Fusion Engineering and Design最新文献

{"title":"Effect of ion irradiation on the surface electrical conductivity of CuCrZr at high frequencies","authors":"C. Marraco Borderas ,&nbsp;J. Genoud ,&nbsp;R. Chavan ,&nbsp;T.P. Goodman ,&nbsp;P. Petersson ,&nbsp;A. Xydou ,&nbsp;A. Mas Sánchez ,&nbsp;D. Birlan ,&nbsp;J-P. Hogge","doi":"10.1016/j.fusengdes.2025.115197","DOIUrl":"10.1016/j.fusengdes.2025.115197","url":null,"abstract":"<div><div>The ohmic losses in the Electron Cyclotron Heating system of the DEMO nuclear fusion reactor depend on the surface electrical conductivity of the material at the frequency of the mm-wave beams generated in the gyrotrons. To reduce the ohmic losses, many components will be made or coated with materials with high electrical conductivity, such as CuCrZr. In addition, in the Equatorial Port Plug these components will also have to withstand very high irradiation doses. The objective of this work was to study the effect of ion irradiation on the surface electrical conductivity of CuCrZr at frequencies between 140 and 170 GHz. The samples were irradiated with Cu ions at 1, 3 and 10 dpa, which did not entail any change in the surface roughness, and were measured using a Fabry-Pérot resonator. In addition, SEM-EDX analysis was performed to chemically characterize the surface of the samples. The results show that the surface electrical conductivity is reduced by more than 40 % at 10 dpa, which would translate in a significant increase of the ohmic losses, rising the cooling needs of the components in the Electron Cyclotron Heating system.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115197"},"PeriodicalIF":1.9,"publicationDate":"2025-05-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144138528","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 design progress of neutral beam duct liner remote handling tool in ITER blanket remote handling system","authors":"Tomoyuki ITO,&nbsp;Yuto NOGUCHI,&nbsp;Nobukazu TAKEDA","doi":"10.1016/j.fusengdes.2025.115217","DOIUrl":"10.1016/j.fusengdes.2025.115217","url":null,"abstract":"<div><div>This paper presents the system design of the Neutral Beam Duct Liner (NBDL) remote handling system for the ITER experimental fusion reactor. All maintenance inside the Vacuum Vessel (VV), such as maintenance of Blanket Modules, Divertors, and NBDL panels, needs to be performed remotely since the environment inside the VV will become highly radioactive once fusion operation begins. The NBDL Remote Handling (NBDL-RH) system is a subsystem of the Blanket Remote Handling System (BRHS) and is designed to be handled by the Vehicle Manipulator (VMNP) of BRHS. One of the key design challenges of this work is to develop a configuration that enables the NBDL-RH Tool to operate inside the Neutral Beam Duct independently from the VMNP, while also achieving operational efficiency. The NBDL-RH system was configured to consists of the NBDL-RH Tool, which functions within the Neutral Beam Duct; utility subsystem such as power supply and signal transmission; in-porting and out-porting subsystem for transporting the NBDL-RH Tool, in its various design configurations, into and out of the VV by means of cask transfers; and another supporting subsystem. To this end, the NBDL-RH Tool has been conceptually designed in a modular configuration incorporating a Tool Changer. This approach reduced the number of cask transfers by approximately one-third compared to a system without a Tool Changer. Furthermore, the modular configuration minimized the amount of manual reassembly work required in the Hot Cell Facility.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115217"},"PeriodicalIF":1.9,"publicationDate":"2025-05-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144154427","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":"Deuterium retention properties and bubble behaviors of Be12Ti after irradiation with D+ at high temperature","authors":"Yutaka Sugimoto ,&nbsp;Mitsutaka Miyamoto ,&nbsp;Jae-Hwan Kim ,&nbsp;Taehyun Hwang ,&nbsp;Suguru Nakano ,&nbsp;Masaru Nakamichi ,&nbsp;Hiroyasu Tanigawa","doi":"10.1016/j.fusengdes.2025.115220","DOIUrl":"10.1016/j.fusengdes.2025.115220","url":null,"abstract":"<div><div>In the Japanese demonstration (JA DEMO) fusion reactor, Be₁₂Ti blocks as a neutron multiplying material and Li₂TiO₃ pebbles as a breeding material will be planned to set in the blanket. When the replacement of the blanket due to the life of the structure materials, tritium generation with 200 appm T in Be₁₂Ti blocks can be anticipated. The Be₁₂Ti blocks containing tritium may cause several problematic issues in JA DEMO. The objective of this study aimed to evaluate the correlation between deuterium (D) retention properties and the bubble behaviors in Be₁₂Ti.</div><div>We investigated the D retention properties in the Be₁₂Ti samples, which were irradiated with D⁺ ions at R.T.-873 K using thermal desorption spectroscopy. The bubble behaviors in the thin Be₁₂Ti samples were observed under annealing using in-situ transmission electron microscope (TEM). And the Be samples were prepared to be comparable with Be₁₂Ti and done similarly to the same experiment.</div><div>The D desorption peaks were confirmed from the mechanical-polished and electropolished Be₁₂Ti samples after irradiation with D⁺ at R.T. and high temperature. For both mechanical-polished and electropolished Be₁₂Ti samples, the desorption peak shifted to higher temperatures with increasing irradiation temperatures. In-situ TEM observed the bubble behaviors, and Most of the bubbles wouldn’t change in thin Be₁₂Ti samples after irradiation with D⁺ at R.T. and 673 K during annealing (∼1073 K). These results indicate that no correlation between the deuterium releases and the bubble behavior in Be₁₂Ti until 1073 K.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115220"},"PeriodicalIF":1.9,"publicationDate":"2025-05-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144134204","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 methodology for TIE detection and tracking for JET’s experimental cameras","authors":"A. González Ganzábal ,&nbsp;G.A. Rattá ,&nbsp;S. Dormido-Canto ,&nbsp;P. Carvalho ,&nbsp;S. Silburn ,&nbsp;I. Coffey ,&nbsp;I. Balboa ,&nbsp;JET Contributors ,&nbsp;WPTE contributors","doi":"10.1016/j.fusengdes.2025.115164","DOIUrl":"10.1016/j.fusengdes.2025.115164","url":null,"abstract":"<div><div>Transient Impurity Events (TIEs), also referred as UFOs, are small particles found in nuclear fusion devices formed as by-products of plasma operation. TIEs have been a main focus of study due to their effects on the behaviour of the plasma. Here, we evaluate the statistical effects of TIEs on disruptions in JET using cameras, often underutilised diagnostics in plasma studies. First, in a dataset of 876 discharges, it was found that in 38.4% of pulses with TIEs, a disruption was detected. Out of these, 11.9% occurred in a critical time interval that indicates that the TIE might have caused the disruption. 24.1% of the TIEs found were originated right after one. A review of the TIE composition, position and speed has also been performed in a reduced dataset of 77 pulses, resulting in the dominant presence of W and Ti TIEs over the rest (33.7% and 29.9%), most notably from the divertor and the Upper Dump Plate Tiles (UDPT) (18.2% and 27.3%, respectively). The analysis of TIE speed, however, did not yield further insights into their disruptive behaviour.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115164"},"PeriodicalIF":1.9,"publicationDate":"2025-05-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144138524","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":"New developments and verification of fusion blanket simulation capabilities in the MOOSE framework","authors":"Trevor Franklin ,&nbsp;Casey Icenhour ,&nbsp;Pierre-Clément A. Simon ,&nbsp;Paul Humrickhouse ,&nbsp;Fande Kong ,&nbsp;Lane B. Carasik","doi":"10.1016/j.fusengdes.2025.115128","DOIUrl":"10.1016/j.fusengdes.2025.115128","url":null,"abstract":"<div><div>Multiphysics modeling capabilities have a crucial role to play in the accelerated deployment of fusion energy. To that end, we developed new multiphysics fusion blanket simulation capabilities in the Multiphysics Object-Oriented Simulation Environment (MOOSE). Firstly, we expanded on the existing capabilities of the previously published work, by coupling 3D tritium transport modeling capabilities using the Tritium Migration Analysis Program, version 8 (TMAP8) to an existing tool including thermal hydraulics, fully three-dimensional (3D) heat transfer, and loosely coupled neutronics analysis. Secondly, we performed a thorough verification of the new capabilities and increased testing code coverage to meet MOOSE’s software quality standards. The MOOSE framework follows a strict software quality assurance plan to be Nuclear Quality Assurance, Level 1 compliant. The new multiphysics fusion blanket simulation capabilities are now held to the same standard. Thirdly, to demonstrate MOOSE’s new fusion blanket modeling capabilities, we performed a fully integrated, multiphysics simulation of a 3D solid ceramic breeder blanket design. This proof-of-concept simulation provides the temperature and tritium distribution across the blanket. The combined efforts towards software quality and the development of multiphysics coupling capabilities provide an effective and reliable framework for modeling solid ceramic fusion blankets using MOOSE.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115128"},"PeriodicalIF":1.9,"publicationDate":"2025-05-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144134202","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 new tubular ironless linear induction motor using non-interrupted winding method","authors":"Jiarong Fang ,&nbsp;Andrei Khodak ,&nbsp;Keith Corrigan ,&nbsp;Gregory Appel ,&nbsp;Peter Titus ,&nbsp;Lucas Moser ,&nbsp;Maarten De Bock","doi":"10.1016/j.fusengdes.2025.115200","DOIUrl":"10.1016/j.fusengdes.2025.115200","url":null,"abstract":"<div><div>The ironless linear induction motor device can be used for any application which requires a large motion span or rotation restrictedly by the ironless feature due to the strong magnetic field environment. One of the possible applications is ITER diagnostics shutters. The tokamak reactor systems have a severe radiation issue during the operation. The traditional Kapton-insulated wires have significantly lower radiation resistance than an expected large radiation dose at ITER Motion Stark Effect (MSE) shutter location. Furthermore, the traditional single-sided linear induction motor winds the wire to make the N-turn pitch coils independently and then connect them in series to make a one-phase winding. Therefore, it is a big challenge to make so many radiation-protection connectors in such a limited space as inside the vacuum vessel of fusion reactors. The approved mineral-insulated kinds of cables need a large bend radius for the end turns, so the traditional single-sided linear motor with two-layer three-phase windings need to be upgraded to the tubular linear motors.</div><div>The new proposed tubular ironless linear induction motor can not only overcome the large bend radius issue with the mineral-insulated cables but also allow the motor coils wound continuously around the tubular-shaped stator, forward and backward N times to make a N-turn winding for each phase, in order to resolve the radiation protection issue with the winding connection. The 3D transient Maxwell electromagnetic model with a tubular three-phase linear induction motor has been analyzed. This paper will present the detailed design and winding method of ironless linear induction motor actuators, and results of the 3D transient numerical simulation of the actuator performance.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115200"},"PeriodicalIF":1.9,"publicationDate":"2025-05-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144134022","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 integrated simulator towards a digital twin for MW-class Gyrotrons for fusion reactors","authors":"Elia Novarese ,&nbsp;Antonio Cammi ,&nbsp;Rosa Difonzo ,&nbsp;Carolina Introini ,&nbsp;Laura Savoldi","doi":"10.1016/j.fusengdes.2025.115157","DOIUrl":"10.1016/j.fusengdes.2025.115157","url":null,"abstract":"<div><div>In magnetic-confinement fusion reactor technology, gyrotrons are foreseen to deliver power to the plasma through mm-microwaves at a pre-determined frequency within the range of <span><math><mrow><mn>80</mn><mo>−</mo><mn>200</mn><mspace></mspace><mspace></mspace><mi>G</mi><mi>H</mi><mi>z</mi></mrow></math></span> and power of <span><math><mrow><mn>1</mn><mo>−</mo><mn>2</mn><mspace></mspace><mspace></mspace><mi>M</mi><mi>W</mi></mrow></math></span>. Today, only specific models focusing on specific components or specific physics of the gyrotron are available, but an overall simulator is missing. The development of a comprehensive simulator capable of describing the entire gyrotron behaviour, including its inherent nonlinearities, is crucial for accurate simulations, sensitivity analyses, operational optimization, and control purposes and represents an essential part for the definition of a new digital twin. The gyrotron is a complex device governed by multi-physics phenomena, thus the development of a simulator capable to simulate its complex dynamics requires the knowledge of the fundamental physics that describes the behaviour of all components. The goal is to develop a complete simulator of gyrotron, based on a fixed geometry and materials already selected, describing the components as objects which elaborate parameter inputs to get outputs. It is shown that in this way, the components can be seen as different boxes, the interconnections of which allow to build the simulator for the entire device. By adopting a state–space formulation, the interconnection between input and output of different blocks can be effectively managed, and through system linearization, an efficient stability analysis can be performed. In this work, each component is presented, together with its physics. The input and output parameters are then identified in order to understand how they influence the coupling between the component models and their connection. This procedure will help to build in future works the simulator of the gyrotron, aiming at developing a digital twin for it. The latter, articulated from the aggregation of simpler component models, could become a useful tool to perform complex simulations, stability analysis, optimization and control.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115157"},"PeriodicalIF":1.9,"publicationDate":"2025-05-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144125365","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":"Effect of vacancy, self-interstitial atoms and transmutation rhenium on lattice thermal conductivity in tungsten","authors":"Daigo Kanamori ,&nbsp;Keisuke Mukai ,&nbsp;Takeo Hoshi ,&nbsp;Takuya Nagasaka","doi":"10.1016/j.fusengdes.2025.115195","DOIUrl":"10.1016/j.fusengdes.2025.115195","url":null,"abstract":"<div><div>Tungsten (W) is a promising candidate for plasma-facing components (PFCs) because of its excellent properties, such as a high melting point and high thermal conductivity (TC). However, neutron irradiation introduces lattice defects and transmutation, leading to the degradation of material properties. In this study, the reduction of lattice thermal conductivity (LTC) in W caused by point defects, such as vacancies, self-interstitial atoms, substitutional rhenium (Re) and interstitial Re were calculated using molecular dynamics at 300 K and 800 K using equilibrium molecular dynamics (EMD). Also, we calculate phonon density of state (DOS) and discuss how the point defects change the phonon DOS of crystalline W. It was found that interstitial Re decreased LTC most significantly, followed by random self-interstitial atoms, vacancies, and substitutional Re. Additionally, it was found that the calculation results of the phonon-phonon scattering rate by EMD deviate significantly from those by the ab initio method.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115195"},"PeriodicalIF":1.9,"publicationDate":"2025-05-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144125364","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":"Test of RANS turbulence models for application on ribbed duct flows by comparison to experimental flow field and heat transfer data","authors":"S. Gordeev,&nbsp;F. Arbeiter,&nbsp;S. Ruck","doi":"10.1016/j.fusengdes.2025.115190","DOIUrl":"10.1016/j.fusengdes.2025.115190","url":null,"abstract":"<div><div>The aim of the study is to find the most accurate and robust CFD solution that can be applied to cases with flow separation and heat transfer induced by ribs.</div><div>The first part of the paper analyses the ability of six Reynolds-Averaged Navier Stokes (RANS) models to reproduce the separated air flow (isothermal) in a transversally ribbed rectangular channel, in comparison to flow field data measured with Laser Doppler Anemometry.</div><div>In the next step the models were evaluated in the prediction of convective heat transfer and pressure drop in v-ribbed heated gas cooling channel measured in HETREX-PT (HEat TRansfer Enhancement eXperiments - Pressure, Temperature) experiments at KIT, with a channel geometry close to the intended application.</div><div>Turbulence models such as standard <em>k-ω</em> SST (SST) and Realisable <em>k-ε</em> model (KE-RE) as well as models derived on the basis of the elliptic blending approach: Reynolds Stress model (RSM), <em>v</em>2-<em>f</em> model (V2F), Elliptic Blending model (KE-EB) and Lag-Elliptic Blending model (KE-LAG-EB) were selected.</div><div>The flow conditions (flow rate, heating power) were scaled from helium flow in HCPB (P=8MPa Tin=300 °C) to air at 0.4 MPa and 24 °C by the two similarity quantities Reynolds number and the dimensionless heating rate <em>q</em>⁺. The rib-arrays consist of upstream pointing transversally oriented 60° V-shaped ribs. The comparative analysis of the turbulence models deals with the investigation of the distribution of vortex structures caused by ribs and their influence on heat transfer.</div><div>The flow between attached ribs calculated by <em>k-ω</em> SST is almost completely detached, leading to a significant under-prediction of heat transfer. The standard <em>k-ε</em> model underestimates the turbulence production at the leading edge and in the shear layer over the recirculation region and, thus, the heat transfer between the ribs. The elliptical blending models give results that are closer to the measurements. The RSM, V2F and KE-EB models perform better agreements with experimental data. The V2F model provides the best prediction and is found to be most suitable for the simulation of heat transfer in the presented rib-structured channel flow.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115190"},"PeriodicalIF":1.9,"publicationDate":"2025-05-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144125366","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 and structural analysis of W-7X first wall graphite tiles under direct NBI loads","authors":"Vojtěch Smolík ,&nbsp;Mikhail Khokhlov ,&nbsp;Axel Lorenz ,&nbsp;Samuel Lazerson ,&nbsp;Victor Bykov ,&nbsp;Paul McNeely ,&nbsp;W7-X team","doi":"10.1016/j.fusengdes.2025.115178","DOIUrl":"10.1016/j.fusengdes.2025.115178","url":null,"abstract":"<div><div>Thermo-mechanical analysis of the Wendelstein 7-X neutral beam dump is presented focusing on failure phenomena resulting from strong impulsive thermal loading of the graphite tiles. One of the plasma heating systems of the Wendelstein 7-X stellarator is Neutral Beam Injection (NBI). There are two NBI boxes with currently a total injected hydrogen beam power of 7 MW and a pulse length up to 5 s. Each NBI box can be operated with four positive ion neutral injectors (PINI). A total of three PINIs were used simultaneously in the last operation campaign in 2022. NBI is highly important for the W7-X physics program, thus increasing NBI power is planned in the next operation phase. A portion of the NBI power passes through the plasma, creating a region of the first wall (FW) with a significantly increased heat load. This region, called the beam dump, could be a limiting factor for the NBI pulse length and thus it requires a precise remodeling of all constituents before the 2024/2025 operation phases to prevent repeated structural damage to this area. Since the graphite tiles are attached by multiple bolts to the CuCrZr heat sinks, the thermal expansion of graphite can induce significant stress in the graphite. The safety limiting factor is the induced thermal stress in the graphite tile due to the NBI beam power load. ANSYS Mechanical model was developed, including the bolted connections, and analyzed to examine the effect of the heat load on the FW components and to evaluate the maximal allowed duration of the NBI beam. A coupled transient simulation of the thermal and structural analysis is performed. The calculation used the NBI heat loads on the FW surfaces estimated by the BEAMS3D code. This paper presents the results of the numerical analysis and the related operating limits.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115178"},"PeriodicalIF":1.9,"publicationDate":"2025-05-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144131096","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}