Fusion Engineering and Design最新文献

{"title":"Application of mini-flat and cylindrical test specimens to extract hardening law and ductility of neutron irradiated Eurofer97","authors":"Chih-Cheng Chang ,&nbsp;Dmitry Terentyev ,&nbsp;Alexander Bakaev ,&nbsp;Aleksandr Zinovev ,&nbsp;Daniele Del Serra ,&nbsp;Patricia Verleysen ,&nbsp;Thomas Pardoen","doi":"10.1016/j.fusengdes.2025.115072","DOIUrl":"10.1016/j.fusengdes.2025.115072","url":null,"abstract":"<div><div>Tensile properties such as strength and ductility are essential for structural integrity assessment of critical components. In the context of nuclear applications, the flat tensile geometry as compared to the reference standard cylindrical geometry offers a number of advantages in terms of material use efficiency, ease of machining, best packing under irradiation and simplified remote handling of active samples. Accordingly, the interchangeability of data extracted from flat and cylindrical specimens is a key issue. Furthermore, this interchangeability must be demonstrated for irradiated samples. Many metallic materials show significant reduction or even a full lack of uniform elongation after neutron irradiation, with most of the strain hardening regime taking place during the post-necking stage. As the necking development depends on geometry, this raises questions on the validity of changing the test specimen geometry. Here, the interchangeability of mini-flat and cylindrical tensile samples after neutron irradiation is investigated by combining experimental and computational analysis. The investigated material is EUROFER97 steel irradiated at 300 °C in the conditions relevant for the ITER fusion reactor. Finite element (FE) simulations are performed with a Gurson-type ductile fracture model parameterized based on the experimental tensile response. The hardening law extracted from mini-flat samples and applied to predict the stress-strain response of a cylindrical sample with 90 % accuracy or better in terms of total elongation, reduction of area, and fracture strength as compared to the direct experimental data obtained with cylindrical tensile specimen geometry.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115072"},"PeriodicalIF":1.9,"publicationDate":"2025-04-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143882680","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 influence of non-steady state operation of a PEM electrolyzer on hydrogen isotope separation in a CECE process","authors":"O. Balteanu,&nbsp;A. Bornea,&nbsp;I. Ștefan,&nbsp;I. Făurescu,&nbsp;G. Ana,&nbsp;C. Bucur,&nbsp;M. Zamfirache","doi":"10.1016/j.fusengdes.2025.115127","DOIUrl":"10.1016/j.fusengdes.2025.115127","url":null,"abstract":"<div><div>The electrolyzer is one of the main components of the Combined Electrolysis and Catalytic Exchange (CECE) process used to provide isotopic enrichment of hydrogen. The CECE process demands that the electrolyzer run under constant operating parameters (mainly the flowrate and water hold-up). The influence of the non-steady state regime for an electrolyzer equipped with a proton exchange membrane (PEM) stack cell, has been investigated, considering variations of the water hold-up, induced by the water management in the cathode and anode circuits. Based on a mathematical model written for a constant hold-up, a new mathematical model was developed to simulate the tritium enrichment, considering different variation of the hold-up between two limits determined from experimental data. Tests with tritiated water were carried out to evaluate the influence of the electrolyzer’s water hold-up variation on the isotopic separation process and to verify the mathematical model.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115127"},"PeriodicalIF":1.9,"publicationDate":"2025-04-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143882679","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":"Research on signal measurement algorithm of circular dot matrix high current sensor","authors":"Xu Wu ,&nbsp;Haihong Huang ,&nbsp;Sheng Dou ,&nbsp;Lan Peng","doi":"10.1016/j.fusengdes.2025.115056","DOIUrl":"10.1016/j.fusengdes.2025.115056","url":null,"abstract":"<div><div>In the field of current measurement of nuclear fusion devices, dot matrix high current sensors are widely used because of their advantages of high precision, light weight, wide range and low cost. According to the magnetic field generated by the measured conductor in the circular dot matrix current sensor ring and the Ampere's circuital law, the current value of the measured conductor can be deduced, so as to realize the non-contact current measurement. Because the Ampere's circuital law adopts the line integral equivalent of discrete points, when there are other energized conductors around the measured conductor, the crosstalk field will cause significant measurement errors. In order to solve this problem, a signal processing algorithm should be considered to improve the measurement accuracy and practicability. The effect of the traditional numerical average algorithm is limited by the number of Hall elements, and the convergence factor is difficult to be determined due to the contradiction between the convergence speed and steady state error of the adaptive Least Mean Square (LMS) algorithm. Based on the ideas of the two algorithms mentioned above, this article proposes the wavelet analysis - Kalman algorithm. This algorithm utilizes the known system model and noise statistical characteristics combined with signal estimation and correction to obtain the optimal algorithm parameters, which can further reduce the measurement error of dot matrix current sensor and improve the adaptability of the sensor to the environment. According to the results of simulation and experimental verification, it is concluded that the wavelet analysis - Kalman algorithm is the best among the three algorithms, which can well suppress the influence of crosstalk field and random noise on the measurement results, and greatly improve the measurement accuracy of the sensor.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115056"},"PeriodicalIF":1.9,"publicationDate":"2025-04-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143879113","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 studies of liquid tin capillary porous system at the OLMAT high heat flux facility","authors":"M. Reji ,&nbsp;E. Oyarzábal ,&nbsp;A. de Castro","doi":"10.1016/j.fusengdes.2025.115013","DOIUrl":"10.1016/j.fusengdes.2025.115013","url":null,"abstract":"<div><div>Extreme heat and particle fluxes at the divertor tiles of a fusion device present one of the most critical challenges in achieving sustainable fusion energy. Solid plasma-facing components (PFCs) typically suffer from cracking, erosion, and melting, particularly during transient events, limiting their durability and effectiveness. In contrast, liquid metal PFCs may offer several advantages over their solid counterparts, primarily through their intrinsic resistance to permanent damage and the ability to dissipate heat via multiple channels, thereby enhancing the resilience and longevity of PFCs. This work investigates the thermal behaviour of a liquid tin (Sn) capillary porous system (CPS) target exposed to a high-energy particle beam at the OLMAT high heat flux (HHF) facility. To obtain accurate temperature measurements of the target, an iterative calibration method was developed, accounting for the metallization of the diagnostic window due to the shot-by-shot deposition of eroded Sn, an effect that partially affected the measurements.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115013"},"PeriodicalIF":1.9,"publicationDate":"2025-04-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143882681","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":"Operation and remote collaboration tools in view of the ITER neutral beam test facility experimental campaigns","authors":"Nuno Cruz ,&nbsp;Alastair Shepherd ,&nbsp;Gabriele Manduchi ,&nbsp;Cesare Taliercio ,&nbsp;Paolo Barbato ,&nbsp;Rita Delogu ,&nbsp;Gianluigi Serianni ,&nbsp;Andrea Rigoni ,&nbsp;Luca Trevisan ,&nbsp;Adriano Luchetta","doi":"10.1016/j.fusengdes.2025.115027","DOIUrl":"10.1016/j.fusengdes.2025.115027","url":null,"abstract":"<div><div>The ITER Neutral Beam Test Facility (NBTF) serves as a crucial testing ground for the development and validation of neutral beam injection systems essential for ITER’s fusion power plant. For this purpose two experimental campaigns in the two prototypes (SPIDER and MITICA) are conducted within the NBTF.</div><div>Collaborative efforts at the NBTF, involving scientists from different institutions across Europe, India and Japan, emphasize the importance of data sharing and advanced computing infrastructures. Common computing platforms facilitate analysis of scientific data, aiding informed decision-making. Remote collaboration tools play a crucial role in fostering communication among global experts. The involvement of EUROfusion and ITER experts in strict collaboration accelerates ITER’s neutral beam heating and diagnostic systems development. Moreover, remote participation, data visualization, and efficient operation tools are essential for enhancing accessibility and collaboration in scientific research. These tools enable researchers to remotely access and control experimental facilities, visualize data in real-time, and collaborate with colleagues worldwide.</div><div>This paper presents the design and implementation of operation tools based on EPICS and MDSplus, developed using Grafana, Python, and NodeJS, to enhance remote participation, data visualization, plant operation and collaboration in fusion experiments. A key improvement in SPIDER’s pulse repetition rate, now reaching 300 s, was achieved through pre-approved pulses and automatic repetition, significantly increasing the average daily pulses. By using ITER CODAC standards and open-source tools like PostgreSQL, Redis, Grafana, MDSplus, and EPICS, we have optimized both operations and remote collaborations, improving security and efficiency in real-time trend visualization, automating experimental setup verification, optimizing experimental time and performance using real-time pulse sequence reconfiguration.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115027"},"PeriodicalIF":1.9,"publicationDate":"2025-04-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143879112","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":"Preparation of KSTAR pellet injection system for advanced plasma scenarios","authors":"SooHwan Park,&nbsp;HyunMyung Lee,&nbsp;JaeIn Song,&nbsp;InSik Woo,&nbsp;KwangPyo Kim,&nbsp;KapRai Park","doi":"10.1016/j.fusengdes.2025.115121","DOIUrl":"10.1016/j.fusengdes.2025.115121","url":null,"abstract":"<div><div>The 20 Hz pellet injection system (PIS) was installed at KSTAR (Korea Superconducting Tokamak Advanced Research) in 2016. The pellet injector has already demonstrated its ability to continuously produce deuterium ice rods and inject pellets at a frequency of 20 Hz for up to 300 s. This system allows for the injection of pellets with varying sizes, velocities, and frequencies, enabling a wide range of plasma experiments at KSTAR. As KSTAR advances toward more complex and high-performance plasma scenarios—incorporating modified PFCs (plasma-facing components) and enhanced heating systems—the pellet injection system must be upgraded accordingly. To support these developments, the PIS underwent maintenance and optimization. Following these improvements, the system achieved reliable pellet injection at approximately 200 m/s across various frequencies, with an operational reliability exceeding 95 %. The density profile during injection was monitored using the TCI (two-color interferometer) system. This paper discusses the current status of the pellet injection system following its regular maintenance and performance tests during plasma experiments. Additionally, we outline plans for further enhancements, including improvements to the vacuum pumping system to support the evolving plasma operation requirements at KSTAR.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115121"},"PeriodicalIF":1.9,"publicationDate":"2025-04-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143882737","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":"Thermo-mechanical analysis of DTT Vacuum Vessel Thermal Shield","authors":"S. Del Nero ,&nbsp;M. Fulici ,&nbsp;G. Barone ,&nbsp;R. Bonifetto ,&nbsp;M. Dalla Palma ,&nbsp;P. Fanelli","doi":"10.1016/j.fusengdes.2025.115090","DOIUrl":"10.1016/j.fusengdes.2025.115090","url":null,"abstract":"<div><div>The Thermo-structural behavior of the Vacuum Vessel (VV) and Vacuum Vessel Thermal Shield (VVTHS) of the Divertor Tokamak Test (DTT) project under thermal loads and piping-induced stresses was evaluated using Finite Element Analysis (FEA). The THS consists of two shells, respectively referred as inner THS and outer THS, with Cooling Pipes (CPs) welded to the innermost. The VV and THS are mechanically coupled by using bolts that constrain relative displacements. A Finite Element Model (FEM) was developed using shell elements for VV and VVTHS, beam elements for CPs and bolts, and coupling equations to simulate bolted connections. The analysis incorporated temperature-dependent material properties and periodic cycling conditions for applied on VV. Results provide insight into the displacement and stress distributions across the components, informing the structural integrity and future design optimization of the DTT VVTHS system.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115090"},"PeriodicalIF":1.9,"publicationDate":"2025-04-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143879111","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":"In-situ detector theoretical design for low-activity concentration tritiated water based on plastic scintillator thin film flow cell","authors":"Xiaoyu Li ,&nbsp;Zhi Chen","doi":"10.1016/j.fusengdes.2025.115104","DOIUrl":"10.1016/j.fusengdes.2025.115104","url":null,"abstract":"<div><div>In order to ensure radiation safety and control the potential risk of tritium, the in-situ measurement technology of low radioactive concentration tritiated water has wide practical demands.<strong>A novel detector was theoretically designed</strong> utilizing plastic scintillator thin films (PSTFs) and silicon photomultiplier arrays (SiPMs) to achieve this objective. Key parameters such as sample chamber thickness, plastic scintillator thickness, and the number of sample chambers were analyzed using Monte Carlo simulations, thoroughly evaluating factors influencing energy deposition, optical transmission, detection efficiency, and minimum detectable activity concentration (MDAC). The results demonstrated that the system achieved a detection efficiency of 22.5% with the MDAC of 6.909 Bq/mL for tritiated water over a counting time of one minute. This compact and highly sensitive detector configuration is well-suited for a range of applications in environmental monitoring and radiation safety.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115104"},"PeriodicalIF":1.9,"publicationDate":"2025-04-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143873712","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":"Structural analysis and optimization of mechanical multi-pipe connection for DEMO Upper Port","authors":"K.J. Büscher,&nbsp;A. Azka,&nbsp;M. Mittwollen","doi":"10.1016/j.fusengdes.2025.115102","DOIUrl":"10.1016/j.fusengdes.2025.115102","url":null,"abstract":"<div><div>This paper presents the structural optimization of a mechanical multi-pipe connection (MPC), which consists of multi-pipe flange connected with a threaded bolt connection, for use in DEMO Upper Port. Mechanical pipe connections are currently being researched in the fusion context as they offer faster operating time of the pipe connections compared to conventional welded connections. However, the main consideration is that the pipe connection must be sealed against a high vacuum at both room temperature and high temperature. To ensure the necessary tightness during the entire process, the metal seals required must be sufficiently preloaded in all operating conditions. In addition, strict space availability limits the overall shape and dimension of the MPC. For this purpose, a structural analysis and subsequent topology optimization of the flange connection is carried out using the commercially available FEA software <span>Abaqus</span>®. The result of the topology optimization, taking into account suitable boundary conditions, is a design for the flange which, in addition to achieving sufficient deformation of the seals throughout, also smoothed out the stress peaks present in previous designs. However, the design cannot yet be produced in its current form, as cavities have also been created within the flange. The manufacturability of the flange must therefore be investigated in a subsequent second step and the design adapted accordingly. In this paper, a design draft of a MPC for use in DEMO Upper Port is presented, which fulfills all the necessary boundary conditions, but still needs to be revised regarding its manufacturability.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115102"},"PeriodicalIF":1.9,"publicationDate":"2025-04-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143877089","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":"Assessment of magnetic smearing effects for the MAST-U beam emission spectroscopy system","authors":"P. Balazs ,&nbsp;O. Asztalos ,&nbsp;M.S. Fonyi ,&nbsp;S. Thomas ,&nbsp;D. Dunai ,&nbsp;G.I. Pokol ,&nbsp;MAST-U Team","doi":"10.1016/j.fusengdes.2025.115075","DOIUrl":"10.1016/j.fusengdes.2025.115075","url":null,"abstract":"<div><div>The MAST-U beam emission spectroscopy (BES) diagnostic measures D<span><math><msub><mrow></mrow><mrow><mi>α</mi></mrow></msub></math></span> emission from the on-axis neutral deuterium heating beam. From the measured light intensity variations, the local density fluctuations can be characterized, which is a valuable method to study both core and edge plasma turbulence, as well as various MHD phenomena. The predecessor 2D turbulence imaging BES diagnostic system was installed on MAST in 2010, with the first mirror location optimized so that measurements had the best achievable poloidal and radial resolution at a specific observation location along the beam. This system was operational in the M8 and M9 campaigns and was successfully used in several physics programs. In the MAST Upgrade, the BES system was relocated due to technical constraints and installed in a dedicated port. The assessment of the new configuration’s spatial resolution was required so that the measurements could be interpreted correctly and consistently. The spatial resolution assessment was performed for multiple observation locations covering the minor radius of the device. Our study concentrated on the dominant smearing caused by the misalignment between the lines of sight and the magnetic field lines within the beam geometry. For comparison, the same analysis was also performed on pre-upgrade scenarios. The relocation of the observation system had a slightly negative effect on the poloidal resolution due to an increase in the misalignment between the lines of sight and the magnetic field lines at the beam location. However, the values in general remain in the region of the old setup, posing no obstacle to the continued utilization of the system for density fluctuation measurements.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115075"},"PeriodicalIF":1.9,"publicationDate":"2025-04-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143873715","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}