Fusion Engineering and Design最新文献

{"title":"Simulation and experiment investigation of lamination W structure for suppressing surface blistering","authors":"Pengcheng Guo ,&nbsp;Hanfeng Song ,&nbsp;Yunhui Tang ,&nbsp;Bing Wang ,&nbsp;Bo Wang","doi":"10.1016/j.fusengdes.2025.115315","DOIUrl":"10.1016/j.fusengdes.2025.115315","url":null,"abstract":"<div><div>Tungsten (W) is a prime plasma facing materials (PFMs) in fusion reactors, facing deuterium (D) induced blistering and retention challenges. The foil gaps are the clearance between adjacent W monoblocks along the poloidal axis. They reduce D retention by acting as “gas release channels” (GRCs). By reducing monoblock thickness, we enhance GRCs effect to suppress blistering. Finite element simulations under steady-state with a flux of <span><math><mrow><mi>ψ</mi><mo>=</mo><mn>1</mn><mo>×</mo><msup><mrow><mn>10</mn></mrow><mn>24</mn></msup></mrow></math></span>D <em>m</em>⁻²s⁻¹ modeled D transport in W monoblocks of varying thicknesses, each with a fixed-width foil gap. We accounted for the lateral escape of D into the gaps, where they recombine to form deuterium gas(D₂) released from the top. Results show that thinner monoblock (3μm) reduce near surface D retention by one order magnitude compared to 100μm W, while lowering D₂ pressure in GRCs through enhanced lateral escape. To validate this approach, laminated W samples with progressively thinned W foils were fabricated and subjected to D irradiation. Experiment demonstrates three findings: (1) Blister size and density increase with fluence. (2) Thickness reduction suppresses blistering via intensified lateral escape effect (LEE), especially below 10μm. (3) Vertical cavities in W foils form GRCs suppress blistering, achieving 8.48 % lower surface blister coverage than W bulk at <span><math><mrow><mn>5</mn><mo>×</mo><msup><mrow><mn>10</mn></mrow><mn>25</mn></msup></mrow></math></span>D m⁻² fluence. This thickness-dependent suppression mechanism correlates with GRCs density optimization, where increased diffusion paths promote D recombination and release. Our combined simulation-experimental approach confirms effectiveness of laminated structure. This work presents a potential approach to suppress blistering in PFMs by enhancing the GRCs effect through reduced W thickness.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115315"},"PeriodicalIF":1.9,"publicationDate":"2025-07-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144572679","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":"JT-60SA edge Thomson scattering procurement and tests","authors":"F.A. D’Isa ,&nbsp;S. Soare ,&nbsp;A. Fassina ,&nbsp;N. Hajnal ,&nbsp;A. Kornev ,&nbsp;A. Makarov ,&nbsp;Y. Ohtani ,&nbsp;M. Akimitsu ,&nbsp;J. Ayllon-Guerola ,&nbsp;M. Cavinato ,&nbsp;L. Giudicotti ,&nbsp;G. Phillips ,&nbsp;V. Raimondi ,&nbsp;C. Sozzi ,&nbsp;R. Pasqualotto","doi":"10.1016/j.fusengdes.2025.115300","DOIUrl":"10.1016/j.fusengdes.2025.115300","url":null,"abstract":"<div><div>A Thomson scattering (TS) diagnostic dedicated to measure the outer edge (low field side) of the plasma is being developed for JT-60SA. Its main purpose is to resolve the pedestal electron temperature and density profiles with high spatial resolution. This is a key topic for the mission of JT-60SA to complement ITER in resolving key physics and engineering issues to finally decide an acceptable DEMO plasma design, including practical and reliable plasma control schemes suitable for a power plant. Two TS systems will be installed in JT-60SA. They share the same laser beam path on the plasma equatorial plane, tangential to the inner wall. A lower oblique port and a horizontal port will host the optics collecting the scattered light from the outer edge and the core of the plasma, respectively. Procurement of TS systems is shared between Japan and EU; the latter is contributing with procurement of the edge TS collection optics and supporting structure, an edge dedicated laser, polychromators and optical fibers for both systems. Procurement is completed while installation and commissioning are well advanced. An overall description of the edge TS diagnostic setup and of its main components is presented. Tests and characteristics of the delivered components are discussed, particularly for the Nd:YAG laser, the fibers, the port plug and the mechanical structure supporting the collection optics.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115300"},"PeriodicalIF":1.9,"publicationDate":"2025-07-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144570893","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":"Development of a flight simulator for the WEST plasma and control system","authors":"Rémy Nouailletas ,&nbsp;Guillaume Gros ,&nbsp;Blaise Faugeras ,&nbsp;Jean-François Artaud ,&nbsp;Philippe Moreau","doi":"10.1016/j.fusengdes.2025.115299","DOIUrl":"10.1016/j.fusengdes.2025.115299","url":null,"abstract":"<div><div>The ITER project (<span><span>www.iter.org</span><svg><path></path></svg></span>) should demonstrate in the next decades the technical feasibility of controlled fusion reactions in tokamaks. One of the critical issues reaching this purpose is the design of plasma scenarios and associated controllers in order to achieve the desired performance while satisfying the operational limits. To succeed, the non-linearity, the uncertainties, and the limited observability of the plasma presently require adjusting controllers and scenarios during commissioning sessions. This method is time-consuming and must be reduced to the strict minimum time. To address this issue, the community has developed for several years simulation tools to design both controllers and scenarios using numerical models of the plasma. From simple linear models of the vertical plasma instability to integrated modeling of both plasma transport and equilibrium, these codes are now efficient enough to predict the plasma behavior and be called “flight simulator”. In this article, the flight simulator developed for WEST will be presented. One of the main features is the use as input of the same pulse schedule files and the same controllers as in the WEST Plasma Control System (PCS). Based on the free boundary equilibrium code NICE with flux diffusion equation and a 1D transport model, a consistent plasma time evolution can be computed and reduces the risk of failure due to numerical issues. To illustrate the abilities of the tool, a standard WEST X-point formation will be simulated and compared to the real data.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115299"},"PeriodicalIF":1.9,"publicationDate":"2025-07-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144563515","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":"Analyzing the safety framework for fusion demonstration plants in Korea","authors":"Hyun Soo Tho ,&nbsp;Jae Young Choi ,&nbsp;Sung Bo Moon ,&nbsp;Nam Il Her ,&nbsp;A Ra Cho ,&nbsp;Won Jae Choi ,&nbsp;Hyun-Kyung Chung ,&nbsp;Jeung Han Lee","doi":"10.1016/j.fusengdes.2025.115312","DOIUrl":"10.1016/j.fusengdes.2025.115312","url":null,"abstract":"<div><div>This paper describes the development of a safety framework for a fusion demonstration plant to be built (K-DEMO) in Korea. The study establishes safety definitions, objectives, and fundamental principles for K-DEMO, analyzes risk factors and accident scenarios, and proposes a tailored regulatory system. It reviews ITER and KSTAR safety cases, IAEA, and international regulations, providing a comparative analysis of safety issues. The study outlines the basic safety direction for K-DEMO, emphasizing unique safety characteristics and objectives. Six regulatory framework alternatives are proposed, from utilizing existing ones to enacting new ones. The short-term recommendation is to use a ‘radiation-generating device’ regulatory framework with revisions, as well as a long-term independent licensing path for commercial fusion reactors. Early regulatory engagement is recommended to reduce licensing uncertainty. This work supports a K-DEMO’s preliminary design and aligns with Korea’s fusion energy development plans, addressing safety issues and reducing uncertainties.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115312"},"PeriodicalIF":1.9,"publicationDate":"2025-07-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144563512","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":"Permeability of magnetohydrodynamical flows through porous structures under various external magnetic fields and forces","authors":"Jun Li,&nbsp;Kun Ting Eddie Chua,&nbsp;Vinh-Tan Nguyen,&nbsp;Daniel Joseph Wise,&nbsp;Wai Hong Ronald Chan","doi":"10.1016/j.fusengdes.2025.115294","DOIUrl":"10.1016/j.fusengdes.2025.115294","url":null,"abstract":"<div><div>Unlike in low-speed hydrodynamical flows where permeability is constant for a given porous structure, magnetohydrodynamical (MHD) flows are subject to the induced Lorentz force in the presence of an external magnetic field that significantly changes flow patterns and speeds. We conducted pore-scale MHD simulations using the lattice Boltzmann method to investigate permeability under a broad range of magnetic fields and driving forces. A simple cross-channel structure is first simulated for a systematic parametric study. At low Reynolds numbers, MHD flows continue to exhibit Darcy-law characteristics of conventional hydrodynamical flows where permeability is independent of driving forces for a given magnetic field. As the magnetic field strength increases, we verified that the obtained permeability reduces significantly when the magnetic field is imposed transversely and less so when in the flow-aligned direction. For low Hartmann numbers and arbitrary magnetic field orientations, we developed a superposition model for the permeability as if the magnetic field components were imposed independently. The superposition model is verified in simulations of a complicated Sierpinski carpet structure at low Hartmann numbers, demonstrating its practical applicability. Additionally, permeability reductions of the Sierpinski carpet in different directions were found to be almost identical for a given external magnetic field, unlike the situation in the simple cross-channel geometry. This is due to the flow passage becoming tortuous, with resisting Lorentz forces always induced in many locations where the local flow is bent by the carpet structure. This occurs even if the overall bulk flow direction is aligned with the imposed magnetic field orientation.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115294"},"PeriodicalIF":1.9,"publicationDate":"2025-07-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144563513","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":"Numerical simulation of magnetohydrodynamic mixed convection flow subjected to inclined nonuniform magnetic field","authors":"Yiming Xu,&nbsp;Xiaodong Wu,&nbsp;Jie Mao,&nbsp;Mizanur.M. Rahman","doi":"10.1016/j.fusengdes.2025.115305","DOIUrl":"10.1016/j.fusengdes.2025.115305","url":null,"abstract":"<div><div>This study numerically investigates the magnetohydrodynamic (MHD) flow and heat transfer characteristics of liquid metal in a vertically electrically conducting square duct subjected to a non-uniform magnetic field and localized surface heating. A self-developed and validated Reynolds-averaged Navier-Stokes (RANS) turbulent model (SSTMHD) is employed to analyze the effects of the magnetic field inclination angle (<span><math><mrow><mi>α</mi><mo>=</mo><msup><mn>0</mn><mo>∘</mo></msup><mspace></mspace><mo>−</mo><mspace></mspace><msup><mn>45</mn><mo>∘</mo></msup></mrow></math></span>) and Grashof number (<em>Gr =</em>2.88 × 10⁸ - 2.88 × 10¹⁰) on velocity distribution, electric current, pressure drop, temperature field, and heat transfer efficiency. The results reveal that in the unheated region, the velocity jet inclines toward the duct core as <span><math><mi>α</mi></math></span> increases from 0° to 45°, aligning with the magnetic field orientation. However, buoyancy-induced vortices develop in the heated region, enhancing high-velocity jets near the heated wall. Thermal analysis shows optimal temperature uniformity at <em>α</em> = 15°, whereas <em>α</em> = 45° exhibits deteriorated performance with extensive high-temperature zones. The average Nusselt number peaks at <em>α</em> = 15° but declines by 28.8% at <em>α</em> = 45°. Parametric studies identify maximum heat transfer efficiency at <em>Gr</em> = 2.88 × 10⁹, <em>α</em> = 45°, though increasing <em>Gr</em> from 2.88 × 10⁸ to 2.88 × 10¹⁰ at <em>α</em> = 15° reduces <em>Nu</em> by 51.3%, highlighting the dominance of streamwise heat convection and vortex-induced streamwise velocity suppression. Pressure distribution shows significant streamwise and transverse fluctuations in heated regions, with buoyancy amplifying streamwise pressure gradients. The magnetic field inclination minimally affects pressure gradients. These results can be referred to the design of liquid metal blankets, and operational parameter ranges of the blanket should be considered in the engineering practice when the magnetic field is inclined.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115305"},"PeriodicalIF":1.9,"publicationDate":"2025-07-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144549536","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":"Component lifetimes and their impact on the availability of commercial fusion power plants","authors":"Jack Foster,&nbsp;Samuel Knight,&nbsp;Stuart I. Muldrew","doi":"10.1016/j.fusengdes.2025.115231","DOIUrl":"10.1016/j.fusengdes.2025.115231","url":null,"abstract":"<div><div>The component lifecycle of fusion power plants is key to their commercial availability. While the compact nature of spherical tokamaks can help reduce costs and provide benefits to the plasma performance, the restricted inboard build presents challenges to both component lifetimes and maintenance. In this paper we detail a new availability model for spherical tokamaks, we then use this model as part of a Monte Carlo sensitivity analysis where we vary the time to replace components, as well as parameters which impact component lifetimes. From the results, we assess the trade-offs between these and plant availability and costs. We also make some statements about targets for these parameters to maximise the availability of commercial fusion power plants.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115231"},"PeriodicalIF":1.9,"publicationDate":"2025-07-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144563466","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":"The manufacturing and assembly of the MITICA beam source and beam line components","authors":"A. Masiello ,&nbsp;L. Bailly-Maître ,&nbsp;E. Bertran ,&nbsp;E. Bragulat ,&nbsp;M. Garcia ,&nbsp;G. Micó ,&nbsp;A. Sampedro ,&nbsp;J.A. Soto ,&nbsp;D. Marcuzzi ,&nbsp;A. Rizzolo ,&nbsp;P. Tinti ,&nbsp;M. Dalla Palma ,&nbsp;F. Geli ,&nbsp;J. Graceffa","doi":"10.1016/j.fusengdes.2025.115303","DOIUrl":"10.1016/j.fusengdes.2025.115303","url":null,"abstract":"<div><div>The MITICA experiment, a full-size prototype of the ITER Neutral Beam (NB) heating injector, is critical in validating the Beam Source (BS) and Beam Line Components (BLC) designs. Testing at MITICA is key to ensuring the NB system achieves ITER's stringent requirements, delivering 16.5 MW of power to the plasma. The BS includes an advanced multi-aperture, multi-grid accelerator and an ion source based on the development of an RF driven negative ion source at IPP Garching, with modifications being made due to experience gained from the full-size ion source prototype SPIDER at the NB test facility in Padua, Italy. The BLCs, comprising the Neutraliser and the Electron Dump (NED), the Electrostatic Residual Ion Dump (ERID) and the Calorimeter (CAL), which dumps the beam during commissioning and calibration of the injector. As first-of-a-kind components, the fabrication of the BS and of the BLC has required extensive R&amp;D, precise engineering and rigorous quality control. This paper summarizes four years of contract follow-up, detailing the design, manufacturing processes and challenges in developing the BS and BLCs, with a focus on engineering solutions and lessons learned.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115303"},"PeriodicalIF":1.9,"publicationDate":"2025-07-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144563514","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":"Design description and thermo-hydraulic assessment of the steering mirror for the EU DEMO Electron Cyclotron system","authors":"Avelino Mas Sánchez,&nbsp;René Chavan,&nbsp;Daniel Birlan,&nbsp;Timothy P. Goodman,&nbsp;Jean-Philippe Hogge,&nbsp;Cinta Marraco Borderas,&nbsp;Anastasia Xydou","doi":"10.1016/j.fusengdes.2025.115313","DOIUrl":"10.1016/j.fusengdes.2025.115313","url":null,"abstract":"<div><div>Six Electron Cyclotron (EC) launchers are currently envisaged to be installed at the Equatorial Ports (EP) of the EU DEMO Tokamak with the purpose of delivering up to 130 MW for plasma bulk heating (BH), thermal instability (TI) control and magnetohydrodynamic (MHD) mode suppression. The MHD stabilization will be performed by two mid steering antennas (MSA) with a fixed mirror and a steerable mirror, each reflecting three mm-wave beams with a nominal power of 2 MW.</div><div>A new proposal for the steering mechanism, which completely avoids the use of flexible cooling pipes, is described and analysed in this paper. In this new concept, the flexure pivot blades feature inner channels that enable cooling water to flow through them and remove the deposited heat efficiently. The thermo-hydraulic analysis shows that the flexure pivots experience moderately low temperature values, particularly when compared with previous uncooled designs. However, the flow velocities along the channels are relatively high, which is translated in a remarkable overall pressure drop in the system.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115313"},"PeriodicalIF":1.9,"publicationDate":"2025-07-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144549516","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":"A dynamic model of a power conversion system with indirect thermal energy storage for a pulsed fusion tokamak for use in design optimisation","authors":"Oliver M.G. Ward ,&nbsp;Eric S. Fraga ,&nbsp;Federico Galvanin ,&nbsp;Nelia Jurado ,&nbsp;Daniel Blackburn ,&nbsp;Robert J. Warren ,&nbsp;Jack Acres","doi":"10.1016/j.fusengdes.2025.115289","DOIUrl":"10.1016/j.fusengdes.2025.115289","url":null,"abstract":"<div><div>This work addresses the challenge of designing a power conversion system, which converts thermal energy into electrical energy, that can handle heat generation from a pulsed fusion tokamak. Large transients would be damaging for components such as turbomachinery and make grid integration difficult. Energy storage is considered as a solution to buffer the impact of the tokamak dynamics on power generation. A dynamic model is presented of a possible power conversion system design using sensible thermal energy storage, implemented in the Modelica modelling language. Novel lumped-parameter dynamic models, based on the logarithmic mean temperature difference, are developed for both one- and two-phase heat exchangers.</div><div>The models are then used for two optimisation-based design problems: a single objective optimisation problem for steady state turbine power and a bi-objective optimisation problem that allows for reduced power generation during a tokamak dwell when no heat is being generated. The optimisation problems are solved using the Fresa.jl meta-heuristic plant propagation algorithm and a multi-agent system allowing for the cooperation of different fitness ranking methods. Both case studies show the dynamic models are robust and fast enough for use in this optimisation framework, and demonstrate the potential of simulation–optimisation in the design of prototype fusion power plants with pulsed operation.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115289"},"PeriodicalIF":1.9,"publicationDate":"2025-07-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144534150","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}