Fusion Engineering and Design最新文献

{"title":"Final design of outer poloidal field coils for COMPASS Upgrade","authors":"P. Hacek ,&nbsp;P. Junek ,&nbsp;J. Krbec ,&nbsp;O. Stukavec ,&nbsp;M. Balaszova ,&nbsp;V. Balner ,&nbsp;P. Barton ,&nbsp;J. Blocki ,&nbsp;O. Bogar ,&nbsp;P. Bohm ,&nbsp;J. Burant ,&nbsp;G. Cunningham ,&nbsp;O. Ficker ,&nbsp;J. Havlicek ,&nbsp;A. Havranek ,&nbsp;M. Hron ,&nbsp;J. Hromadka ,&nbsp;P. Hynek ,&nbsp;M. Imrisek ,&nbsp;F. Jaulmes ,&nbsp;J. Zelda","doi":"10.1016/j.fusengdes.2025.114986","DOIUrl":"10.1016/j.fusengdes.2025.114986","url":null,"abstract":"<div><div>The paper aims to provide an overview of the final design of the outer poloidal field coils system for COMPASS Upgrade. Due to a relatively unique combination of design features of the new device (placement in high toroidal magnetic field, copper coils sub-cooled to liquid nitrogen temperature, hot vacuum vessel operation), the poloidal field coils design faced several interesting engineering challenges. Most notably high electromagnetic stress in the coil conductor, compatibility of the insulation to thermal and mechanical stress and design of coil supports with given spatial constraints while able to accommodate coil movements and withstand considerable mechanical stress. The paper describes solution to these challenges together with underlying analyses and mechanical tests.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114986"},"PeriodicalIF":1.9,"publicationDate":"2025-03-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143716181","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}

{"title":"Burn control strategies using plasma elongation in DEMO","authors":"Luigi Emanuel di Grazia ,&nbsp;Emiliano Fable ,&nbsp;Massimiliano Mattei ,&nbsp;Mattia Siccinio ,&nbsp;Francesco Maviglia ,&nbsp;Hartmut Zohm","doi":"10.1016/j.fusengdes.2025.114976","DOIUrl":"10.1016/j.fusengdes.2025.114976","url":null,"abstract":"<div><div>In this paper, a feedback control algorithm to reduce the DEMO fusion power fluctuations due to the presence of possible disturbances and unpredicted events is proposed. Fluctuations can be limited controlling temperature and densities of the different plasma species by means of a set of actuators like electron cyclotron resonance heating, fuelling rate modulation and/or impurity injection. However, electron cyclotron resonance heating is expensive in terms of power cost and impurities are difficult to control because it is hard to remove them from the core. A possible alternative is to use plasma shape as a virtual actuator and in particular elongation through plasma shape magnetic control. This work exploits the possibility to use elongation modifications in a coordinated way with electron cyclotron resonance heating power, and electron density, for real time control. The integrated control scheme implements a supervised control allocation strategy and accounts for constraints coming from actuator limits as maximum elongation, maximum ECRH power or maximum electron density, but also on other key plasma parameters like plasma safety factor and Greenwald density limit. Numerical results of the overall control scheme to compensate the effect of uncontrolled argon injection and tungsten flake event are obtained within the DEMO flight simulator based on Fenix.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114976"},"PeriodicalIF":1.9,"publicationDate":"2025-03-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143705473","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}

{"title":"Intermediate thermomechanical analysis and optimization of the ITER Upper port mounted bolometer camera","authors":"Z. Wang ,&nbsp;N. Jaksic ,&nbsp;H. Meister ,&nbsp;A. Pataki ,&nbsp;M.A. Villarejo","doi":"10.1016/j.fusengdes.2025.114997","DOIUrl":"10.1016/j.fusengdes.2025.114997","url":null,"abstract":"<div><div>The bolometer diagnostic system in the ITER monitors the plasma radiation from multiple positions inside the vacuum vessel for a complete measurement. The cameras are named according to their locations, like the port plug (PP) cameras and the divertor ones. This paper is about the cameras in the upper port plug. Because of the severe working environment, especially the high neutron and gamma heating power and the electromagnetic (EM) forces during the plasma disruptions, the camera structure has two functions: 1) in the thermal point of view, the heat deposited on the sensors needs to be effectively exhausted; 2) in the structural point of view, the camera must keep in position under various of mechanical loads.</div><div>Due to limited space, passive cooling methodology is chosen, in which the camera housing conducts the heat to the Diagnostic Shield Module (DSM), so a thick metallic housing is helpful in both neutron shielding and heat conduction. However, during disruptions these thick walls will induce strong eddy currents and cause high EM forces. Additionally, the mechanical constraints, in order to resist these dynamic EM loads, generate high thermal loads on the camera. Therefore, the design optimization must carefully find a balance among all relevant issues.</div><div>The port plug design has been finished and provides the attachment boundary conditions for the camera analysis, but the information is not detailed enough, then the camera finite element (FE) model is integrated into the existing PP FE model for a seamless interface. The methodology and intermediate results of the thermomechanical analysis are presented, and the experience gained are also applicable for similarly attached in-vessel components.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114997"},"PeriodicalIF":1.9,"publicationDate":"2025-03-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143716293","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}

{"title":"Role of additional grids on ion flow dynamics of an inertial electrostatic confinement fusion neutron source","authors":"S.R. Mohanty ,&nbsp;L. Saikia ,&nbsp;N. Bharali ,&nbsp;S. Kalita","doi":"10.1016/j.fusengdes.2025.114985","DOIUrl":"10.1016/j.fusengdes.2025.114985","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 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.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114985"},"PeriodicalIF":1.9,"publicationDate":"2025-03-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143705447","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}

{"title":"Petri net modelling – A remote maintenance simulation approach for fusion remote maintenance equipment concepts assessment","authors":"Gabriele Benzoni ,&nbsp;Van-Dung Truong ,&nbsp;William Brace ,&nbsp;Antonio Cammi ,&nbsp;Carolina Introini ,&nbsp;Gioacchino Miccichè ,&nbsp;Siuko Mikko ,&nbsp;Claudio Tripodo","doi":"10.1016/j.fusengdes.2025.114996","DOIUrl":"10.1016/j.fusengdes.2025.114996","url":null,"abstract":"<div><div>The modelling of the EU-DEMO fusion reactor maintenance process, which allows the accurate design of remote maintenance equipment (RME), requires a shift in approach due to the frequent modification of the reactor architecture design. This paper presents a novel method based on the use of Petri Nets (PN) to model the maintenance strategy, simulating the maintenance process for RME deployment in the DEMO In-Bioshield area. The approach begins with defining the maintenance procedure based on system requirements and identifying the key processes. Then, the structure of the PN is defined using transitions and places where the tokens represent the RME. The PN model is developed using Modelica, a multiphysics and multidomain simulation language that uses an object-oriented approach to models. A case study of the remote maintenance simulation in the basement area of the In-Bioshield demonstrated that the resulting PN models correctly describe the maintenance process, allowing the analysis of main design drivers for RME concept variants and their ranking by adjusting the concept's technical specifications as simulation inputs. In particular, the results identified the most critical processes and their influence on the overall DEMO maintenance while highlighting the possible RME design.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114996"},"PeriodicalIF":1.9,"publicationDate":"2025-03-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143705446","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}

{"title":"Real-time cognitive load monitoring of fusion remote maintenance system operators by electroencephalogram","authors":"Qiwei Xue ,&nbsp;Danil Vodolazskii ,&nbsp;Huapeng Wu ,&nbsp;Yuntao Song ,&nbsp;Milella Nando","doi":"10.1016/j.fusengdes.2025.114920","DOIUrl":"10.1016/j.fusengdes.2025.114920","url":null,"abstract":"<div><div>In tokamak maintenance, components near the plasma are exposed to radiation and hazardous materials, necessitating remote handling to protect operators from direct exposure and ensure operational integrity. Efficient and reliable human–machine collaboration in these high-stakes environments is essential, as operator errors are intolerable and environmental feedback is limited. This study proposes an electroencephalography (EEG)-based workload classification algorithm for real-time monitoring of remote handling (RH) operators, aiming to enhance operational safety and efficiency by assessing operator workload and facilitating timely adjustments. EEG signals undergo denoising through independent component analysis (ICA) and bandpass filtering to remove artifacts and improve signal quality. Feature extraction and selection identify the top EEG features most indicative of workload, including power spectral density (PSD) metrics and fractal dimensions, which serve as inputs to an optimized artificial neural network (ANN) model. The ANN model, trained on both the STEW dataset and custom data, achieves 82% classification accuracy, generalizing well across varying cognitive load levels in multi-task settings. The model’s performance metrics, including validation accuracy and confusion matrix results, confirm its reliability in discerning workload levels. The findings demonstrate the utility f EEG-based workload monitoring in RH environments, providing a foundation for future improvements in human–machine interaction and operational safety. This research contributes to the advancement of RH systems by enabling real-time workload adjustments based on operator status.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114920"},"PeriodicalIF":1.9,"publicationDate":"2025-03-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143705445","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}

{"title":"An open source fusion machine agnostic standard for the exchange and processing of infrared videos and video annotations","authors":"Erwan Grelier,&nbsp;Victor Moncada,&nbsp;Raphael Mitteau,&nbsp;West Team","doi":"10.1016/j.fusengdes.2025.114934","DOIUrl":"10.1016/j.fusengdes.2025.114934","url":null,"abstract":"<div><div>The exploitation of the infrared diagnostics of long pulse fusion machines requires sophisticated and automated intelligent models for effective machine protection. To achieve this, it is imperative to train these models on high-quality and diverse datasets derived from different fusion machines, such as WEST and W7-X, as well as from simulations for future projects such as ITER. To address the need for a standardized approach to exchange infrared videos of the inside of vessels and video annotations within these scenes, we propose two open-source standards accessible on GitHub. These standards aim to facilitate the sharing and use of data for the training of machine protection models across various fusion machines. The proposed standards address the challenge of creating a common platform for sharing infrared video data as well as video annotations, ensuring compatibility among different machines. This initiative serves as a pivotal step towards establishing a unified framework for collaborative research in fusion research and development. The ThermaVIP software platform uses these standards to read infrared movies in the standardized format, read and write annotations to the proposed JSON standard, and read from and write to a MYSQL database. As a demonstration, a cross-machine database was deployed on the EUROfusion gateway. This database serves as an initial repository hosting infrared videos and annotations from both WEST and W7-X, laying the foundation for a comprehensive and diverse dataset essential for training intelligent models. This paper presents the proposed open source standards and the first deployment of a cross-machine database. This collaborative and standardized approach is vital to ensure the robustness and generalization of future protection models.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114934"},"PeriodicalIF":1.9,"publicationDate":"2025-03-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143705444","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}

{"title":"Simulated installation of a breeding blanket segment in a two-port mover context","authors":"Petri Tikka,&nbsp;Hannu Saarinen,&nbsp;Hannu Martikainen,&nbsp;William Brace,&nbsp;Janne Lyytinen","doi":"10.1016/j.fusengdes.2025.114989","DOIUrl":"10.1016/j.fusengdes.2025.114989","url":null,"abstract":"<div><div>The abstract relates to work undertaken on the Two Port Mover (TPM) Remote Maintenance (RM) concept in European DEMO. The focus of the study was to assess the operational procedures for installing the Blanket Leg Unit and Lower Port Winch of the Two-Port Mover. In addition, alternative means for constraining the rotations of the breeding blanket during the removal and installation process of blankets were studied.</div><div>The Two-Port Mover was tested in a dynamic simulation. The assessment process was carried out by using a Unity game-engine in a combination of AGX Dynamics for Unity plugin. The scope was to utilize virtual prototyping to visualize how the cabling of the studied Lower Port winch approach would interact within the Vacuum Vessel sector. Dynamic physics enables the cabling and the interface plate to collide with the surrounding environment and proper adjustments to the performed procedures can be validated already in the early stages of the design process. The final connection with the interface plate and the winches is performed by a remotely operated manipulator in a virtual environment. In the context of this simulation, the manipulator was controlled with a haptic device. This ensured precise control of the connection process, but also demonstrated how the cables would interact while operating the manipulator. Thus, influencing initial TPM design maturity.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114989"},"PeriodicalIF":1.9,"publicationDate":"2025-03-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685806","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}

{"title":"Study on the new manufacture of ITER vacuum vessel thermal shield","authors":"Kwanwoo Nam ,&nbsp;Dongkwon Kang ,&nbsp;Moohyun You ,&nbsp;Myeongjun Kim ,&nbsp;Sang-chul Kim ,&nbsp;Chang Hyun Noh ,&nbsp;Hyunsoo Kim ,&nbsp;Kijung Jung","doi":"10.1016/j.fusengdes.2025.114964","DOIUrl":"10.1016/j.fusengdes.2025.114964","url":null,"abstract":"<div><div>This paper describes the preparation and the status for the manufacturing of the new Vacuum Vessel Thermal Shield (VVTS) for ITER machine. As the delivered VVTS had the corrosion problem at the pipe weld, the VVTS was determined to be repaired and re-manufactured. The new VVTS has no silver coating and its pipe material is changed to exclude corrosion cracking at the cooling pipe. Roughness of the panel surface is reduced to have lower emissivity without silver coating. Several technical efforts to improve the pipe welding are presented in this paper. Stitch weld between the pipe and the panel is carefully tested with various specimens as Pre-Production Sample (PPS). Tack weld position is intended not to be overlapped with the stitch weld. Back shielding at the opposite side of the stitch weld is also applied to minimize the oxidation. Down-slope current of the welding machine is optimized for the pipe stitch weld. Heat correction method after the welding is investigated to confirm the soundness of the weld joint and the base metal. Impact test and corrosion test are performed for the specimens after the heat correction. All the manufactured VVTS panels are subjected to be leak-tested in a huge vacuum chamber with the pressurized cooling pipe with helium gas. Delivery status of the re-manufactured VVTS panels is presented and the anticipated manufacturing schedule are introduced in this paper.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114964"},"PeriodicalIF":1.9,"publicationDate":"2025-03-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143697386","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}

{"title":"Study on vacuum outgassing characteristics of hot-pressing Boron Carbide(B4C) for ITER equatorial port","authors":"Xiaoyue Hu ,&nbsp;Qingsheng Hu ,&nbsp;Jiahong Li ,&nbsp;Chuansen Yang ,&nbsp;Junru Chen ,&nbsp;Changjun Xu ,&nbsp;Haiyang Xu ,&nbsp;Juan Jiang ,&nbsp;Junyu Zhao","doi":"10.1016/j.fusengdes.2025.114974","DOIUrl":"10.1016/j.fusengdes.2025.114974","url":null,"abstract":"<div><div>There are approximately 33,000 blocks of boron carbide (B₄C) employed as the main neutron shielding material in the International Thermonuclear Experimental Reactor (ITER) Equatorial Port#12 Integration System (EQ#12) in-vessel components. The gases desorbed from the surface and diffused from B₄C internally can adversely affect the vacuum environment of ITER device. Therefore, it is crucial to study its vacuum outgassing characteristics for ensuring the vacuum performance of the ITER device. In this paper, B₄C block with an average density of (2.50±0.01) g/cm³ were prepared via the hot-pressing process. Utilizing a self-developed outgassing rate testing equipment, the outgassing characteristics of two kinds of B₄C samples (non-prebaked and prebaked at 900 °C) were studied by switching between two pumping paths method. Results indicate that after the ITER thermal cycle, the outgassing rate per unit area of all B₄C samples were as low as the order of 10^–9 Pa·m³·s⁻¹·m^-2, the H₂O content is significantly decreased, with H₂ constituting the majority of the outgassing composition, and the majority impurities released were CO and CO₂. Furthermore, samples pre-baked at 900 °C exhibit lower impurity levels, with the outgassing rate per unit area of impurity (CO) being less than 10^–10 Pa·m³·s⁻¹·m^-2, implying that the high-temperature pre-baking treatment facilitates the decomposition of organic molecules and enhances the diffusion of internal gases, thereby further reducing in the outgassing rate of B₄C. This study demonstrates that B₄C treated with rigorous processes can serve as main shielding material in the vacuum chamber of ITER devices, providing valuable reference for the selection of shielding material of future fusion reactors.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114974"},"PeriodicalIF":1.9,"publicationDate":"2025-03-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143696887","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}