Fusion Engineering and Design最新文献_第9页

Pellet fragmentation studies for the ITER disruption mitigation system ITER干扰减缓系统的颗粒碎裂研究

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-05-05 DOI: 10.1016/j.fusengdes.2025.115132

Gábor Kocsis , Gergely Bartók , Attila Buzás , Gábor Cseh , Dániel Dunai , Gábor Gárdonyi , Sándor Hegedűs , Marcell Málics , Domonkos Nagy , Dániel Réfy , Tamás Szepesi , Márton Vavrik , Erik Walcz , Sándor Zoletnik , Stefan Jachmich , Uron Kruezi , Michael Lehnen

{"title":"Pellet fragmentation studies for the ITER disruption mitigation system","authors":"Gábor Kocsis , Gergely Bartók , Attila Buzás , Gábor Cseh , Dániel Dunai , Gábor Gárdonyi , Sándor Hegedűs , Marcell Málics , Domonkos Nagy , Dániel Réfy , Tamás Szepesi , Márton Vavrik , Erik Walcz , Sándor Zoletnik , Stefan Jachmich , Uron Kruezi , Michael Lehnen","doi":"10.1016/j.fusengdes.2025.115132","DOIUrl":"10.1016/j.fusengdes.2025.115132","url":null,"abstract":"<div><div>The thermal and mechanical loads during disruptions are a major threat for large reactor-class tokamak devices. Therefore, shattered pellet injection (SPI) is selected as the baseline technology for the ITER Disruption Mitigation System (DMS). The aim of DMS Support Laboratory located at the HUN-REN Centre for Energy Research is to study the production, launch and shattering of cryogenic protium, deuterium, and neon pellets in the ITER geometry. This paper reports on the fragment analysis procedure and the first results of the fragment plume investigation performed with pellets made of the above materials and accelerated to a speed ranging between 70 and 500m/s. The experimental results show that the fragment plume consists of macroscopic and microscopic fragments. The shattering of about 500 m/s protium and deuterium pellets resulted in a most common fragment size of a few millimeters, while at lower velocities around 250m/s still the same few millimeters size fragments dominate but larger fragments have a higher proportion in the mass distribution. At low velocities (70 m/s) for neon pellets most of the pellet mass was converted into large fragments (from 10 to 20 mm ). The results are also compared with the Parks pellet fragmentation model.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"217 ","pages":"Article 115132"},"PeriodicalIF":1.9,"publicationDate":"2025-05-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143904523","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}

引用次数: 0

Electromagnetic design optimization of the inboard shielding blanket for the volumetric neutron source 体积中子源舱内屏蔽层的电磁设计优化

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-05-05 DOI: 10.1016/j.fusengdes.2025.115122

Ivan Alessio Maione , Christian Bachmann , Irene Pagani , Riccardo Lombroni

{"title":"Electromagnetic design optimization of the inboard shielding blanket for the volumetric neutron source","authors":"Ivan Alessio Maione , Christian Bachmann , Irene Pagani , Riccardo Lombroni","doi":"10.1016/j.fusengdes.2025.115122","DOIUrl":"10.1016/j.fusengdes.2025.115122","url":null,"abstract":"<div><div>This work presents a set of electromagnetic (EM) analyses performed on the Volumetric Neutron Source (VNS), a facility designed to test fusion reactor components under near-reactor conditions. The study investigates eddy currents, Lorentz forces, and halo current distributions in critical components such as the shield blanket, divertor, vacuum vessel, and thermal shield under transient electromagnetic scenarios. Key events such as Vertical Displacement Events (VDEs), analyzed using MAXFEA, and toroidal field coil fast discharges (TFCFDs) are implemented in finite element method models developed in ANSYS to calculate the induced EM loads.</div><div>Focus is given to the inboard blanket's design, with modifications to reduce EM loads by optimizing electrical contacts, refining material configurations, and incorporating ferromagnetic elements to satisfy the requirements for the attachment system. Results provide essential feedback for structural improvements and advancing the VNS toward operational feasibility. The methodology and findings contribute broadly to fusion reactor design by addressing critical challenges posed by EM transients.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"217 ","pages":"Article 115122"},"PeriodicalIF":1.9,"publicationDate":"2025-05-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143904524","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}

引用次数: 0

Manufacturing Assessment of the Simplified Full-Scale Prototype of Diagnostics Shield Module (DSM) for Application of ITER Upper Port 18 用于ITER上端18口的诊断屏蔽模块（DSM）简化全尺寸样机制造评估

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-05-03 DOI: 10.1016/j.fusengdes.2025.115141

Heejin Shim , Jaemin Kim , MunSeong Cheon , Sunil Pak

{"title":"Manufacturing Assessment of the Simplified Full-Scale Prototype of Diagnostics Shield Module (DSM) for Application of ITER Upper Port 18","authors":"Heejin Shim , Jaemin Kim , MunSeong Cheon , Sunil Pak","doi":"10.1016/j.fusengdes.2025.115141","DOIUrl":"10.1016/j.fusengdes.2025.115141","url":null,"abstract":"<div><div>Upper Port #18 (UP18) is one of the ITER Diagnostic Ports located at the upper position of the Vacuum Vessel (VV). A key aspect of the ITER research program is the diagnosis of the plasma and the first-wall, such as plasma temperature, density and radiative properties. For this purpose, a variety of diagnostic equipment peers into the ITER VV from many different vantage points. The main function of this port integration system is to host and locate tenant diagnostics while provide apertures for diagnostic viewing access to the plasma.</div><div>The upper port plug assembly is composed of three main structure; the Upper Port Plug (UPP) structure, Diagnostic First Wall (DFW) and Diagnostic Shield Module (DSM). The UPP structure is common to all diagnostic upper ports and serves as a base platform for in-vessel integration. The DSM is one of the key parts of the port plug, the DSM of UP18 should be integrated using the generic modular DSM design. This generic modular DSM needs to be customized to integrate each tenant diagnostic system according to their specific requirements. UP18 hosts three tenant diagnostic systems; the Neutron Activation System (NAS), the Vacuum Ultra-violet (VUV) system, and the Upper Vertical Neutron Camera (UVNC). The DSM of UP18 has precise cut-outs to host those tenant systems and provides a Line of Sight (LOS) in the form of a narrow deep opening for measuring plasma behavior under extreme conditions.</div><div>This paper focuses on the manufacturability assessment of the simplified full-scale prototype of the DSM structure and the feasibility of electron beam welding assembly to finalize the upper port assembly design through the entire manufacturing process, including dimensional inspections.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"217 ","pages":"Article 115141"},"PeriodicalIF":1.9,"publicationDate":"2025-05-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143902399","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}

引用次数: 0

Primary and secondary creep of OFHC copper at various temperatures OFHC铜在不同温度下的一次蠕变和二次蠕变

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-05-03 DOI: 10.1016/j.fusengdes.2025.115144

R. Citarella , N. Mantel , F. Penta , M. Perrella , M. Bruno , J.H. You

{"title":"Primary and secondary creep of OFHC copper at various temperatures","authors":"R. Citarella , N. Mantel , F. Penta , M. Perrella , M. Bruno , J.H. You","doi":"10.1016/j.fusengdes.2025.115144","DOIUrl":"10.1016/j.fusengdes.2025.115144","url":null,"abstract":"<div><div>The proper design of reliable high temperature structures for the realization of fusion power plants is a key issue. Therefore, the behaviour of primary and secondary creep of involved materials plays a crucial role. Unfortunately, in the case of the oxygen free high conductivity copper (OFHC Cu), employed for manufacturing some parts of the divertor cooling system, a well consolidated creep constitutive model is still missing. In addition, to the authors’ knowledge, only a limited amount of experimental data on the creep of OFHC Cu, obtained at temperatures quite dissimilar from those expected for in service fusion power plants, are available in the literature. In this work the creep behaviour of OFHC Cu in air atmosphere was analysed under different operating conditions. Creep constant-load tests were carried out at 300°C, 400°C, 450°C and 550°C to measure primary and secondary creep strains. The testing load levels were chosen taking account of the creep design aims of the European Demonstration Power Plant (EU-DEMO) project. Finally, phenomenological laws were proposed to model the creep response of the examined material, and numerical analyses on EU-DEMO monoblock component were performed to assess the effect of primary creep response.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"217 ","pages":"Article 115144"},"PeriodicalIF":1.9,"publicationDate":"2025-05-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143902325","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}

引用次数: 0

Study of vortex structure and turbulent heat transfer mechanism in A-FNS Li target using LES 利用LES研究A-FNS Li靶内的涡结构及湍流换热机理

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-05-03 DOI: 10.1016/j.fusengdes.2025.115136

Daichi Hagari, Takafumi Okita, Eiji Hoashi

{"title":"Study of vortex structure and turbulent heat transfer mechanism in A-FNS Li target using LES","authors":"Daichi Hagari, Takafumi Okita, Eiji Hoashi","doi":"10.1016/j.fusengdes.2025.115136","DOIUrl":"10.1016/j.fusengdes.2025.115136","url":null,"abstract":"<div><div>A liquid lithium (Li) jet is planned to be used as a beam target of the Fusion Neutron Sources (FNSs). FNSs are currently being developed as A-FNS in Japan and IFMIF-DONES in EU, based on the experience gained from IFMIF/EVEDA in both Japan and EU. The flow characteristics and heat transfer mechanisms of the Li jet need to be clarified to ensure the stable and efficient operation of FNSs. Li flow characteristics have been studied using Li Loop of Osaka University (LLOU) and EVEDA Li Test Loop (ELTL). However, it is difficult to experimentally elucidate heat transfer phenomena inside the Li jet during beam-on-target operation. Therefore, it is desirable to evaluate these phenomena using CFD simulation for the safety analysis of such facility. In this study, Large Eddy Simulation (LES) calculations of the Li target with heat transfer due to beam irradiation were first performed as a single-phase flow, incorporating a simplified heat source model. The results showed that a Görtler vortex generated at the nozzle exit developed up to the center of the beam irradiation. Furthermore, we clarified that velocity fluctuations associated with the detachment of the vortex from the back wall occurred twice per second. Heat transfer calculations revealed that such vortices disturbed the temperature field caused by beam energy deposition and lowered the temperature by 40 °C compared to the surrounding temperature near the peak region of the beam energy.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"217 ","pages":"Article 115136"},"PeriodicalIF":1.9,"publicationDate":"2025-05-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143902326","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}

引用次数: 0

Shadow masks predictions in SPARC tokamak plasma-facing components using HEAT code and machine learning methods 使用HEAT代码和机器学习方法对SPARC托卡马克等离子体组件进行阴影掩模预测

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-05-02 DOI: 10.1016/j.fusengdes.2025.115010

D. Corona , M. Scotto d’Abusco , M. Churchill , S. Munaretto , A. Kleiner , A. Wingen , T. Looby

引用次数: 0

A coupled NBI-EC model in investigating the assistant effect on the current ramp-up in EAST 一个耦合的NBI-EC模型用于研究东部电流上升的辅助效应

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-05-01 DOI: 10.1016/j.fusengdes.2025.115134

Hongcan Liu , Qianhong Huang , Ji Wang , Xueyu Gong , Yuanlai Xie , Caichao Jiang , Yijun Zhong , Yuqing Chen , Xingyuan Xu , Wangbin Liu , Junfeng Liu , Ruoxin Bai

{"title":"A coupled NBI-EC model in investigating the assistant effect on the current ramp-up in EAST","authors":"Hongcan Liu , Qianhong Huang , Ji Wang , Xueyu Gong , Yuanlai Xie , Caichao Jiang , Yijun Zhong , Yuqing Chen , Xingyuan Xu , Wangbin Liu , Junfeng Liu , Ruoxin Bai","doi":"10.1016/j.fusengdes.2025.115134","DOIUrl":"10.1016/j.fusengdes.2025.115134","url":null,"abstract":"<div><div>Simulations using TRANSP, ONETWO, and EFIT based on EAST device parameters analyzed the current ramp-up phase under combined neutral beam injection (NBI) and electron cyclotron (EC) injection. The evolution of the plasma current and changes in its profile were analyzed under conditions of 6.0 MW neutral beam injection (NBI) and 2.4 MW electron cyclotron wave (ECW) injection. The study focused on the profile of the current density, particularly the contributions from the Ohmic current, bootstrap current, and non-inductive driven currents. Results showed an approximately 80% reduction in Ohmic current and loop voltage, with volt-second consumption minimized to 0.135 V·s, the lowest compared to NBI or EC alone. This positive effect was attributed to the electron cyclotron wave (ECW) injecting, which elevated the electron temperature, thereby enhancing the efficiency of neutral beam current drive (NBCD). The increased electron temperature facilitated more effective thermalization of fast ions, leading to improved NBCD performance. Consequently, the overall current drive efficiency was significantly boosted, contributing to better plasma stability and confinement. This highlights the efficiency of NBI+EC heating in managing magnetic flux evolution and minimizing resistive losses.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115134"},"PeriodicalIF":1.9,"publicationDate":"2025-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143891052","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}

引用次数: 0

STUMM – monitoring module for DONES neutron source – technical challenges DONES中子源监测模块-技术挑战

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-04-30 DOI: 10.1016/j.fusengdes.2025.115125

U. Wiącek , S. Becerril , J. Castellanos , K. Dojko , W. Janik , R. Kantor , J. Kotuła , A. Kulińska , A. Kurowski , R. Ortwein , M. Turzański

{"title":"STUMM – monitoring module for DONES neutron source – technical challenges","authors":"U. Wiącek , S. Becerril , J. Castellanos , K. Dojko , W. Janik , R. Kantor , J. Kotuła , A. Kulińska , A. Kurowski , R. Ortwein , M. Turzański","doi":"10.1016/j.fusengdes.2025.115125","DOIUrl":"10.1016/j.fusengdes.2025.115125","url":null,"abstract":"<div><div>The Start-Up Monitoring Module (STUMM) will be used to characterize the neutron and gamma radiation fields during the commissioning phase of IFMIF-DONES (International Fusion Materials Irradiation Facility — DEMO<img>Oriented Neutron Source). STUMM will be placed behind the neutron source in the space reserved for the irradiation of material samples. The main mission of the module is to characterize the neutron source and irradiation parameters, qualify the instrumentation, and validate the theoretical calculations. To achieve this mission, it is planned to equip STUMM with about 240 various detectors arranged in rigs. The engineering design of STUMM is a challenging task due to its complexity, very harsh operating conditions, and one-of-a-kind application of the module. This work presents the engineering design of STUMM, including a description of the module's main objective, its requirements, the geometry, and the proposed engineering solutions.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115125"},"PeriodicalIF":1.9,"publicationDate":"2025-04-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143891051","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}

引用次数: 0

Electromagnetic preliminary design of the real-time millimetre-wave radar system for the diagnostic of the IFMIF-DONES lithium target 实时毫米波雷达系统的电磁初步设计，用于诊断IFMIF-DONES锂靶

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-04-30 DOI: 10.1016/j.fusengdes.2025.115076

J. Martínez-Fernández , S. Cabrera , C. de la Morena , D. Jiménez-Rey , D. Regidor , F. Arranz , E.J. Blanco , B. Brañas , M. Chamorro , G. D’Ovidio , J.M. García , R. García , F. Mota , M.I. Ortiz , E. Poveda , R. Román , N. Roy , A. Ros , V. Villamayor

{"title":"Electromagnetic preliminary design of the real-time millimetre-wave radar system for the diagnostic of the IFMIF-DONES lithium target","authors":"J. Martínez-Fernández , S. Cabrera , C. de la Morena , D. Jiménez-Rey , D. Regidor , F. Arranz , E.J. Blanco , B. Brañas , M. Chamorro , G. D’Ovidio , J.M. García , R. García , F. Mota , M.I. Ortiz , E. Poveda , R. Román , N. Roy , A. Ros , V. Villamayor","doi":"10.1016/j.fusengdes.2025.115076","DOIUrl":"10.1016/j.fusengdes.2025.115076","url":null,"abstract":"<div><div>This work describes the electromagnetic preliminary design of a mmWave system that, using radar techniques, can provide the position of the outermost layer of the IFMIF-DONES liquid lithium target, which will lead to the determination of the lithium thickness for safety purposes. Possible perturbations in the liquid lithium curtain with a wavelength in the transversal direction in the tens of mm range could lead to some mm changes in the perturbation amplitude, i.e. the curtain depth, thus leading to the necessity of an incident radar-beam spot illuminating the transversal wavelength in the same tens of mm range. Additionally, no movable parts are advisable in an environment so harsh, which naturally points to a phased array design for the system antenna. A tentative design will be explored using theoretical calculations of a phased array that, given the space constraints, needs to be placed in the near-field region. Thus, both the number of array elements and the working frequency will be determined, leading to a theoretical near-field spot size. In addition, considering the long distances involved between the electronics (located in a separate room with good shielding) and the antenna position (close to the lithium target), propagation loss calculations for different waveguide technologies have been performed in order to make an initial proposal for the signal routing and the proper waveguide technology to guide the mmWave signal.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115076"},"PeriodicalIF":1.9,"publicationDate":"2025-04-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143891067","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}

引用次数: 0

Creep behavior of pebble bed for solid breeder blanket under multiple perturbations 多重扰动下固体增殖层卵石床的蠕变行为

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-04-30 DOI: 10.1016/j.fusengdes.2025.115118

Qigang Wu , Mingzhun Lei , Pinghui Zhao , Zhao Liu , Weibin Xi

{"title":"Creep behavior of pebble bed for solid breeder blanket under multiple perturbations","authors":"Qigang Wu , Mingzhun Lei , Pinghui Zhao , Zhao Liu , Weibin Xi","doi":"10.1016/j.fusengdes.2025.115118","DOIUrl":"10.1016/j.fusengdes.2025.115118","url":null,"abstract":"<div><div>Tritium breeding plays a crucial role in achieving the commercialization of fusion reactors. Solid breeding and multiplication pebble beds are considered promising solutions for tritium breeding. The pebble bed is exposed to a complex service environment, leading to structural instability. This can cause the structure to reorganize, resulting in creep behavior. Such creep may deteriorate heat transfer and reduce the efficiency of tritium extraction. In this study, a beryllium-based pebble bed is adopted, and the Discrete Element Method (DEM) is employed to investigate its structural evolution under multiple perturbations. First, the theoretical framework for structural evolution under external loads is presented. Subsequently, the effects of cycle loading, electromagnetic (EM) load perturbations, and vibration with various frequencies and amplitudes on the pebble bed are examined. The creep behavior of the pebble bed under various disturbances, with varying particle surface friction coefficients, is analyzed. Finally, based on the results, a solution to mitigate significant creep is proposed. The findings reveal that creep behavior is an inherent characteristic of pebble beds. The direction of creep is primarily governed by the dominant external forces. The particle surface friction coefficient exerts a significant influence on creep behavior, suggesting that it can be adjusted to influence the structural stability. This study provides valuable insights for the design of solid breeding blankets and the optimization of pebble bed configurations in fusion reactors.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115118"},"PeriodicalIF":1.9,"publicationDate":"2025-04-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143890900","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}

引用次数: 0