Fusion Engineering and Design最新文献

{"title":"A scoping study of far-SOL main-wall protection limiters for steady-state operation of compact pilot plant tokamaks","authors":"J.H. Nichols ,&nbsp;E.A. Unterberg ,&nbsp;P.C. Stangeby","doi":"10.1016/j.fusengdes.2025.115278","DOIUrl":"10.1016/j.fusengdes.2025.115278","url":null,"abstract":"<div><div>We present a novel method for handling steady-state heat fluxes incident on the main wall of pilot plant-scale magnetic fusion devices, based on the utilization of protection limiters in the far scrape-off layer (SOL). This method helps avoid large plasma-wall gaps, without excessively compromising blanket performance. We present an optimization algorithm for determining the appropriate size and scale of these protection limiters given (1) probability distributions of SOL plasma parameters and (2) assumed risk tolerance. As part of this optimization, we have developed an analytic description of parallel heat fluxes across limiter shadows, and an objective cost function (the ‘Far-SOL Marginal Cost’) to quantify the impact that different main-wall thermal management design choices have on reactor capital cost. Applying the model to a midscale fusion pilot plant concept shows that making use of far-SOL protection limiters can reduce capital costs on the order of $500 M, relative to naively increasing the plasma-wall gap. Our analysis demonstrates that the far-SOL power decay length is the highest-leverage plasma assumption for thermal loading of the first wall, and the primary cost driver for main wall thermal management. The relative cost efficiency of protection limiters increases as assumptions on the far-SOL heat flux become more pessimistic. The concepts described in this paper motivate the further development of far-SOL protection limiters as part of larger efforts to design economical core-edge-wall compatible solutions for a fusion pilot plant.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115278"},"PeriodicalIF":1.9,"publicationDate":"2025-06-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144338599","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":"Thermal testing of high-temperature vacuum insulations for tokamak COMPASS-U","authors":"P. Bartoň ,&nbsp;P. Holejšovská ,&nbsp;M. Šebík ,&nbsp;Š. Fuková ,&nbsp;J. Varju","doi":"10.1016/j.fusengdes.2025.115259","DOIUrl":"10.1016/j.fusengdes.2025.115259","url":null,"abstract":"<div><div>This study presents the development and testing of high-temperature vacuum insulations for the COMPASS Upgrade (COMPASS-U) tokamak at IPP Prague. This included the development of a specific high-vacuum high-temperature (500 °C) testing apparatus, able to test the insulation performance in a tokamak-like environment. At first, baseline insulation options, such as passive heat shields, were tested to verify the soundness of the method used. Then, several commercial insulations (microporous insulation, multilayer insulation, <span><math><mrow><mo>…</mo><mspace></mspace></mrow></math></span>) were tested, with results that matched the theoretical predictions. Finally, we have developed our MLI-like insulation with good thermal properties but increased resistance against electromagnetic-induced forces and measured its performance with various amounts of layers.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115259"},"PeriodicalIF":1.9,"publicationDate":"2025-06-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144335839","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 implementation of the metal additive manufacturing for the DTT experiment: NBI, and ECRH components","authors":"Adriano Pepato ,&nbsp;D. Agguiaro ,&nbsp;P. Agostinetti ,&nbsp;M. Bonesso ,&nbsp;A. Bruschi ,&nbsp;S. Candela ,&nbsp;V. Candela ,&nbsp;S. Ceccuzzi ,&nbsp;R. Dima ,&nbsp;F. Fanale ,&nbsp;G. Favero ,&nbsp;E. Gaietti ,&nbsp;S. Garavaglia ,&nbsp;G. Granucci ,&nbsp;S. Mancin ,&nbsp;A. Moro ,&nbsp;A. Murari ,&nbsp;P. Rebesan ,&nbsp;M. Romanato ,&nbsp;A. Romano ,&nbsp;F. Veronese","doi":"10.1016/j.fusengdes.2025.115238","DOIUrl":"10.1016/j.fusengdes.2025.115238","url":null,"abstract":"<div><div>Nuclear fusion faces many challenges, one of which is the production of reactor components. Due to the extreme operating conditions, the geometrical aspect is of great importance. Some important components are, for example, the accelerating grids of the Negative Ions Neutral Beam (NBI) Injection system. To guarantee the most appropriate beam optics and optimized cooling, the grids must be built with a shape that would be impossible to obtain with traditional manufacturing approaches. Additive manufacturing technologies allow producing very geometrically complex components, with high dimensional accuracy and an optimized shape considering also the design-for-assembly point of view. However, these innovative technologies are not free from challenges. A key point is the optimization of the process parameters, which are specific for each material and powder; this preliminary research is fundamental to obtain the best quality and performance from a material. Additive manufacturing represents a highly promising production method also for the fabrication of components made of refractory metals. Indeed, this special class of materials is extremely difficult to form due to their unique characteristics; moreover, they are usually very expensive, so waste should be reduced as much as possible. In nuclear fusion, refractory metals are good candidates for plasma-facing and divertor applications, for example, where the operative conditions are prohibitive. In this work, the studies related to the characterization of materials processed with Laser Powder Bed Fusion (LPBF) technique are presented, for what concerns copper alloys and refractory metals. The latest updates on the innovative design specially developed for additive manufacturing of the accelerating grids for the NBI system of DTT are also described.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115238"},"PeriodicalIF":1.9,"publicationDate":"2025-06-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144330410","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 implications of impurities on shutdown dose rates in the burning plasma experimental tokamak","authors":"Lin Kong ,&nbsp;Xilong Tong ,&nbsp;Xiaokang Zhang ,&nbsp;Shanliang Zheng","doi":"10.1016/j.fusengdes.2025.115285","DOIUrl":"10.1016/j.fusengdes.2025.115285","url":null,"abstract":"<div><div>With the growing demand for nuclear fusion energy, understanding radiation safety implications in experimental tokamaks becomes critical. Structural material impurities like cobalt (Co) significantly impact shutdown dose rates (SDDR) through long-lived radionuclides such as ⁶⁰Co, affecting maintenance feasibility and waste management. Current assessments using contact dose rates (CDR) often overlook complex geometrical effects, potentially underestimating radiation risks. This study employs a comprehensive approach integrating 3D Monte Carlo neutron transport, FISPACT-II activation analysis, and the NATF toolkit to evaluate impurity impacts in a burning plasma experimental tokamak. The results reveal that SDDR exhibits strong linear correlations with Co content (p &lt; 0.01) inside tokamak, and statistically significant linear correlations (p &lt; 0.05) for locations outside the tokamak. Geometric effects cause up to 6.5-fold differences between SDDR and CDR. The work demonstrates that maintaining Co below 0.05 wt. % enables remote handling compliance while highlighting the necessity of localized shielding for maintenance optimization. This research provides the full-device SDDR mapping with geometric considerations for the Chinese-designed tokamak, offering crucial insights for material specification and radiation protection strategies in fusion reactors.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115285"},"PeriodicalIF":1.9,"publicationDate":"2025-06-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144330398","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":"Advancing remote handling capabilities in the nuclear industry with AI-based surrogate models for robotic technologies","authors":"Akhtar Zeb ,&nbsp;Petteri Kokkonen ,&nbsp;Mikko Tahkola ,&nbsp;William Brace ,&nbsp;Ferdinando Milella","doi":"10.1016/j.fusengdes.2025.115286","DOIUrl":"10.1016/j.fusengdes.2025.115286","url":null,"abstract":"<div><div>The development and deployment of cutting-edge robotic technologies are crucial for enhancing remote handling capabilities in confined and hazardous environments within the nuclear industry. These advancements play a vital role in minimising radiation exposure to workers, improving operational safety, and optimising the efficiency of maintaining nuclear facilities throughout their lifecycle. Accurate prediction of deformations in key robotic components, such as revolute joints and actuator brackets, is essential for achieving precise and reliable handling of complex and delicate equipment, including breeding blankets in fusion reactors. This study focuses on designing such components by developing parametric Functional Mock-up Units (FMUs) using machine learning-based surrogate models. Two scenarios are explored: one involving a revolute joint and the other an actuator bracket. Input and output parameters for the FMUs were carefully selected to ensure seamless integration into potential system-level models. Finite Element Analysis (FEA) simulations were conducted using diverse sampling strategies, including full factorial, simple random, and Latin hypercube sampling. Multiple surrogate models trained on FEA-generated datasets demonstrated high accuracy and computational efficiency on testing datasets. The resulting surrogate models were encapsulated as FMUs to serve as modular components in physics-based simulations, effectively representing similar joints and brackets in robotic systems. These parametric FMUs facilitate efficient simulation-driven parametric design, predictive control, and condition monitoring of test rig devices, emulating the functionality and operating conditions of fusion reactor remote maintenance robots. This research advances robotic technologies for challenging nuclear applications, offering valuable tools and insights to enhance the design and operation of robotic systems in the fusion industry.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115286"},"PeriodicalIF":1.9,"publicationDate":"2025-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144330409","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 conceptual design of the soft x-ray tomography for the DTT","authors":"S. Palomba ,&nbsp;A. Belpane ,&nbsp;V. D’Agostino ,&nbsp;L. Gabellieri ,&nbsp;M. Marinelli ,&nbsp;A. Murari ,&nbsp;E. Peluso ,&nbsp;C. Verona ,&nbsp;G. Verona-Rinati ,&nbsp;F. Bombarda","doi":"10.1016/j.fusengdes.2025.115269","DOIUrl":"10.1016/j.fusengdes.2025.115269","url":null,"abstract":"<div><div>DTT, the Divertor Tokamak Test facility, currently under construction at ENEA in Frascati (Rome, Italy), is a fully superconducting tokamak. DTT is a medium-sized experimental fusion reactor designed to test new divertor and plasma control technologies for use in larger, fusion reactor-scale devices such as ITER and DEMO. This work focuses on the conceptual design of Soft X-ray tomographic system for DTT first phase, when the machine is expected to operate with up to 17.5 MW of total injected power The diagnostic layout has been developed to optimize the tomographic reconstruction of emissivity distributions using Tikhonov-Phillips regularization techniques. Measurement arrays are positioned within each of the four access ports of a single toroidal sector, with their lines of sight (LoS) cover the entire poloidal cross-section of the vacuum vessel. This configuration is essential to ensure accurate tomographic reconstruction, which is useful for analyzing and monitoring plasma behavior. A large effort has been devoted to defining the best layout for the mechanical supports and their positioning, to ensure compatibility with the other systems located in the same ports. The selected detectors for this diagnostic are grown Chemical Vapor Deposition (CVD) diamonds, which offer significant advantages over traditional solutions, including high radiation hardness, increased mechanical robustness, and the ability to operate at elevated temperatures and pressures.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115269"},"PeriodicalIF":1.9,"publicationDate":"2025-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144321038","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":"Advancements in the IFMIF-DONES target system for fusion materials irradiation","authors":"D. Oravecz ,&nbsp;A. Zsákai ,&nbsp;R.L. Csiszár ,&nbsp;D. Ferenczy ,&nbsp;T. Dézsi ,&nbsp;F.S. Nitti ,&nbsp;J. Maestre ,&nbsp;D. Bernardi ,&nbsp;A. Ibarra","doi":"10.1016/j.fusengdes.2025.115288","DOIUrl":"10.1016/j.fusengdes.2025.115288","url":null,"abstract":"<div><div>This paper provides an overview of the advancements in the Target System design of the IFMIF-DONES Project which simulates the effects of the extreme neutron irradiation conditions expected in the future fusion power reactors. The system’s role in generating a high-intensity neutron source for testing candidate materials to be used in the reactor is highlighted. The discussion includes design innovations, recent developments, challenges, and future prospects, emphasizing critical aspects and validation needs for the Target System.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115288"},"PeriodicalIF":1.9,"publicationDate":"2025-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144321039","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":"Hydraulic characterization of the central cooling channel for the DEMO PF coil conductor","authors":"Aleksandra Dembkowska ,&nbsp;Monika Lewandowska ,&nbsp;Paweł Herbin","doi":"10.1016/j.fusengdes.2025.115258","DOIUrl":"10.1016/j.fusengdes.2025.115258","url":null,"abstract":"<div><div>Recently a design of the 6 Poloidal Field (PF) coils for the European DEMOnstration Fusion Power Plant (EU-DEMO) tokamak has been proposed by the CEA IRFM team. Each of PF coils designed by CEA is wound using a square NbTi Cable-in-Conduit Conductor (CICC) with a central cooling channel separated by a steel spiral from the bundle region. The outer diameters of spirals in the EU-DEMO PF3, PF4 and PF6 conductors designed by CEA are in the range 13.6 - 15.8 mm. Spirals with such large diameters have never been tested for pressure drop, so applicability of the available friction factor correlations for them is uncertain. To clarify this issue, we produced (by 3D printing) two samples relevant for hydraulic tests, with geometry similar to spiral cooling channels in CICCs. The first one, with the geometry identical to the ITER SHOWA spiral which had been tested for pressure drop in the past, served as verification, if samples produced by 3D printing feature the same hydraulic resistance as the respective samples traditionally produced (by inserting a spiral into a tight steel or rubber tube). The second sample had a large diameter identical to the cooling channel of the PF6 conductor designed by CEA. Both samples were tested for pressure drop at the THETIS installation, using demineralized water at three different temperatures, to get experimental data in possibly wide Re range. The experimental data were used to develop friction factor correlation for a spiral duct with large diameter, which could be utilized in future thermal-hydraulic analyses of the EU-DEMO PF coils or other CICCs with cooling channels of similar geometry.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115258"},"PeriodicalIF":1.9,"publicationDate":"2025-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144330397","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":"Estimation of tritium transfer parameters in biphasic lithium ceramic based on the results of reactor irradiation experiments","authors":"Timur Kulsartov ,&nbsp;Zhanna Zaurbekova ,&nbsp;Regina Knitter ,&nbsp;Julia Leys ,&nbsp;Asset Shaimerdenov ,&nbsp;Yevgen Chikhray ,&nbsp;Saulet Askerbekov ,&nbsp;Inesh Kenzhina ,&nbsp;Alexandr Yelishenkov","doi":"10.1016/j.fusengdes.2025.115282","DOIUrl":"10.1016/j.fusengdes.2025.115282","url":null,"abstract":"<div><div>It is expected that the development of thermonuclear fusion will be able to easily satisfy the energy needs of humanity. There are enough fuel reserves for the fusion reaction: tritium can be bred via a ⁶Li(n,α)³H reaction from lithium, which is common in nature, and deuterium is quite easily extracted from seawater. One of the problems on the way to implement thermonuclear fusion today is the search for and development of breeder materials that can withstand the high radiation and energy loads that are expected in a long-pulsed fusion devices.</div><div>Various types of lithium-containing ceramic materials are currently being actively studied for use as a breeder material in helium-cooled breeder blanket concepts.</div><div>This study focuses on the methodology and results of calculations of tritium residence time in the samples of biphasic lithium ceramic pebble bed containing nominal 65 mol % lithium orthosilicate and 35 mol % lithium metatitanate (pebble diameter 0.25 -1.250 mm).</div><div>The values of the tritium residence time obtained as a result of modeling the release of tritium from ceramics within the framework of the diffusion-desorption model have a temperature dependence of lgτ = -1.374+1676/<em>t</em>. They are in good agreement with the literature data, suggesting that the tritium residence time increases with increasing open porosity.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115282"},"PeriodicalIF":1.9,"publicationDate":"2025-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144321037","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":"Comparative analysis of high-temperature corrosion processes of beryllides of different compositions","authors":"Timur Kulsartov ,&nbsp;Inesh Kenzhina ,&nbsp;Kuanysh Samarkhanov ,&nbsp;Yergazy Kenzhin ,&nbsp;Yuriy Gordienko ,&nbsp;Yuriy Ponkratov ,&nbsp;Yevgeniy Chikhray ,&nbsp;Vadim Bochkov ,&nbsp;Zhanna Zaurbekova ,&nbsp;Alexander Yelishenkov ,&nbsp;Meiram Begentayev ,&nbsp;Saulet Askerbekov ,&nbsp;Sergey Udartsev ,&nbsp;Mikhail Podoinikov","doi":"10.1016/j.fusengdes.2025.115283","DOIUrl":"10.1016/j.fusengdes.2025.115283","url":null,"abstract":"<div><div>Beryllium intermetallic compounds, such as titanium beryllide (Be₁₂Ti), chromium beryllide (Be₁₂Cr), and zirconium beryllide (Be₂Zr), exhibit exceptional physicochemical properties, making them promising materials for diverse scientific and energy applications. Among them, Be₁₂Ti is the leading candidate for neutron multiplier use in future European projects employing the Helium Cooled Pebble Bed (HCPB) concept and solid blanket systems of ITER and DEMO-type reactors, due to its high melting point, radiation-induced swelling, low activation, and excellent corrosion resistance. To broaden the scope of material selection, exploring alternative compounds has gained importance. Having properties similar to Be₁₂Ti, chromium beryllide Be₁₂Cr demonstrates potential as a possible option, including high thermal and radiation resistance, although its corrosion resistance in vapor-gas medium requires further research. Beyond fusion applications, beryllides have potential in other domains. For example, Be₂Zr exhibits remarkable properties for hydrogen energy, such as forming stable hydride phases, making it an excellent candidate for hydrogen storage systems. These investigations are especially relevant for advancing hydrogen and fusion energy technologies in Kazakhstan. Ulba Metallurgical Plant JSC, a leader in beryllium material production, synthesizes not only Be₁₂Ti, Be₁₂Cr and Be₂Zr, but also less studied beryllides.</div><div>This study performs a comparative analysis of high-temperature corrosion in beryllides with varying compositions. A series of experiments were conducted to investigate the corrosion mechanisms under vapor-gas mediums with different isotopic compositions using non-isothermal heating across a wide temperature range. Key features of beryllide corrosion were revealed, including time-dependent changes in sample mass and gas-phase composition during linear heating. Corrosion behaviors of different beryllide compositions were established, and temperature-dependent reaction rates determined. These findings enhance understanding of beryllide corrosion properties, providing a scientific basis for their potential in fusion and hydrogen technologies.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115283"},"PeriodicalIF":1.9,"publicationDate":"2025-06-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144321036","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}