Fusion Engineering and Design最新文献

{"title":"Advances in magnet and shielding designs for fusion and high energy physics applications","authors":"L. Giannini ,&nbsp;C. Luongo ,&nbsp;L. Bottura ,&nbsp;B. Bordini ,&nbsp;A. Lechner ,&nbsp;A. Kolehmainen ,&nbsp;D. Leichtle ,&nbsp;A. Portone ,&nbsp;P. Testoni ,&nbsp;J. Bajari ,&nbsp;M. Siccinio ,&nbsp;C. Bachmann ,&nbsp;G. Federici","doi":"10.1016/j.fusengdes.2025.114899","DOIUrl":"10.1016/j.fusengdes.2025.114899","url":null,"abstract":"<div><div>This paper introduces the work scope of a collaboration among EUROfusion, CERN, and F4E to create models and design tools applicable both for fusion devices and muon accelerator magnets. The study described here is motivated by the commonality in challenges to design magnets and radiation shields applicable to compact fusion machines to serve as neutron source, and future high-energy physics experiments such as the muon collider or high intensity neutrino factories.</div><div>Both applications present design challenges revolving around the trade-off between the need for very high fields over a relatively large free bore, while keeping the coils sufficiently far away and properly shielded from radiation to limit heat load and damage to materials. The present focus is on creating design models and tools for superconducting solenoids built exclusively with high-temperature superconductors (HTS), or in a hybrid configuration with low-temperature superconductors (LTS).</div><div>We use the pinch solenoid magnets for a mirror fusion machine as a case study. The magnetic field requirements and configuration, material limits, structural constraints, and shielding properties are considered while using an optimization model to scan and systematically size the coil/shield combination. The investigation involves conductor selection, mechanical analyses, and cooling schemes. Moreover, we examine the optimization of magnet stability in operation, surveying radiation-shielding materials and innovative shielding concepts. The similarities in design challenges between fusion devices and accelerator magnets are highlighted.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"214 ","pages":"Article 114899"},"PeriodicalIF":1.9,"publicationDate":"2025-02-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143511204","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":"Distributed editing of experiment programs at Wendelstein 7-X","authors":"Anett Spring,&nbsp;Heike Riemann,&nbsp;Marc Lewerentz,&nbsp;W7-X Team","doi":"10.1016/j.fusengdes.2025.114880","DOIUrl":"10.1016/j.fusengdes.2025.114880","url":null,"abstract":"<div><div>Configuring experiment programs at complex fusion experimental facilities such as Wendelstein 7-X is a challenge: the amount of parameters, the growing number of components, the required specialized knowledge of technical systems and diagnostics, the complex timing – all this demands an integrated solution for experiment leaders, engineers, and physicists.With the growing number of integrated components, the W7-X experiment program editor Xedit was extended to cope with <em>TaskLinks</em>: allowing externally configured program parts of individual components to be linked into the planned sequence of the central experiment program. The preparation of the specific <em>Tasks</em> is done by the component owners using a local Xedit instance – in the same way, as the users are already familiar with from the creation of local programs for commissioning or calibration runs. Centrally, as with all integrated components, the linked components’ <em>Tasks</em> are then visualized and all parameters are checked for limit violations or other pre-defined rules before saving the complete planned program ready for execution.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"214 ","pages":"Article 114880"},"PeriodicalIF":1.9,"publicationDate":"2025-02-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143510516","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":"Dose assessment for radioactive products distributed on liquid Li loops of fusion neutron sources","authors":"Shunsuke Kenjo,&nbsp;Makoto Oyaidzu,&nbsp;Saerom Kwon,&nbsp;Kentaro Ochiai,&nbsp;Satoshi Sato","doi":"10.1016/j.fusengdes.2025.114901","DOIUrl":"10.1016/j.fusengdes.2025.114901","url":null,"abstract":"<div><div>Radiation dose rates around liquid Li loops in International Fusion Materials Irradiation Facility (IFMIF)-like fusion neutron sources, such as A-FNS, increase because of the radionuclides produced by high-energy deuterons and neutrons. This study assesses radiation dose rates around the pipe, heat exchanger (HX), and electromagnetic pump (EMP) of a liquid Li loop using the Monte Carlo code MCNP6.2 and the photon data library mcplib84 to advance the development of maintenance strategies. The radiation sources include not only major nuclides (tritium and Be-7) reported in previous studies but also other radionuclides that have not been well investigated thus far. The calculation results suggest that hands-on maintenance of Li pipes can be performed after the Li drain. However, accesses HX and EMP are limited because of nuclides such as Y-88, which are produced from impurities in liquid Li, even when Be-7 is trapped in Cold Trap.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"214 ","pages":"Article 114901"},"PeriodicalIF":1.9,"publicationDate":"2025-02-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143510515","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":"MOOSE-based Tritium Migration Analysis Program, Version 8 (TMAP8) for advanced open-source tritium transport and fuel cycle modeling","authors":"Pierre-Clément A. Simon ,&nbsp;Casey T. Icenhour ,&nbsp;Gyanender Singh ,&nbsp;Alexander D. Lindsay ,&nbsp;Chaitanya Bhave ,&nbsp;Lin Yang ,&nbsp;Adriaan Riet ,&nbsp;Yifeng Che ,&nbsp;Paul Humrickhouse ,&nbsp;Pattrick Calderoni ,&nbsp;Masashi Shimada","doi":"10.1016/j.fusengdes.2025.114874","DOIUrl":"10.1016/j.fusengdes.2025.114874","url":null,"abstract":"<div><div>Tritium management is critical for the safety, sustainability, and economics of fusion energy systems, and advanced and reliable modeling tools help accelerate the development of tritium technologies. This paper presents the Tritium Migration Analysis Program, Version 8 (TMAP8), an open-source, MOOSE-based application developed to provide state-of-the-art tritium transport and fuel cycle modeling capabilities. TMAP8 aims to expand the capabilities of previous versions (i.e., TMAP4 and TMAP7) by leveraging modern computational techniques, ensuring high software quality assurance standards (key to building trust), and enabling multispecies, multiscale, and multiphysics simulations for integrated tritium transport modeling in complex geometries. This paper outlines TMAP8’s scope and rigorous development practices, emphasizing its transparency, accessibility, modularity, and reliability. We present the current suite of verification and validation cases based on those from TMAP4, demonstrating TMAP8’s accuracy and reliability against analytical solutions and experimental data. Additionally, the paper showcases TMAP8’s integrated fuel cycle modeling capabilities, highlighting its applicability at various scales and levels. The TMAP8 code and documentation are openly available, promoting collaborative development and widespread adoption within the fusion community. Future work will soon expand TMAP8’s verification and validation suite to include those from TMAP7 and other recent experimental studies for validation.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"214 ","pages":"Article 114874"},"PeriodicalIF":1.9,"publicationDate":"2025-02-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143510514","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":"Ventilated immersive suit for interactive & operative nuclear operations (VISION) applied to ITER test blanket modules","authors":"Stéphane Gazzotti ,&nbsp;Tanguy Sève ,&nbsp;Killian Huc ,&nbsp;Simon Demolin ,&nbsp;Chiara Di Paolo ,&nbsp;Vincent Weistroffer ,&nbsp;Claude Andriot ,&nbsp;Jean-Pierre Friconneau ,&nbsp;Jean-Pierre Martins","doi":"10.1016/j.fusengdes.2025.114889","DOIUrl":"10.1016/j.fusengdes.2025.114889","url":null,"abstract":"<div><div>CEA is conducting feasibility studies on Test Blanket Modules (TBM) replacement operations in ITER Port Cells, employing an innovative validation concept through simulations using Extended Reality (XR). Collaborating with MATISEC (company specialized in production of security equipment for hostile environments), this study addresses nuclear engineering with motivation to assess in early design phase the use of Personnel Protection Equipment. This study also focusses on the new Immersive Air-Fed Suit (AFS) tailored for XR simulations to prepare hands on operations in hazardous environment. To address the increased operator's workload and fatigue associated with AFS use, the concept uses a modified MATISEC MRV5 prototype. It incorporates internal and external sensors, inertial units, optical and posture sensors, instrumented gloves and depth cameras. Integrated with the XDE physics engine(interactive physics engine) from CEA LIST (Laboratory for Integration of Systems and Technology), these components form an interactive simulation enabling to perform technical tasks in a virtual environment. The virtual simulation replicates human behavior and accurately simulates assembling/disassembling insulation, flanges or cutting/welding pipes operations with scale one tangible tools. The augmented suit and virtual reality resources allow the exploration of intervention scenarios, aligning with French labor regulations limiting AFS use due to operator fatigue. This technology is implemented in the Virtual Integration Platform for Engineering &amp; Remote handling (VIPER) at CEA IRFM (Institute for Magnetic Fusion Research) in Cadarache. This innovative concept allows to check Human Factors requirements early in the design process, integrating advanced monitoring systems for real-time data. Applied to the Pipe Forest accessibility use case for TBM replacement in port cells #16 and #18, it streamlines the design and integration of complex components in constrained working environments minimizing worker exposure in line with the ALARA principle of radiation safety (As Low As Reasonably Achievable). The immersive simulation capabilities position the project as a valuable tool for industries prioritizing worker safety, particularly in nuclear facilities. This innovation extends its applicability to various fields, ranging from engineering analysis to worker training, offering a novel approach to integrate human factors into technical studies.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"214 ","pages":"Article 114889"},"PeriodicalIF":1.9,"publicationDate":"2025-02-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143511093","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":"Stellaris: A high-field quasi-isodynamic stellarator for a prototypical fusion power plant","authors":"J. Lion ,&nbsp;J.-C. Anglès ,&nbsp;L. Bonauer ,&nbsp;A. Bañón Navarro ,&nbsp;S.A. Cadena Ceron ,&nbsp;R. Davies ,&nbsp;M. Drevlak ,&nbsp;N. Foppiani ,&nbsp;J. Geiger ,&nbsp;A. Goodman ,&nbsp;W. Guo ,&nbsp;E. Guiraud ,&nbsp;F. Hernández ,&nbsp;S. Henneberg ,&nbsp;R. Herrero ,&nbsp;C. Hintze ,&nbsp;H. Höchter ,&nbsp;J. Jelonnek ,&nbsp;F. Jenko ,&nbsp;R. Jorge ,&nbsp;M. Zheng","doi":"10.1016/j.fusengdes.2025.114868","DOIUrl":"10.1016/j.fusengdes.2025.114868","url":null,"abstract":"<div><div>Magnetic confinement fusion research has so far prioritized the tokamak concept, which presents greater design simplicity at the cost of control complexity in comparison to stellarators. Recent progress on high-temperature superconductors (HTS) has enabled a new generation of high-field tokamaks with more compact designs. However, the presence of large magnetic fields implies correspondingly large plasma currents, raising challenges regarding plasma stability. Meanwhile, key milestones have been reached in recent years by Wendelstein 7-X, the world’s most advanced stellarator, and breakthroughs in computational optimization have enabled radically improved stellarator designs. In this paper, we present a concept for a new class of quasi-isodynamic (QI) stellarators leveraging HTS technology to overcome well-known challenges of a tokamak. This class of QI-HTS stellarators, labeled Stellaris, is shown to achieve an extensive set of desirable properties for reactor candidates simultaneously for the first time, offering a compelling path toward commercially viable fusion energy. We summarize a comprehensive reactor study, ranging from optimization of the plasma confinement region to first wall cooling, divertor considerations, blanket design, magnet quench safety, support structures, and remote maintenance solutions. Our results demonstrate that a coherent set of trade-offs between physics and engineering constraints can lead to a compelling stellarator design, suited for power plant applications. We anticipate that this work will motivate greater focus on QI stellarators, in both publicly and privately funded research.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"214 ","pages":"Article 114868"},"PeriodicalIF":1.9,"publicationDate":"2025-02-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143609741","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":"Design and evaluation of an advanced robotic bolting tool applied to IFMIF-DONES","authors":"V. Redondo,&nbsp;N. Barbosa,&nbsp;P. Espinosa,&nbsp;M. Ferre","doi":"10.1016/j.fusengdes.2025.114877","DOIUrl":"10.1016/j.fusengdes.2025.114877","url":null,"abstract":"<div><div>Operating bolts is a key aspect in most maintenance procedures. This work focuses on IFMIF-DONES (The International Fusion Materials Irradiation Facility - DEMO Oriented Neutron Source being built in Granada), where the radiation conditions require the use of robots for the maintenance procedures and some bolts need to be tightened at high torques to warrant proper functioning during operation.</div><div>The design presented in this contribution consists of a servo motor, a metallic structure, a socket wrench (as the physical interface with the bolt), a spring and a load cell between the motor and the socket wrench (to inform about the fitting of the bolt), and two slots for pins that will act both as reaction torque limiters and guiding system.</div><div>For the evaluation of the tool, a set of validation tests has been carried out in a mock-up developed in the laboratory. It consists of different screws and pins placed in a horizontal plane reachable by the robotic arm. During the experiments, the forces and torques in the joints of the robot are monitored, their analysis is presented in this work.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"214 ","pages":"Article 114877"},"PeriodicalIF":1.9,"publicationDate":"2025-02-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143488598","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":"Kinetic analysis of tritium release from irradiated biphasic lithium ceramics Li4SiO4-Li2TiO3 with different phase ratios","authors":"S. Askerbekov ,&nbsp;Y. Chikhray ,&nbsp;T. Kulsartov ,&nbsp;A. Akhanov ,&nbsp;A. Shaimerdenov ,&nbsp;M. Aitkulov ,&nbsp;Zh. Bugybay ,&nbsp;I. Kenzhina ,&nbsp;Sh. Gizatulin ,&nbsp;R. Knitter ,&nbsp;J. Leys","doi":"10.1016/j.fusengdes.2025.114873","DOIUrl":"10.1016/j.fusengdes.2025.114873","url":null,"abstract":"<div><div>This paper analyzes the kinetics of tritium release from biphasic Li₂TiO₃/Li₄SiO₄ lithium ceramics using thermal desorption spectroscopy after neutron irradiation at the WWR-K reactor. Samples with different Li₂TiO₃ contents (25 mol% and 35 mol%) in the Li₄SiO₄ main phase, fabricated by the KALOS process at the Karlsruhe Institute of Technology, were irradiated at a low temperature and a thermal neutron flux of 2 × 10¹³ n/(cm²·s) during 21.5 effective full power days until accumulating a fluence of 3.7 × 10¹⁹ n/cm².</div><div>The experimental results confirm the significant influence of phase composition on the processes of tritium release. The analysis allowed us to develop a reasonable mechanism of tritium release during linear heating up to 1173 K.</div><div>Tritium was found to be uniformly distributed throughout the ceramic volume and its release is closely related to the microstructural characteristics of the material. Key factors affecting the process include the presence and distribution of traps and defects interacting with the external surface of the sample. The release process of these traps is determined by the transport of tritium to the boundaries, followed by desorption mainly in the form of HT molecules and has three main peaks.</div><div>Samples with 25 mol% Li₂TiO₃ showed high activation energy values, indicating the presence of more stable traps and complex tritium transport pathways. With an increased Li₂TiO₃ content of 35 mol%, a decrease in activation energy was observed, indicating a faster desorption process, probably due to changes in microstructure or the number of active defects facilitating tritium release at lower temperatures.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"214 ","pages":"Article 114873"},"PeriodicalIF":1.9,"publicationDate":"2025-02-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143488597","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":"EU-DEMO limiters design integration issues and constraints driven by remote maintenance challenges","authors":"M.L. Richiusa ,&nbsp;J. Lyytinen ,&nbsp;A. Sinha ,&nbsp;G.A. Spagnuolo","doi":"10.1016/j.fusengdes.2025.114890","DOIUrl":"10.1016/j.fusengdes.2025.114890","url":null,"abstract":"<div><div>The Limiter (LIM) System of a port-based tokamak like the EU-DEMO encompasses different kinds of limiters for first wall protection purposes. Although the limiters’ position and poloidal surface extension are driven by plasma physics inputs and verified under charged particle heat loads by means of field line tracing, they should also be designed to be easily and independently handled through vacuum vessel ports. Among the four identified types of limiters, four Outboard Lower Limiters (OLL) and four Inboard Midplane Limiters (IML) – when the inboard protection is conceived as a standalone component – do not have dedicated ports for their maintenance, as no vacuum vessel openings are foreseen in the lower outboard first wall, precisely behind the OLL, and behind the IML in the inboard equatorial first wall. On one hand, limiters should be designed to protect the first wall against energy depositions following plasma disruptive events; on the other side, though, it is important to ensure that the protection system is designed under realistic constraints to be easily handled and realistically maintained. Therefore, integration and remote maintenance requirements and needs become an important factor affecting both the OLL and IML integrated engineering design, for which a dedicated handling strategy becomes one of the main drivers, together with physics needs.</div><div>The paper presents the rationale followed for addressing the integration issues which drive the design of limiters with no dedicated ports behind them, and the remote maintenance strategy supporting their design concept. The definition of the handling strategy will help identify robust design drivers that apply to the entire lifecycle of the OLL and IML and improve the feasibility of achieving a practicable design solution compatible with its remote maintenance at every stage.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"214 ","pages":"Article 114890"},"PeriodicalIF":1.9,"publicationDate":"2025-02-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143464511","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":"Feasibility study for cryogenic pellets production with pure gaseous helium cooling for ITER Disruption Mitigation System","authors":"T. Boujet,&nbsp;A. Attard,&nbsp;P. Bonnay,&nbsp;N. Luchier,&nbsp;J. Manzagol,&nbsp;F. Millet","doi":"10.1016/j.fusengdes.2025.114891","DOIUrl":"10.1016/j.fusengdes.2025.114891","url":null,"abstract":"<div><div>CEA/DSBT designed and operated a test bench for pellet injection cooled by liquid helium (LHe) to study the production and the acceleration of large cryogenic pellets for the ITER Disruption Mitigation System (DMS). Large (ø28.5 mm) protium (¹H) pellets of ∼3 g were successfully formed in 20 mins and then accelerated above 500 m/s. However, LHe cooling is not distributed by ITER cryoplant and shall be replaced by supercritical helium (SHe) cooling.</div><div>To evaluate the feasibility of using SHe as a coolant, the CEA/DSBT test bench is modified to operate with pure gaseous helium cooling (GHe at 1.25 bara), which behave more like SHe than LHe used up to now. The main difference between GHe and LHe cooling is the temperature variation induced by the thermal heat removal. In LHe cooling, the heat exchange occurs mainly at a constant temperature due to the liquid to gas phase change (latent heat). In the opposite, in GHe cooling, only the specific heat is available for heat removal, resulting in a cooling temperature increase. Excessive temperature rise is a drawback to the goal of reduced pellet formation times, where the cell temperature must be kept as low as possible.</div><div>This paper presents a comparison of LHe and GHe cooling using the current ∅28.5 mm <em>in-situ</em> condensation cell and highlights some pellet formation key parameters such as the species (pure protium and pure neon or protium/neon mix) and the cold cell temperature. The protium pellets were the most extensively compared, as they are the fastest to produce and the most characterised with LHe cooling. All other types of DMS pellets were also briefly studied. The GHe cooling results show similar pellet formation durations, pellet aspects and speeds as those with LHe cooling. This proof of principle using gaseous cooling is a significant step in the design study of the ITER-DMS cold cell using SHe cooling.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"214 ","pages":"Article 114891"},"PeriodicalIF":1.9,"publicationDate":"2025-02-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143453370","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}