Fusion Engineering and Design最新文献

{"title":"Development of a translation stage for beam studies in the negative ion source SPIDER","authors":"R. Agnello ,&nbsp;M. Barbisan ,&nbsp;L. Lotto ,&nbsp;R. Pasqualotto ,&nbsp;B. Zaniol ,&nbsp;G. Serianni","doi":"10.1016/j.fusengdes.2025.115413","DOIUrl":"10.1016/j.fusengdes.2025.115413","url":null,"abstract":"<div><div>Beam diagnostics play a crucial role in characterizing the beam performances of SPIDER, the prototype negative ion source for the ITER neutral beam injection system. To enhance the alignment and spatial resolution of Beam Emission Spectroscopy (BES) diagnostics, a remotely controlled translation stage capable of sub-millimeter accuracy has been developed. This stage allows dynamic adjustments of lines-of-sight (LOS) to improve alignment with individual beamlets and enable detailed scans of the beam for homogeneity and divergence studies. Preliminary tests demonstrate the system’s ability to measure beam divergence and intensity variations with high precision, validating its potential for optimizing beam performance. Future applications include advanced studies of single beamlet divergence, validation of emission codes, and support for MITICA diagnostics.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115413"},"PeriodicalIF":2.0,"publicationDate":"2025-09-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144997861","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 shinethrough detector and interlock for neutral beam injection operations on MAST-U","authors":"Roy McAdams,&nbsp;Philippe Jacquet,&nbsp;Ian Day,&nbsp;Effy Rose,&nbsp;Andrew Ash,&nbsp;Jake Ashton,&nbsp;Hana El-Haroun,&nbsp;Paul Jepson,&nbsp;David Keeling,&nbsp;Damian King,&nbsp;Robert King,&nbsp;Stephen Marsden,&nbsp;Alistair McShee,&nbsp;Maria Nicassio,&nbsp;Dean Payne,&nbsp;Robert Proudfoot,&nbsp;Ridhima Sharma,&nbsp;Jamie Smith,&nbsp;Christopher Tame,&nbsp;Thomas Wilson","doi":"10.1016/j.fusengdes.2025.115408","DOIUrl":"10.1016/j.fusengdes.2025.115408","url":null,"abstract":"<div><div>Neutral Beam Injection (NBI) is a powerful tool and is very commonly used for heating, current drive and diagnostics on magnetically confined devices for fusion power development. Not all the neutral beam power is deposited within the plasma. This shinethrough power must be dealt with at the first wall and any components irradiated by it must be protected against excessive heating. This paper describes the design, implementation and testing of a shinethrough detector and interlock for the MAST-U machine. It is based on the detection of the infra-red emission from the beam dump which can then be used to terminate the beam pulse if this exceeds a required threshold. The effects on the detected signal of loosely bound material (“dust”) on the beam dump is also discussed.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115408"},"PeriodicalIF":2.0,"publicationDate":"2025-09-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145005235","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":"Application of function parametrization for plasma position estimation in Aditya-U tokamak","authors":"Sameer Kumar ,&nbsp;Kumudni Tahiliani ,&nbsp;Praveenlal Edappala ,&nbsp;Praveena Kumari ,&nbsp;I Suresh ,&nbsp;Surya Kumar Pathak ,&nbsp;Daniel Raju ,&nbsp;Rakesh L Tanna ,&nbsp;Rohit Kumar ,&nbsp;Harshita Raj ,&nbsp;Joydeep Ghosh ,&nbsp;Aditya-U Team","doi":"10.1016/j.fusengdes.2025.115415","DOIUrl":"10.1016/j.fusengdes.2025.115415","url":null,"abstract":"<div><div>The fast and accurate measurement of plasma position for the tokamak control system is determined by the application of function parametrization on the magnetic probe data. In Aditya-U tokamak, a poloidal array of 16 probes is installed around the plasma column, and the plasma position has been estimated by an algorithm based on the function parametrization technique. The validation of the method is done by placing a current loop inside the vacuum vessel at different positions. It is found that the measurement accuracy improved as the number of probes was increased from 7 to 16. Also, to enable the real-time position measurement in the future, time integration of the probe output is enabled using the integrator circuits in 7 probes, which will be extended to all the probes.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115415"},"PeriodicalIF":2.0,"publicationDate":"2025-09-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144997862","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":"RCC-MRx Type P damage assessment methodologies for the design of Nuclear fusion reactor components","authors":"K. Degiorgio,&nbsp;M. Muscat,&nbsp;P. Mollicone","doi":"10.1016/j.fusengdes.2025.115407","DOIUrl":"10.1016/j.fusengdes.2025.115407","url":null,"abstract":"<div><div>The RCC-MRx (Design and Construction Rules for mechanical components of nuclear installations: high-temperature, research and fusion reactors) code is developed by the French Association for Design, Construction and Surveillance Rules of Nuclear Power Plant Components (AFCEN). RCC-MRx differentiates between the different type of component damage depending on the type of load set. A constant steady load results in Type P damage while a cyclic time varying load results in Type S damage. The work presented here deals with Type P damages. Two failure modes are of interest: immediate excessive deformation and immediate plastic instability. To prevent these failure modes, RCC-MRx presents an elastic, limit analysis and an elastoplastic approach. The elastic approach is guaranteed to give a safe but highly conservative design. The limit and elastoplastic approach require more computational effort and requires the availability of the relevant material properties. The latter approach leads to less conservative but still safe designs. Having a structurally safe and less conservative design is most of the time preferred because of issues of sustainability and cost. RCC-MRx has primarily been written for fission type nuclear reactors and process pressure vessels rather than for nuclear fusion reactors. Fusion reactors differ from fission ones both in the type of loading and also in the type of geometry. Some fusion reactor components have a box type shape rather than cylindrical or spherical as in fission type reactors and process pressure vessels. RCC-MRx has a section dedicated to the assessment of box type of structures. This paper considers the Type P damage rules for negligible creep and negligible irradiation applied to a simple hollow box section, modelled in cantilever mode under the action of various load sets. The results indicate that elastic analysis is the most conservative. Also, depending on overall deformation of the structure, the results show that the elastoplastic plastic instability rule limit may be reached before that of the elastoplastic excessive deformation rule. The elastoplastic rule for excessive deformation presents several challenges in its application and is discussed in more detail together with a methodology to overcome these difficulties. The finite element software Ansys® Academic Research Mechanical, Release 2023 R2 is used as the analysis tool.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115407"},"PeriodicalIF":2.0,"publicationDate":"2025-09-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144988172","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 optimization and fabrication method development for the HCCP TBM shield considering manufacturability","authors":"Jae Sung Yoon ,&nbsp;Suk-Kwon Kim ,&nbsp;Seong Dae Park ,&nbsp;Dong Won Lee ,&nbsp;Hyoseong Gwon","doi":"10.1016/j.fusengdes.2025.115409","DOIUrl":"10.1016/j.fusengdes.2025.115409","url":null,"abstract":"<div><div>The Helium Cooled Ceramic Pebble (HCCP) Test Blanket Module (TBM) is being co-designed in a Korean-EU collaboration. The HCCP TBM set consists of a TBM box and a TBM shield. This study aims to investigate the manufacturing process and propose a simplified manufacturing method to facilitate the fabrication of the HCCP TBM shield. The HCCP TBM shield structure comprises five blocks with piping connections consisting of water inlet/piping, helium inlet/piping, purge gas inlet/piping, and NAS I&amp;C piping that run through these five blocks and connect to the TBM manifold. The existing Helium Cooled Pebble Bed (HCPB) TBM shield design includes multiple reinforcement plates, which pose challenge in welding and inspection. In this study, we proposed a simplified internal structure for the existing HCPB TBM shield, evaluated its structural soundness through thermal-hydraulic and thermo-mechanical analyses, and suggested a new fabrication method that reduces the number of reinforcement plates to improve fabrication convenience while maintaining the structural integrity of the existing design.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115409"},"PeriodicalIF":2.0,"publicationDate":"2025-09-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144925818","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":"Multi-scale investigation into the irradiation hardening mechanism of reduced activation ferrite/martensitic (RAFM) steels under heavy ion irradiation","authors":"Yong Feng ,&nbsp;Hang Xu ,&nbsp;Tingping Hou ,&nbsp;Xiangheng Xiao ,&nbsp;Kaiming Wu","doi":"10.1016/j.fusengdes.2025.115414","DOIUrl":"10.1016/j.fusengdes.2025.115414","url":null,"abstract":"<div><div>The irradiation resistance of RAFM steels has received considerable attention in the development of candidate structural materials for application in advanced reactors. The present study enhances the mechanical properties and irradiation resistance of RAFM steels by precisely modulating the concent of Si and W. The results show that increasing Si while decreasing W content can make the grain refinement, dislocation line increase, and carbide precipitation of RAFM steel is more fine and diffuse, showing more excellent mechanical properties and lower irradiation hardening rate, and provides a new reference for the design and optimization of RAFM steels. Additionally, the contribution of dislocation loops to irradiation hardening was evaluated using the Dispersive Barrier Hardening (DBH) model, and irradiation-induced matrix atomic misalignment phenomenon and its triggered lattice distortion and dislocation proliferation mechanism were deeply analyzed at the atomic level in conjunction with geometric phase analysis (GPA), and furthermore irradiation-induced segregation of the matrix composition and formation of nano clusters of Si were also revealed by atom probe tomography (APT). These findings have established the nature of irradiation hardening in RAFM steels and may provide a better understanding of irradiation damage mechanisms.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115414"},"PeriodicalIF":2.0,"publicationDate":"2025-09-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144931994","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 permeation based hydrogen isotopes sensor and its testing in gas phase and molten Pb-Li","authors":"Rudreksh B. Patel ,&nbsp;Pragnesh Dhorajiya ,&nbsp;Sudhir Rai ,&nbsp;P.A. Rayjada ,&nbsp;Amit Muniya ,&nbsp;Amit Sircar ,&nbsp;Ankush Deoghar ,&nbsp;Rajendra Bhattacharyay ,&nbsp;Paritosh Chaudhuri","doi":"10.1016/j.fusengdes.2025.115411","DOIUrl":"10.1016/j.fusengdes.2025.115411","url":null,"abstract":"<div><div>For any nuclear fusion reactor, accurate measurement of bred tritium in the breeding blanket plays a key role for tritium management. These breeding blankets consist of mainly two types of tritium breeders. One is solid breeders, mainly lithium-based ceramic pebbles, and another is liquid breeders, the composite of lithium-based alloys. In a liquid-based breeding blanket, among various proposed breeding materials, a Pb-Li eutectic alloy is one of the most acceptable material in fusion reactors due to its good thermo-physical properties as well as its multiple applications, such as tritium breeder, neutron multiplier and coolant. However, the measurement of bred tritium in molten Pb-Li is equally challenging for any electronic diagnostics due to high-temperature compatibility issues and the corrosive nature of molten Pb-Li. Such a molten Pb-Li compatible sensor is not available commercially either. Therefore, the need for the development of a highly reliable and molten Pb-Li compatible sensor with a fast response time is obvious. Institute for Plasma Research (IPR) has designed, developed, and tested the permeation-based hydrogen isotope sensor in the gas phase (in UHP (Ultra High Pure) hydrogen gas) as well as in the liquid phase (in molten Pb-Li). In the present work, the experimental details, including testing setups for both gas phase and molten Pb-Li phase along with their testing results, are discussed.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115411"},"PeriodicalIF":2.0,"publicationDate":"2025-08-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144916273","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":"Optimization of the Laval nozzle for supersonic molecular beam injection by numerical simulation","authors":"J.H. Qiao ,&nbsp;B. Cao ,&nbsp;Z.Y. He ,&nbsp;W.K. Wang ,&nbsp;J.S. Yuan ,&nbsp;G.Z. Zuo","doi":"10.1016/j.fusengdes.2025.115412","DOIUrl":"10.1016/j.fusengdes.2025.115412","url":null,"abstract":"<div><div>Supersonic molecular beam injection (SMBI) is an efficient and routine technique for plasma fueling in the Experimental Advanced Superconducting Tokamak (EAST). To further improve the efficiency of particle injection, the effect of the nozzle throat diameter, divergent section length, and divergent section angle on the beam characteristics is simulated. Furthermore, an experimental test platform with a moveable pitot tube is developed and implemented to validate the reliability and accuracy of the numerical simulation. The results demonstrate that nozzle dimensions are crucial in determining the characteristics of the beam as it enters the vacuum chamber. A divergent half angle of about 20° is found to produce the most concentrated number density distribution near the axis. Increasing the throat diameter and the divergent section length also extends the high-density region near the nozzle exit. This paper presents optimization strategies for the design of nozzles in SMBI systems, offering useful guidance for the design and application of SMBI in future fusion devices.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115412"},"PeriodicalIF":2.0,"publicationDate":"2025-08-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144919813","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 UFO detection via infrared diagnostics in fusion reactors: Application to the WEST tokamak","authors":"Erwan Grelier,&nbsp;Julie Bonnail,&nbsp;Xavier Courtois,&nbsp;West Team","doi":"10.1016/j.fusengdes.2025.115401","DOIUrl":"10.1016/j.fusengdes.2025.115401","url":null,"abstract":"<div><div>We present UFOund, a deep-learning-based system for the automated detection and localization of moving particles (nicknamed UFOs) in infrared thermography data from the WEST tokamak. UFOs — small particles eroded from plasma-facing components (PFCs) — pose a significant disruption risk during experimental campaigns, accounting for approximately 35% of disruptions in WEST’s March–April 2023 experiments. Our approach processes sequences of infrared frames from WEST’s infrared thermography diagnostic using a spatiotemporal convolutional neural network. The model, trained on a manually annotated dataset of 295 infrared movies, achieves a balanced accuracy of 0.78 and an F1 score of 0.67 on an unseen test set with a detection threshold of 0.95, and gives very good qualitative results during operation at WEST. We further demonstrate a neural activation-based method to extract segmentation masks and approximate particle trajectories without additional manual annotations. Since November 2024, UFOund has been integrated into WEST’s post-pulse analysis pipeline, delivering near-real-time detection across all infrared views and significantly accelerating between-pulse decision making by the PFC Protection Officers.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115401"},"PeriodicalIF":2.0,"publicationDate":"2025-08-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144911549","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"An OpenMC model of the SPARC tokamak for the diagnostic scoping studies","authors":"X. Wang ,&nbsp;R. Gocht ,&nbsp;J. Ball ,&nbsp;S. Mackie ,&nbsp;E. Panontin ,&nbsp;E. Peterson ,&nbsp;P. Raj ,&nbsp;I. Holmes ,&nbsp;A.A. Saltos ,&nbsp;A. Johnson ,&nbsp;A. Grieve ,&nbsp;R.A. Tinguely","doi":"10.1016/j.fusengdes.2025.115390","DOIUrl":"10.1016/j.fusengdes.2025.115390","url":null,"abstract":"<div><div>This paper presents an OpenMC model for Monte Carlo neutronics simulations supporting the design scoping studies for various diagnostics for the SPARC tokamak. This constructive solid geometry (CSG) model uses realistic SPARC dimensions. Key components are modeled as a collection of homogenized cells of similar shapes with material composition preserved. A midplane port with a shielded opening, which allows a high flux of direct plasma neutrons reaching the tokamak hall and diagnostic hall neutron detectors, is modeled in greater detail for higher fidelity of neutron diagnostics simulations. The OpenMC model is verified with a CAD-based MCNP model for SPARC built by Commonwealth Fusion Systems, and it is found that the two models produce consistent tokamak hall neutron flux spectra. Compared to the CAD-based MCNP model, the CSG-based OpenMC model is easier to modify for parametric analyses to support rapid design iterations needed in a project like SPARC, which demands speedy engineering and physics design convergence. Multiple neutron diagnostics components are conceptualized and scoped using this model including the fast neutron collimators for the neutron camera and magnetic proton recoil neutron spectrometer, moderation and shielding for neutron flux monitors, and irradiation ends for the activation foil system. The uncollided neutron fluxes at detectors with collimated fields of view are verified using the optical code ToFu. The 14.1 MeV neutron peaks behind the collimators, which are planned to be 1–3 cm in diameter and 280 cm in length, are dominated by uncollided DT fusion neutrons. Activation foils have the best signal strength and uncollided/total neutron ratio at the plasma end of the foil channel in the port shielding.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115390"},"PeriodicalIF":2.0,"publicationDate":"2025-08-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144911558","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}