{"title":"Role of additional grids on ion flow dynamics of an inertial electrostatic confinement fusion neutron source","authors":"S.R. Mohanty , L. Saikia , N. Bharali , S. Kalita","doi":"10.1016/j.fusengdes.2025.114985","DOIUrl":null,"url":null,"abstract":"<div><div>The present study aims to enhance the performance of an inertial electrostatic confinement fusion (IECF) device in terms of neutron production rate. Previously, we achieved a neutron generation rate of 10<sup>6</sup> neutrons per second, but for broader applications of the device, higher neutron production is needed by increasing ion density and energy. Additionally, more stable and well-confined plasma with longer confinement times is essential. We compared a conventional single-grid IECF device to a new triple-grid version to assess the advantages of using multiple grids for ion confinement. Our computational models, using the 2D-3V XOOPIC code, indicate that the optimized potentials of the triple-grid device can significantly improve ion confinement. The models reveal that the triple-grid design more effectively channels ion beams toward the center, compared to the more dispersed ion distribution in the single-grid design. Alterations in the electrostatic fields generate a modified potential well, resulting in the formation of highly concentrated ion beams channeled through specific pathways. Preliminary experimental results indicate a one-order improvement in neutron yield (10<sup>7</sup> neutrons per second) due to the functional improvement in the triple-grid system.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114985"},"PeriodicalIF":1.9000,"publicationDate":"2025-03-27","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/S0920379625001851","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}
Role of additional grids on ion flow dynamics of an inertial electrostatic confinement fusion neutron source
The present study aims to enhance the performance of an inertial electrostatic confinement fusion (IECF) device in terms of neutron production rate. Previously, we achieved a neutron generation rate of 106 neutrons per second, but for broader applications of the device, higher neutron production is needed by increasing ion density and energy. Additionally, more stable and well-confined plasma with longer confinement times is essential. We compared a conventional single-grid IECF device to a new triple-grid version to assess the advantages of using multiple grids for ion confinement. Our computational models, using the 2D-3V XOOPIC code, indicate that the optimized potentials of the triple-grid device can significantly improve ion confinement. The models reveal that the triple-grid design more effectively channels ion beams toward the center, compared to the more dispersed ion distribution in the single-grid design. Alterations in the electrostatic fields generate a modified potential well, resulting in the formation of highly concentrated ion beams channeled through specific pathways. Preliminary experimental results indicate a one-order improvement in neutron yield (107 neutrons per second) due to the functional improvement in the triple-grid system.
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.