Journal of Fusion Energy最新文献

Study of Resistive Wall Mode Feedback Control with Varying Plasma Configurations 变等离子体结构的电阻壁模式反馈控制研究

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2025-10-17 DOI: 10.1007/s10894-025-00519-x

Jing Wu, Shuo Wang, Xue-Feng Chen, Guang-Zhou Hao, Lei Xue, Yue-bin Liang, Peng Lu, Lie-Ming Yao

引用次数: 0

Tritium Management for LHD Deuterium Plasma Experiments LHD氘等离子体实验氚管理

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2025-10-15 DOI: 10.1007/s10894-025-00518-y

Masahiro Tanaka, Hiromi Kato, Miki Nakada, Saori Kurita, Chie Iwata, Hiroki Chimura, Naoyuki Suzuki

{"title":"Tritium Management for LHD Deuterium Plasma Experiments","authors":"Masahiro Tanaka, Hiromi Kato, Miki Nakada, Saori Kurita, Chie Iwata, Hiroki Chimura, Naoyuki Suzuki","doi":"10.1007/s10894-025-00518-y","DOIUrl":"10.1007/s10894-025-00518-y","url":null,"abstract":"<div><p>In high-temperature plasma experiments using deuterium gas in large fusion devices, tritium is produced by the deuterium fusion reaction. Although the amount of tritium produced is not large, it is a radioactive material, so it is essential to develop safe handling systems and obtain public acceptance. Here, we summarize tritium safety management and tritium behavior in the facility, and have monitored the results of six years of deuterium plasma experiments in the Large Helical Device (LHD). More than 95% of the tritium exhausted from the LHD vacuum vessel was recovered by a tritium removal system. The extremely low concentrations of tritium discharged from the stack into the environment were monitored for each chemical form of tritiated water vapor, tritiated molecular hydrogen, and tritiated hydrocarbons, and were verified to be well below the levels specified by management at the National Institute for Fusion Science (NIFS). Although the tritium handled in the LHD deuterium experiment was a small amount, the operational experience and the instruments thereby developed would likely be useful for tritium safety management in future fusion reactors.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"44 2","pages":""},"PeriodicalIF":2.1,"publicationDate":"2025-10-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-025-00518-y.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145315852","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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

Recent Developments of the in-divertor Optical Box of the ITER Erosion Deposition Monitor ITER侵蚀沉积监测仪内导光箱的最新进展

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2025-10-14 DOI: 10.1007/s10894-025-00517-z

Miklos Palankai, Teteny Baross, Jeno Kadi, Tamas Turcsik, Matyas Toth, Eszter Szucs, Gabor Szarvas, Fruzsina Daranyi, Attila Bohm, Gabor Veres, Mark Kempenaars, Govindarajan Jagannathan

{"title":"Recent Developments of the in-divertor Optical Box of the ITER Erosion Deposition Monitor","authors":"Miklos Palankai, Teteny Baross, Jeno Kadi, Tamas Turcsik, Matyas Toth, Eszter Szucs, Gabor Szarvas, Fruzsina Daranyi, Attila Bohm, Gabor Veres, Mark Kempenaars, Govindarajan Jagannathan","doi":"10.1007/s10894-025-00517-z","DOIUrl":"10.1007/s10894-025-00517-z","url":null,"abstract":"<div><p>The primary purpose of the ITER Erosion Deposition Monitor (EDM) is to track the erosion and deposition conditions of the Divertor Vertical Targets, as well as to monitor any changes in topology and surface damage resulting from plasma-wall interactions at these targets. The optical box of this diagnostic system, which is mounted on one of the Divertor Cassettes beneath the Divertor Dome, serves to provide a rigid support and protective shielding for the optical components housed inside. The EDM is an optical diagnostic system, whose accuracy depends on the integrity of the mechanical parts. The most critical in-vessel parts of this diagnostic system can be found on one of the Divertor Cassettes of the ITER machines, exposed to high heat and electromagnetic (EM) loads. The design challenges involve finding a solution for the proper heat transfer between the different components and besides, it is creating a solid design that can withstand the loads the optical box is exposed to. To achieve the required design level, the optical box and its components went through several design changes and simulation stages. This paper focuses on the challenges of the mechanical development of the parts that can be found on the Divertor Cassette. These components are the structural elements of the optical box and the support brackets of the mirrors inside the box. The paper presents the results of the analyses and the mechanical solutions of the structure of the box and the mirror supports which could withstand the high heat load and mechanical stresses coming from the EM loads.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"44 2","pages":""},"PeriodicalIF":2.1,"publicationDate":"2025-10-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-025-00517-z.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145315993","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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

Active Divertor Heat Flux Control using Impurity Powder Dropper 采用杂质粉末滴管的主动导流器热流控制

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2025-10-06 DOI: 10.1007/s10894-025-00513-3

M. Ono, R. Raman, R. Maingi, S. Kaye, A. Sanchez-Villar

{"title":"Active Divertor Heat Flux Control using Impurity Powder Dropper","authors":"M. Ono, R. Raman, R. Maingi, S. Kaye, A. Sanchez-Villar","doi":"10.1007/s10894-025-00513-3","DOIUrl":"10.1007/s10894-025-00513-3","url":null,"abstract":"<div><p>Divertor plasma-facing components (PFCs) in a tokamak are typically designed to withstand average steady-state heat loads of about 5–10 MW/m², a limit that applies to both solid and liquid lithium (LL) PFCs. Exceeding these design values can result in surface damage to tungsten PFCs or excessive lithium (Li) evaporation in liquid lithium divertor (LLD) PFCs. Since exceeding the divertor heat load limits has serious consequences, it is therefore prudent to develop a tool to reduce the divertor heat load and bring the heat load to within the design limit without affecting the plasma performance. Active low Z impurity injection such as Li has been suggested as a potential solution to mitigate excess heat flux as suggested previously, given that non-coronal radiation can be quite large ~ 20–30 MJ per mole of injected Li. Li is considered desirable for reducing the edge neutral recycling helping to improve plasma energy confinement. In this paper, we model the Impurity Power Dropper (IPD) to investigate its potential of divertor heat flux control. The IPD is typically located at the top of the tokamak device and uses a vertical drift tube of a few meters. In the 2 m drift tube case, the IPD powder is accelerated to ~ 6 m/sec before reaching the plasma with the upper divertor configuration, matching the condition for the in-board side pellet injection case. By modeling the IPD geometry we determined the IPD powder deposition profile, and thus the non-coronal radiation and ionization profiles in time as well. From the enhanced radiation power loss, it is therefore possible to reduce the divertor heat load using the divertor simulation code. The IPD divertor heat flux control can be tested in the facilities with IPD including ST-40, DIII-D, EAST, WEST and NSTX-U.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"44 2","pages":""},"PeriodicalIF":2.1,"publicationDate":"2025-10-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145256228","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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

Spectroscopic Diagnostics of Non-Maxwellian Electron Velocity Distribution Function in the Large Helical Device 大型螺旋装置中非麦克斯韦电子速度分布函数的光谱诊断

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2025-09-27 DOI: 10.1007/s10894-025-00516-0

Tomoko Kawate, Motoshi Goto

引用次数: 0

Developing Integrated Cost Models for Fusion Power Plants 发展核聚变电厂的综合成本模型

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2025-09-24 DOI: 10.1007/s10894-025-00515-1

Rhian Chapman

{"title":"Developing Integrated Cost Models for Fusion Power Plants","authors":"Rhian Chapman","doi":"10.1007/s10894-025-00515-1","DOIUrl":"10.1007/s10894-025-00515-1","url":null,"abstract":"<div><p>Systems models and associated cost analyses are widely used within the fusion community to analyse tokamak designs, from prototype and demonstrator machines to potential commercial fusion power plants. To ensure the design programmes of fusion prototype/demonstrator power plants deliver a cost optimised design (within existing uncertainty limitations) the use of integrated cost modelling during the design process is essential. This integration produces holistic solutions in which engineering design choices and changes are directly represented in the cost results, allowing alternative solutions to be tested technologically and financially in the same analysis and cost estimates to be directly aligned with each specific design solution. Using examples from the STEP (Spherical Tokamak for Energy Production) programme this paper shows how implementing such an approach allows an interrogation of the design through the lens of cost-effectiveness, enabling a systematic exploration of potential trade-offs between performance and cost, highlighting cost drivers and interrogating the design aspects underpinning them, and facilitating holistic comparisons between design options. Including cost analysis into early design decisions through integrated cost modelling will drive a cost-optimised design; this is vital in proving that fusion power plants can be an economically viable energy source. One top-level example of this approach is understanding the critical size drivers and therefore cost drivers of the design, such as the inboard radial build for the STEP design. This understanding enables optimisation of this parameter within the relevant margins required to ensure performance (within design uncertainties).</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"44 2","pages":""},"PeriodicalIF":2.1,"publicationDate":"2025-09-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-025-00515-1.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145144599","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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

Review of Contributions of Image Observations Using Visible Cameras to Advancements in Sustaining Long-pulse Discharges in LHD 可见光相机图像观测对LHD持续长脉冲放电的贡献综述

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2025-09-24 DOI: 10.1007/s10894-025-00514-2

Mamoru Shoji, Hiroshi Kasahara, Tesuo Seki, Ryohsuke Seki, Masayuki Tokitani, Hirohiko Tanaka, Suguru Masuzaki, Motoshi Goto

{"title":"Review of Contributions of Image Observations Using Visible Cameras to Advancements in Sustaining Long-pulse Discharges in LHD","authors":"Mamoru Shoji, Hiroshi Kasahara, Tesuo Seki, Ryohsuke Seki, Masayuki Tokitani, Hirohiko Tanaka, Suguru Masuzaki, Motoshi Goto","doi":"10.1007/s10894-025-00514-2","DOIUrl":"10.1007/s10894-025-00514-2","url":null,"abstract":"<div><p>This paper reviews the contributions of image observations to extending the duration of Ion Cyclotron Range of Frequencies (ICRF)-heated long-pulse discharges in the Large Helical Device (LHD). The plasma discharges were monitored using over 25 visible cameras, three fast-framing cameras, and various advanced plasma diagnostics, which revealed that most long-pulse discharges were interrupted by the following four events: termination of ICRF plasma heating due to arcing events in antennas, uncontrollable plasma density rise by outgassing from divertor plates, iron influx from plasma-facing components in the vacuum vessel, and carbon influx originating from the divertor regions. Image observations played a crucial role in mitigating the above four events that restricted the duration of long-pulse discharges by implementing appropriate countermeasures such as enhancing the cooling efficiency of the divertor plates, adopting new operational techniques to disperse the heat-load distribution, improving the ICRF antenna configurations, installing new additional ICRF antennas, and modifying the divertor configuration. Interruptions in long-pulse discharges were statistically analyzed using experimental data in three previous experimental campaigns, demonstrating a history of continuous efforts to extend the plasma discharge duration. This paper highlights the contributions of image observations over the past two decades, which have revealed inherent limitations in conventional magnetic plasma confinement devices that utilize carbon and iron plasma-facing components in sustaining steady-state plasma discharges. Knowledge obtained from statistical analysis provides valuable information for optimizing next-generation plasma confinement devices aiming at steady-state operation.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"44 2","pages":""},"PeriodicalIF":2.1,"publicationDate":"2025-09-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-025-00514-2.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145144600","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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

Spectroscopic Diagnostics for Highly Charged Iron Ions Observed in Solar Corona and LHD 在日冕和LHD观测到的高电荷铁离子的光谱诊断

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2025-09-18 DOI: 10.1007/s10894-025-00512-4

Tetsuya Watanabe, Hirohisa Hara

引用次数: 0

Conceptual Design and Analysis of Tritium Confinement Ventilation System for Deuterium-Tritium Fusion Plant 氘-氚聚变装置氚约束通风系统概念设计与分析

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2025-09-11 DOI: 10.1007/s10894-025-00511-5

Jing Huang, Bin Guo, Fukun Liu, Gang Wu

{"title":"Conceptual Design and Analysis of Tritium Confinement Ventilation System for Deuterium-Tritium Fusion Plant","authors":"Jing Huang, Bin Guo, Fukun Liu, Gang Wu","doi":"10.1007/s10894-025-00511-5","DOIUrl":"10.1007/s10894-025-00511-5","url":null,"abstract":"<div><p>The negative pressure ventilation system, serving as a critical subsystem within the tritium safety confinement system of the compact fusion energy experimental, is responsible for maintaining dynamic confinement functionality over the C2 and C3 confinement subzones during normal operational conditions, thereby restricting the leakage and dispersion of radioactive materials. Consequently, rational and reliable design of the tritium confinement negative pressure ventilation system is of paramount importance. Key aspects of the system process design include determining pipeline network dimensions and evaluating thermal-hydraulic characteristics. In this study, the system design requirements were established in accordance with the international standard ISO 16646:2024 and the operational specifications of the device. This involved calculating the system airflow capacity and proposing a preliminary process design scheme for the negative pressure ventilation system. A thermal-hydraulic computational model for the initial system configuration was developed using the fluid simulation software AFT Arrow. Steady-state simulations were conducted to predict the thermal-hydraulic behavior of the pipeline network under maximum ventilation load conditions, enabling the determination of critical equipment selection parameters. The findings of this study will lay the groundwork for subsequent research on negative pressure ventilation systems in compact fusion energy applications, providing essential technical insights for optimizing system performance and ensuring compliance with radiological safety standards.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"44 2","pages":""},"PeriodicalIF":2.1,"publicationDate":"2025-09-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145037064","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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

Machine Learning Applications Enabling Fusion Energy: Recent Developments 实现聚变能源的机器学习应用：最新发展

IF 2.1 4区工程技术

Journal of Fusion Energy Pub Date : 2025-09-03 DOI: 10.1007/s10894-025-00509-z

Cristina Rea

引用次数: 0