Fusion Engineering and Design最新文献

{"title":"Irradiation hardening and mechanical behavior of K-RAFM steels subjected to Fe ion irradiation at doses up to 20 dpa","authors":"Sangeun Kim ,&nbsp;Jinwoo Park ,&nbsp;Mingyu Lee ,&nbsp;Taeyun Kwon ,&nbsp;Hyung-Ha Jin ,&nbsp;Chang-hoon Lee ,&nbsp;Byung-Yong Yu ,&nbsp;Weon Cheol Lim ,&nbsp;Chansun Shin","doi":"10.1016/j.fusengdes.2025.115235","DOIUrl":"10.1016/j.fusengdes.2025.115235","url":null,"abstract":"<div><div>This study explores the irradiation hardening behavior of K-RAFM steel and Reference steel through micropillar compression tests. Fe ion irradiation at 300 °C was conducted to achieve a dose of 20 dpa. The irradiated specimens exhibited increased yield strength and reduced strain bursts, which are attributed to the formation of radiation-induced defects. K-RAFM steel exhibited superior resistance to irradiation hardening compared to Reference steel across all irradiation conditions. This improved performance is attributed to the addition of Ti, which enhances the fraction of MX precipitates that serve as efficient traps for radiation-induced defects. Additionally, the yield strength changes observed for K-RAFM steel at 2 dpa and 20 dpa are consistent with trends reported for other RAFM steels in the literature, highlighting its promise as a structural material for fusion reactor applications.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115235"},"PeriodicalIF":1.9,"publicationDate":"2025-06-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144195778","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":"Exploratory thermal and fluid-dynamic assessment of a pin of the Helium cooled pebble bed breeding blanket concept with a modular pin monoblock design for the EU DEMO nuclear fusion reactor","authors":"A. Gioè ,&nbsp;F.A. Hernández ,&nbsp;G. Bongiovì ,&nbsp;A. Quartararo ,&nbsp;E. Vallone ,&nbsp;G. Agnello ,&nbsp;G.A. Spagnuolo ,&nbsp;S. d’Amico ,&nbsp;P. Chiovaro ,&nbsp;P.A. Di Maio","doi":"10.1016/j.fusengdes.2025.115243","DOIUrl":"10.1016/j.fusengdes.2025.115243","url":null,"abstract":"<div><div>The Helium-Cooled Pebble-Bed (HCPB) Breeding Blanket (BB) concept is one of the two candidates eligible for the driver blanket for the EU-DEMO nuclear fusion reactor. It foresees gaseous helium at high pressure as a coolant and tritium carrier, and solid tritium breeder and neutron multiplier. In order to overcome the potential showstoppers that emerged during its pre-conceptual design phase, alternative HCPB BB variants are under consideration in the frame of the DEMO studies. Among them, the concept envisaging a modular pin monoblock presents the advantages of having all the functional materials contained in a pin structure and of avoiding the need for a first wall, remarkably simplifying manufacturing. Hence, in this work, a campaign of thermofluid-dynamic scoping analyses aimed at assessing the performances of this novel BB concept is presented. To this scope, different geometric layouts have been assessed under a wide range of loading conditions and evaluating the sensitivity to key parameters, through cost-effective 2D CFD models. As an outcome, two promising geometric configurations ensuring both temperatures in line with the design requirements and an acceptable pressure drop have been found to be further assessed from the structural standpoint in a second phase of the activity.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115243"},"PeriodicalIF":1.9,"publicationDate":"2025-06-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144189616","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":"Remote maintenance strategy of the volumetric neutron source shielding blanket","authors":"Rocco Mozzillo ,&nbsp;Vincenzo Claps ,&nbsp;Nicolas Calzone ,&nbsp;Günter Janeschitz ,&nbsp;Curt Gliss ,&nbsp;Christian Bachmann","doi":"10.1016/j.fusengdes.2025.115226","DOIUrl":"10.1016/j.fusengdes.2025.115226","url":null,"abstract":"<div><div>A feasibility study of a new testing facility, i.e. the volumetric neutron source, VNS, in a tokamak configuration was initiated in 2023 and it is now under way with the purpose of addressing potential showstoppers. Key outcomes of the engineering activities are presented at this conference. The main goal of the VNS is to provide a realistic environment to test the in-vessel components of fusion reactors, in particular the tritium breeding blanket. The lessons learned during previous years of DEMO development point to the need for a thorough nuclear design integration already at level of the basic machine design, hence the issues related to the maintenance of the in-vessel components have been addressed at a basic level. The work presented here describes the remote maintenance strategy for VNS blankets, which is an adaptation of the concept proposed for DEMO. Consistent with the initial requirements of the machine, the remote replacement sequence of the blankets, the potential list of the required tools and transporter and the conceptual design of some of the main tools are presented and discussed in this article.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115226"},"PeriodicalIF":1.9,"publicationDate":"2025-05-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144184710","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 management and cascading of geometrical requirements from designer to manufacturer in the ITER life cycle","authors":"Gabriele D’Amico ,&nbsp;Francisco Javier Fuentes ,&nbsp;Andres Jimenez ,&nbsp;Francesca Giovanna Lanzotti ,&nbsp;Gianluca Picci","doi":"10.1016/j.fusengdes.2025.115223","DOIUrl":"10.1016/j.fusengdes.2025.115223","url":null,"abstract":"<div><div>A structured process is in place to manage the geometrical requirements of the ITER machine and the associated risk. This process involves systematically breaking down geometrical requirements from the project level to system, sub-system until component level. The breakdown at component level feeds the manufacturing phase. A proper management and cascading of those requirements is accomplished to create a solid link between design intents and manufactured component. Clear, reachable and reasonable geometrical requirements must be cascaded to the manufacturers to avoid over-constrains or showstoppers in the lifecycle. Along the manufacturing process, it becomes possible to leverage the as-built geometrical data from the as-manufactured component to feedback reverse engineering process and optimize the subsequent assembly phases of the fusion machine. This paper addresses the complexity of the above-described dimensional risk management approach, detailing each phase of the process, from design through manufacturing to final assembly.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115223"},"PeriodicalIF":1.9,"publicationDate":"2025-05-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144184707","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":"Neutron spectroscopy with LaCl3(Ce)-based detector on EAST tokamak","authors":"A. Pankratenko ,&nbsp;T. Kormilitsyn ,&nbsp;T. Semenov ,&nbsp;S. Obudovsky ,&nbsp;Yu. Kashchuk ,&nbsp;G. Zhong ,&nbsp;Y. Zhang ,&nbsp;M. Xu","doi":"10.1016/j.fusengdes.2025.115236","DOIUrl":"10.1016/j.fusengdes.2025.115236","url":null,"abstract":"<div><div>A neutron spectrometer based on the LaCl₃(Ce) inorganic scintillator was installed on the EAST tokamak as a part of its neutron diagnostics complex. Detector data was obtained during approximately 300 shots in the course of the experimental campaign in July 2024. The spectrometer was extensively tested under neutron irradiation and additionally calibrated on-site using standard γ-sources. Using pulse-shape discrimination technique, we have separated the spectra into components and studied the neutron-produced proton component in detail. We have successfully measured the neutron energies and count rates with the results showing agreement with measurements of other diagnostics installed on EAST machine. This result demonstrates for the first time the usability of LaCl₃(Ce) as a neutron spectrometer for magnetic confinement experiments with deuterium plasma.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115236"},"PeriodicalIF":1.9,"publicationDate":"2025-05-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144184709","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 and analysis of the calorimeter support structure for the negative neutral beam injection system of China fusion engineering test reactor","authors":"Yunhua Tong ,&nbsp;Xiang Gao ,&nbsp;Lei Cao ,&nbsp;Yuanlai Xie ,&nbsp;Ning Tang ,&nbsp;Haitao Zhang","doi":"10.1016/j.fusengdes.2025.115237","DOIUrl":"10.1016/j.fusengdes.2025.115237","url":null,"abstract":"<div><div>The negative ion-based neutral beam injection system (NBI) is a core component of the Chinese fusion engineering experimental reactor (CFETR). Effectively cutting off the beam and completing the debugging of the neutral beam device require a neutral beam power measurement system, which is of great significance and indispensability. This paper presents a detailed design of the target plate support structure for the calorimeter, with a focus on analyzing the strength and deformation of the support structure under different load conditions. A prototype is developed based on the design, and its structure is verified to meet the design requirements through pressure testing in a 4 MPa nitrogen internal pressure environment, providing a reference for the structural design and manufacturing of NBI calorimeters.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115237"},"PeriodicalIF":1.9,"publicationDate":"2025-05-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144184708","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":"Automated design rationalization of robot component geometry for ITER blanket remote handling system","authors":"Takuya Iwamoto,&nbsp;Yuto Noguchi,&nbsp;Nobukazu Takeda","doi":"10.1016/j.fusengdes.2025.115219","DOIUrl":"10.1016/j.fusengdes.2025.115219","url":null,"abstract":"","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115219"},"PeriodicalIF":1.9,"publicationDate":"2025-05-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144177835","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 of the DEMO divertor target baffles","authors":"F. Crescenzi ,&nbsp;M. Cerocchi ,&nbsp;R. De Luca ,&nbsp;F. Giorgetti ,&nbsp;P. Lorusso ,&nbsp;A. Mancini ,&nbsp;G. Mugnaini ,&nbsp;S. Roccella ,&nbsp;L. Verdini ,&nbsp;J.H. You","doi":"10.1016/j.fusengdes.2025.115218","DOIUrl":"10.1016/j.fusengdes.2025.115218","url":null,"abstract":"<div><div>The divertor is one of the key components of a Tokamak fusion machine since it must be capable to exhaust both particles and power. Since the CAD model has been released the DEMO Outboard Vertical Target baffles (OVT) represent one of the most challenging components both from the design and fabrication technology point of view. It is infact exposed to intense neutron damage and high heat fluxes and has a very narrow radius of curvature (around 100mm compared to the radius of 500mm of ITER ones). Within the Work Package Divertor (WP-DIV 2021-2027) the EUROfusion Consortium launched a dedicated R&amp;D task to explore the fabrication of the component itself. ENEA that is involved in the R&amp;D technology activities of the target PFCs for the WP-DIV will study two alternative joining technologies with the aim to design and manufacture a mock-up made by a curved CuCrZr cooling pipe and Tungsten monoblocks joined to the pipe itself. The first technology is the well assessed Hot Radial Pressing (HRP) while the second one will be the brazing through an interlayer material between the pipe and the monoblocks. This paper reports the results of both joining technologies by means of Non-Destructive Examinations (Ultrasonic Testing) to give preliminary feedback on a suitable and industrially scalable manufacturing process.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115218"},"PeriodicalIF":1.9,"publicationDate":"2025-05-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144177728","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":"Modeling of hydrogen isotope permeation through liquid Sn supported by various metal substrates","authors":"Yuya Ando,&nbsp;Ryo Hatano,&nbsp;Ryosuke Ohata,&nbsp;Teppei Otsuka","doi":"10.1016/j.fusengdes.2025.115233","DOIUrl":"10.1016/j.fusengdes.2025.115233","url":null,"abstract":"<div><div>Hydrogen isotope permeation through liquid Sn (Sn<em>_L</em>) supported by solid metals (<em>M</em> = Fe, Ni, V, F82H, and Pd) was examined at constant temperatures from 473 to 773 K and pressures from 0.67 to 93 kPa. The interaction between Sn<em>_L</em> and the supporting metal substrate formed an intermediate alloy (IA) layer at the interface due to corrosion caused by the chemical reactions of Sn<em>_L</em> with M. The Sn<em>_L</em>/M systems were categorized into two types according to the overall deuterium permeation behavior. In the Sn<em>_L</em>/Fe and Sn<em>_L</em>/Ni systems, the IA layer was crucial in governing the overall deuterium permeation flux. In the Sn<em>_L</em>/Pd system, deuterium permeation was strongly suppressed by the IA layers, whereas in the Sn<em>_L</em>/V and Sn<em>_L</em>/F82H systems, the rate-determining step for the overall deuterium permeation flux was the Sn<em>_L</em> layer. The Sn<em>_L</em>/V system exhibited the highest deuterium permeation flux, which was less affected by the formation of the IA layer. This result highlights the potential of V and its alloys as membrane windows for tritium extraction from Sn<em>_L</em> by permeation.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115233"},"PeriodicalIF":1.9,"publicationDate":"2025-05-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144177729","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":"ITER core plasma thomson scattering diagnostic collection optics design","authors":"M. Amarika ,&nbsp;G. Beaskoetxea ,&nbsp;A. Estevez ,&nbsp;M. Roldán ,&nbsp;A. María ,&nbsp;G. Murga ,&nbsp;L. Sanchez ,&nbsp;U. Walach ,&nbsp;J. Puig","doi":"10.1016/j.fusengdes.2025.115194","DOIUrl":"10.1016/j.fusengdes.2025.115194","url":null,"abstract":"<div><div>The ITER Core Plasma Thomson Scattering (CPTS) diagnostic is conceived to measure the electron temperature and density with accuracies of 10 % and 5 %, respectively, at the Tokamak plasma core with a spatial resolution of a/30=66 mm (<em>a</em> plasma minor radius). For this purpose, a Nd:YAG 1064 nm laser is injected into the vacuum vessel during the plasma pulse, where it is scattered by the plasma electrons due to Thomson scattering (TS). The Collection Optics (CO) is in charge of acquiring the scattered photons at the plasma core (0 &lt; <em>r</em>/<em>a</em> &lt; 0.85) and guiding the light from the In-Vessel to the Ex-Vessel area where the laser chord is reimaged on a fibre backplane. The fibre bundles then transmit the collected light to the polychromators, where it is processed.</div><div>The design drivers and constraints for this system are diverse. Firstly, the CO shall provide a high optical transmission in the wavelength range of 400 -1050 nm. Secondly, there is a need to find a balance between collecting a sufficient amount of TS photons to ensure the required diagnostic performance while ensuring the shielding performance of the system. Thirdly, the CO design and material selection shall be compatible with the In-Vessel harsh environment and loading conditions and include a cleaning system for the First Mirror Unit (FMU). Finally, in terms of integration, the design needs to fit within existing available volumes allowing the integration of surrounding components and shall be able to compensate operational relative displacements between the In-Vessel and Ex-Vessel areas.</div><div>The proposed solution is based on a six mirrors dogleg configuration In-Vessel, and another two mirrors in a periscope configuration and a lens barrel composed of seven lenses Ex-Vessel. The analysis performed and the error budget has confirmed that the required optical performance of the CO is met, ensuring the required transmission, spatial resolution and coupling efficiency of the optical system.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115194"},"PeriodicalIF":1.9,"publicationDate":"2025-05-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144177834","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}