proposed and being developed to measure the electron temperature at the edge region. It makes use of multi-channel multilayers Schwarzschild telescope, coupled with a micro-channel plate (MCP) equipped with a P46 phosphor screen, and a high-speed camera with a CMOS sensor to image the selected line emissions, i.e., C IV lines (312.4 Å, 419.7 Å), W XLVI line (127 Å), Ne VIII lines (88.1 Å, 103 Å), and Ne VII Line (465.2 Å), at the edge region in two dimensions with high spatial and temporal resolutions simultaneously. The MEUVI diagnostics is installed on the EAST horizontal J port to monitor plasma and first imaging data is obtained during the commissioning of the system in the 2024 experiment campaign. It is in good agreement with that measured by the traditional extreme ultraviolet (EUV) spectrometer. In addition, the electron temperature derived from the MEUVI data is higher than that given by the Helium beam emission (He-BES) spectroscopy system since the Ne VIII emission is mainly located inside the last closed surface region. However, the tendency of the evolution of the electron temperature is consistent each other, which are given by these two systems. These results verify that the MEUVI diagnostics can work as a potential tool for the measurement of edge plasma temperature and monitoring of impurities.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-10-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142426621","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Socio economic perspectives on fusion power for a sustainable future energy system 从社会经济角度看聚变发电对未来可持续能源系统的影响
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-10-04 DOI: 10.1016/j.fusengdes.2024.114679
C. Bustreo , N. Ben Ayed , M. Biberacher , G. Bongiovì , E. Börcsök , R. Čadenović , V. Cok , G. Colucci , E. De Marchi , D.N. Dongiovanni , Z. Ferencz , R. Geysmans , A. Giacometti , F. Gracceva , C.R. Jones , R. Kembleton , J. Kenens , U. Lamut , Y. Lechon , D. Lerede , S.H. Ward
{"title":"Socio economic perspectives on fusion power for a sustainable future energy system","authors":"C. Bustreo ,&nbsp;N. Ben Ayed ,&nbsp;M. Biberacher ,&nbsp;G. Bongiovì ,&nbsp;E. Börcsök ,&nbsp;R. Čadenović ,&nbsp;V. Cok ,&nbsp;G. Colucci ,&nbsp;E. De Marchi ,&nbsp;D.N. Dongiovanni ,&nbsp;Z. Ferencz ,&nbsp;R. Geysmans ,&nbsp;A. Giacometti ,&nbsp;F. Gracceva ,&nbsp;C.R. Jones ,&nbsp;R. Kembleton ,&nbsp;J. Kenens ,&nbsp;U. Lamut ,&nbsp;Y. Lechon ,&nbsp;D. Lerede ,&nbsp;S.H. Ward","doi":"10.1016/j.fusengdes.2024.114679","DOIUrl":"10.1016/j.fusengdes.2024.114679","url":null,"abstract":"<div><div>In the global effort towards the mitigation of climate change, low-carbon electricity generating technologies play a pivotal role. Nuclear fusion stands as a highly promising option for carbon-free electricity generation in a sustainable, reliable, affordable and socially acceptable future energy system. The EUROfusion work package “Socio Economic Studies” (WPSES) on fusion conducts research aimed at identifying social and economic conditions that can effectively support fusion deployment in future energy markets. Placing nuclear fusion in the broader context of energy and climate issues, the SES research explores fusion as an energy technology contributing to sustainable energy production for the future society. Because of the cross-cutting nature of the research, SES studies can provide decision-makers with scientific evidence relevant for shaping appropriate strategies in favour of fusion. This paper aims to offer the scientific community a thorough overview of EUROfusion SES research, addressing a gap in the current literature.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-10-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142426746","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Elucidating the thermal response of W-Ta alloys with Transient Grating Spectroscopy, TEM and atomistic simulation 利用瞬态光栅光谱学、TEM 和原子模拟阐明 W-Ta 合金的热响应
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-10-01 DOI: 10.1016/j.fusengdes.2024.114676
E. Yildirim , E. Jimenez-Melero , B. Dacus , C. Dennett , K.B. Woller , M. Short , P.M. Mummery
{"title":"Elucidating the thermal response of W-Ta alloys with Transient Grating Spectroscopy, TEM and atomistic simulation","authors":"E. Yildirim ,&nbsp;E. Jimenez-Melero ,&nbsp;B. Dacus ,&nbsp;C. Dennett ,&nbsp;K.B. Woller ,&nbsp;M. Short ,&nbsp;P.M. Mummery","doi":"10.1016/j.fusengdes.2024.114676","DOIUrl":"10.1016/j.fusengdes.2024.114676","url":null,"abstract":"<div><div>Critical for tungsten alloys’ use as plasma-facing component materials are their thermal response and their evolution under irradiation. Utilising Transient Grating Spectroscopy, TEM, and Molecular Dynamics, this study sought to probe these changes in W, W6Ta, and W11Ta alloys. Irradiation with 12.25 MeV W<span><math><msup><mrow></mrow><mrow><mn>6</mn><mo>+</mo></mrow></msup></math></span> ions was carried out in the CLASS facility at MIT at a temperature of 500 °C for doses of 0.1, 0.3, and 1.0 dpa. The alloys’ thermal diffusivity was found to degrade less than that of the pure counterpart. Molecular Dynamics simulation revealed that this was due to a reduced defect population below TEM resolution. Despite these alloys showing enhanced resilience to thermal property degradation, it was found that the absolute values of their thermal diffusivity remained below that of pure tungsten. This study highlighted a key interplay between enhancing radiation tolerance with alloying additions and the alloy additions’ initial negative effect on the thermal response and thus in-service behaviour.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-10-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142426625","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Measurements of microwave transmission mode in HL-3 tokamak relevant ECH corrugated waveguides transmission line 测量 HL-3 托卡马克中与 ECH 波纹波导传输线相关的微波传输模式
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-09-29 DOI: 10.1016/j.fusengdes.2024.114677
Guoyao Fan , Mei Huang , Donghui Xia , Cheng Chen , Feng Zhang , Xixuan Chen , Wanxin Zheng , Gangyu Chen
{"title":"Measurements of microwave transmission mode in HL-3 tokamak relevant ECH corrugated waveguides transmission line","authors":"Guoyao Fan ,&nbsp;Mei Huang ,&nbsp;Donghui Xia ,&nbsp;Cheng Chen ,&nbsp;Feng Zhang ,&nbsp;Xixuan Chen ,&nbsp;Wanxin Zheng ,&nbsp;Gangyu Chen","doi":"10.1016/j.fusengdes.2024.114677","DOIUrl":"10.1016/j.fusengdes.2024.114677","url":null,"abstract":"<div><div>The transmission modes of high-power millimeter wave in corrugated waveguides transmission line (TL) are crucial, especially for the long-pulse operation for long-distance TL. The microwave transmission mode in the TL on HL-3 tokamak relevant the electron cyclotron heating system are studied for the purpose according to the phase retrieval method based on intensity distribution measured by an infrared camera at several different locations away from the outlet of TL. A specific high power test platform with about 40-meter TL is established and the mode contents in the middle and the end of the TL are analyzed. In the middle of the TL, the proportion of main transmission mode LP<sub>01</sub> mode is about 97 % and other high-order modes contents are &lt;3 %. In the end of the TL, the main mode purity is about 94 %, and the high-order mode, LP<sub>11</sub> even mode is excited about 4.6 %. These mode analysis results indicate that the high-power and long-pulse millimeter wave corrugated waveguides TL are designed and machined well, and the alignment method for long distance transmission line installation is highly useful for high-purity wave mode transmission.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142357804","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Lithium vapour-box divertor module design for investigating vapour shielding performance and lithium transport in linear plasma generator Magnum-PSI 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
IF 1.9 3区 工程技术
Fusion Engineering and Design Pub Date : 2024-09-27 DOI: 10.1016/j.fusengdes.2024.114659
F. Romano , V.F.B. Tanke , J.A. Schwartz , S. Brons , R.J. Goldston , T.W. Morgan
{"title":"Lithium vapour-box divertor module design for investigating vapour shielding performance and lithium transport in linear plasma generator Magnum-PSI","authors":"F. Romano ,&nbsp;V.F.B. Tanke ,&nbsp;J.A. Schwartz ,&nbsp;S. Brons ,&nbsp;R.J. Goldston ,&nbsp;T.W. Morgan","doi":"10.1016/j.fusengdes.2024.114659","DOIUrl":"10.1016/j.fusengdes.2024.114659","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":1.9,"publicationDate":"2024-09-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142326352","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
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