Fusion Engineering and Design最新文献

{"title":"Preparation of Fe-Al coating on 316LSS by low-temperature and high-activation pack aluminizing","authors":"Shijian Lin ,&nbsp;Yongjin Wu ,&nbsp;Changzheng Li ,&nbsp;Zhiyi Cai ,&nbsp;Lihong Nie ,&nbsp;Qisen Ren ,&nbsp;Bin Luo ,&nbsp;Hao Yang ,&nbsp;Hongtao Huang","doi":"10.1016/j.fusengdes.2025.114978","DOIUrl":"10.1016/j.fusengdes.2025.114978","url":null,"abstract":"<div><div>The Fe-Al/Al₂O₃ composite coating is the preferred tritium permeation barrier system in the current research. The Fe-Al transition layer possesses distinct properties, including excellent thermal adaptability and self-healing capabilities. Pack aluminizing is a widely utilized technique for preparing Fe-Al coatings. In this study, the pack aluminizing process was employed on the surface of 316 L stainless steel substrate, and the effects of aluminizing agent ratio, substrate roughness, substrate geometry, aluminizing temperature and aluminizing time on the growth of the aluminized layer were investigated. The experimental results indicated that the aluminized layer comprises Fe₂Al₅ and FeAl₃ phases. Increasing the aluminizing temperature and duration resulted in a thicker Fe-Al coating. However, these factors did not significantly affect the phase composition. The geometry of the substrate does not significantly affect the growth thickness and phase composition of the aluminized layer. Based on these findings, the kinetics of the aluminized layer formation process were analyzed. The relationship between aluminizing temperature and coating thickness followed the Arrhenius equation. The activation energy of pack aluminizing on the surface of 316 L stainless steel was determined to be 68.70 kJ/mol under the aluminizing agent ratio of 40 wt.% aluminum, 56 wt.% alumina and 4 wt.% aluminum chloride. The value was found to be lower than the previously reported activation energies. Furthermore, a thicker coating can be achieved at the same aluminizing temperature and duration by increasing the aluminum source and activator content.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114978"},"PeriodicalIF":1.9,"publicationDate":"2025-03-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685163","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":"Simulation of helicon wave current drive on the Experimental Advanced Superconducting Tokamak under high poloidal beta scenarios","authors":"Daozheng Zi ,&nbsp;Zehou Cheng ,&nbsp;Shuheng Sun ,&nbsp;Miaohui Li ,&nbsp;Xinxia Li","doi":"10.1016/j.fusengdes.2025.114968","DOIUrl":"10.1016/j.fusengdes.2025.114968","url":null,"abstract":"<div><div>The high poloidal beta (<span><math><msub><mrow><mi>β</mi></mrow><mrow><mi>p</mi></mrow></msub></math></span>) scenario serves as a promising operational mode for tokamak fusion reactors. In this paper, the helicon wave current drive under high <span><math><msub><mrow><mi>β</mi></mrow><mrow><mi>p</mi></mrow></msub></math></span> scenarios on the EAST device is studied numerically. Theoretical analysis based on the fast wave dispersion relation indicates that a higher wave frequency enhances wave power absorption in the device. GENRAY/CQL3D simulations indicate that an effective on-axis plasma current drive can generally be achieved. Scans of plasma parameters reveal that lower plasma density and higher plasma temperature contribute to higher current drive efficiency. Moreover, a scheme of combined current drive using lower hybrid waves and helicon waves in the device is analyzed, resulting in significant complementarity in the current drive profile and a positive synergistic effect on the net current drive. This work is expected to provide a new perspective for the next stage of EAST operations.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114968"},"PeriodicalIF":1.9,"publicationDate":"2025-03-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685165","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":"Model experiments to the conductivity of turn insulation of large fusion magnets during unmitigated quench","authors":"Linlin Fang ,&nbsp;Yury Ilin ,&nbsp;Xiongyi Huang ,&nbsp;Qingxiang Ran ,&nbsp;Zhiheng Dai ,&nbsp;Cao Wang ,&nbsp;Guoliang Li ,&nbsp;Jinxing Zheng ,&nbsp;Kun Lu ,&nbsp;Yuntao Song","doi":"10.1016/j.fusengdes.2025.114975","DOIUrl":"10.1016/j.fusengdes.2025.114975","url":null,"abstract":"<div><div>The ITER superconducting magnet system stores a significant amount of energy. During an unmitigated quench, the undissipated energy can cause localized conductors to melt and break, leading to the formation of arcs. These arcs not only directly damage the conductor but may also cause indirect damage to adjacent components, such as the vacuum vessel and cryostat, potentially leading to the release of radioactivity. As the arcs form and develop in the magnet, the turn insulation gradually carbonizes. If the resistivity of the carbonized insulation is sufficiently low, it can affect the current distribution and arc propagation. To understand the conductivity of the turn insulation in a superconducting magnet during an unmitigated quench, this paper references the ITER magnet design and manufactures simplified samples. The experimental setup was established, and the samples were heated under a direct current. The voltage and temperature signals of the samples were analyzed during testing to gain a preliminary understanding of the turn insulation's conductivity from room temperature to 1000 °C over a heating period of several hundred seconds.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114975"},"PeriodicalIF":1.9,"publicationDate":"2025-03-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685918","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":"Enabling model-based scenario control in EAST by fast surrogate modeling within COTSIM","authors":"Z. Wang ,&nbsp;E. Schuster ,&nbsp;T. Rafiq ,&nbsp;Y. Huang ,&nbsp;Z. Luo ,&nbsp;Q. Yuan ,&nbsp;J. Barr","doi":"10.1016/j.fusengdes.2025.114969","DOIUrl":"10.1016/j.fusengdes.2025.114969","url":null,"abstract":"<div><div>The Control-Oriented Transport Simulator (COTSIM) is a fast, modular code designed to predict the evolution of both equilibrium and internal profiles in the EAST tokamak. Built on MATLAB/Simulink®, COTSIM is tailored for iterative control design, making it suitable for applications such as pulse design, feedforward scenario optimization, feedback-control testing prior to implementation, and real-time estimation and optimization. Recent advancements have enhanced its prediction accuracy for EAST while maintaining computational efficiency through the integration of neural-network-based surrogate models for the Multi-Mode Anomalous Transport Module (MMM), GENRAY/CQL3D (Lower Hybrid Wave [LHW]), and NUBEAM (Neutral Beam Injection [NBI]). Additionally, the transport solver has been coupled with both fixed-boundary and free-boundary equilibrium solvers. This study demonstrates the development and testing of model-based optimal feedback controllers in COTSIM simulations. These controllers regulate key plasma properties crucial for advanced tokamak scenarios, including the safety factor (<span><math><mi>q</mi></math></span>) at various spatial locations, plasma internal energy (<span><math><mi>W</mi></math></span>), normalized beta (<span><math><msub><mrow><mi>β</mi></mrow><mrow><mi>N</mi></mrow></msub></math></span>), and internal inductance (<span><math><msub><mrow><mi>l</mi></mrow><mrow><mi>i</mi></mrow></msub></math></span>). Control actuators include plasma current, plasma density, low-frequency (2.45 GHz) and high-frequency (4.60 GHz) LHW powers, and individual NBI powers. To validate these control algorithms, experimental testing has been conducted on EAST. Results from simulations and experiments demonstrate the ability to regulate scenario-defining plasma properties, suggesting COTSIM’s utility as a tool for advanced tokamak control development.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114969"},"PeriodicalIF":1.9,"publicationDate":"2025-03-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685164","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Real-time monitoring system for detection and characterization of thermal events on WEST Tokamak: Implementation and first results","authors":"Valentin Gorse,&nbsp;Erwan Grelier,&nbsp;Victor Moncada,&nbsp;Raphael Mitteau,&nbsp;WEST Team","doi":"10.1016/j.fusengdes.2025.114960","DOIUrl":"10.1016/j.fusengdes.2025.114960","url":null,"abstract":"<div><div>Analyzing thermal events in fusion devices is essential for both scientific understanding and machine protection. The infrared diagnostics of long-pulse machines, such as W Environment Steady-state Tokamak (WEST), generate a large amount of video data, presenting a challenge for human operators to conduct real-time thermal event analysis. Therefore, there is a need for a process able to detect and analyze thermal events automatically and in real-time, for feedback control and investment protection. Up to now, multiple types of intelligent methods have been applied between experiments during previous WEST campaigns (detection of thermal events, characterization of strike lines on the tungsten divertor, and detection of electric arcs). This paper introduces a modular framework enabling their use on infrared data in real-time. With a NVIDIA A40 Graphical Processing Unit (GPU) added to the Wall Monitoring System (WMS) of WEST, the detection of thermal events and characterization of strike lines, which rely on Artificial Intelligence (AI) approaches, run at 30 fps. The electric arc detection system, based on a compact Convolutional Neural Network (CNN), operates at over 100 frames per second. For the first time in the fusion domain, an AI-based image analysis method is being utilized to send instructions to the heating antennae through integration with the Plasma Control System (PCS). Therefore, this framework unlocks the possibility of using the produced results for real-time heating feedback control. Furthermore, these results are stored in a dedicated local database for later studies. It was first tested during the C9 campaign of WEST and performed well on the large quantity of infrared videos captured, paving the way toward intelligent real-time control of large fusion machines such as ITER.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114960"},"PeriodicalIF":1.9,"publicationDate":"2025-03-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685915","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 tungsten fiber-reinforced copper composite pipes for EU-DEMO Divertor target","authors":"P. Lorusso ,&nbsp;S. Roccella ,&nbsp;E. Cacciotti ,&nbsp;M. Cerocchi ,&nbsp;F. Crea ,&nbsp;R. De Luca ,&nbsp;L. Verdini ,&nbsp;P. Junghanns ,&nbsp;K. Hunger ,&nbsp;A. von Müller ,&nbsp;J.H. You","doi":"10.1016/j.fusengdes.2025.114973","DOIUrl":"10.1016/j.fusengdes.2025.114973","url":null,"abstract":"<div><div>Within the roadmap of the EU-DEMO reactor design pursued by the EUROfusion Programme, R&amp;D activities are promoted for the technological development of Plasma Facing Components. A dedicated task aims at consolidating and verifying the current target concepts envisioned for DEMO Divertor, derived from the reference ITER-like W-monoblock concept and the back-up solution with tungsten fiber-reinforced copper (W_f-Cu) composite pipes. ENEA has undertaken a research activity to support the back-up concept, finding alternative technological solutions for monoblock-pipe joining to reduce the use of materials having high activation and/or degradation under neutron irradiation. In particular, the possibility of joining the blocks to the pipe without brazing alloy has been investigated. An impregnation procedure consisting of copper casting with the simultaneous impregnation of pre-wrapped W fibers and the junction of the W monoblocks in a single process has been developed. A crucial point is the realization of high-quality composite tubes, having dimensions as close as possible to the ones of the standard CuCrZr tubes currently envisaged for DEMO Divertor, as well as a Cu matrix in which the content of defects and imperfections is reduced as much as possible. For this purpose, a set of samples having a DEMO Divertor target cooling tube shape are fabricated, and their quality is assessed through non-destructive (ultrasonic testing) and destructive (i.e., metallography) examination techniques.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114973"},"PeriodicalIF":1.9,"publicationDate":"2025-03-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685913","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Validation of vacuum vessel thermal shield deformation via finite elements and morphing techniques based analysis","authors":"Edoardo Pompa ,&nbsp;Pierric Leonard ,&nbsp;Tudorel Popa ,&nbsp;Luigi Reccia ,&nbsp;Marco E. Biancolini ,&nbsp;Gabriele D'Amico ,&nbsp;Francisco J. Fuentes","doi":"10.1016/j.fusengdes.2025.114937","DOIUrl":"10.1016/j.fusengdes.2025.114937","url":null,"abstract":"<div><div>The Vacuum Vessel Thermal Shield (VVTS) is the barrier that reduces by two orders of magnitude heat loads transferred by thermal radiation and conduction from hot components to magnets and other systems inside the cryostat that operate at 4 .5K. In order to maintain its function during operation, the clearance between VVTS, Toroidal Field Coils (TFC) and Vacuum Vessel (VV), shall be guaranteed. Hence, it is of paramount importance to monitor the gap during the machine assembly phase, when changes in the constraints of the flexible structure may affect the as-built geometries. In particular, after the assembly of the TF coils on the sector module in the Sectors Sub-Assembly Tools (SSAT), accessibility to the VVTS becomes limited to the area of the sector edge. From this stage on, as-built data of the accessible surfaces may not be representative of the full deformed shape. In order to validate the actual measurement strategy, an analysis based on Finite Elements and Morphing Techniques has been carried out.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114937"},"PeriodicalIF":1.9,"publicationDate":"2025-03-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685914","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":"Superconducting magnet operation in JT-60SA integrated commissioning test","authors":"Kazuya Hamada ,&nbsp;Haruyuki Murakami ,&nbsp;Kazuma Fukui ,&nbsp;Katsumi Kawano ,&nbsp;Yoshihiro Onishi ,&nbsp;Katsutomi Usui ,&nbsp;Yoshitoshi Kashiwa ,&nbsp;Atsushi Honda ,&nbsp;Hisashi Ichige ,&nbsp;Minoru Sato ,&nbsp;Taichi Abe ,&nbsp;Ryota Sakurai ,&nbsp;Masahide Iguchi ,&nbsp;Katsuhiko Tsuchiya ,&nbsp;Kiichi Ohtsu ,&nbsp;Katsuhiro Shimada ,&nbsp;Shoichi Hatakeyama ,&nbsp;Kunihito Yamauchi ,&nbsp;Akihiko Isayama ,&nbsp;Koji Takahashi ,&nbsp;Christine Hoa","doi":"10.1016/j.fusengdes.2025.114946","DOIUrl":"10.1016/j.fusengdes.2025.114946","url":null,"abstract":"<div><div>JT-60SA is a superconducting tokamak experiment device constructed in 2021. The first integrated commissioning (IC) tests in 2021 were interrupted due to an electrical short at the EF1 terminals caused by local weak electrical insulation. Terminal joint repairs, insulation reinforcements, and high-voltage tests took two years. In 2023, the IC test was resumed. The TF coils reached their nominal current of 25.7 kA with a stored energy of about 1 GJ. The 18 TF coils, central solenoid (CS), and six equilibrium field (EF) coils safely passed a fast discharge test to qualify the magnet protection system and the cryogenic system's recovery procedure. The plasma experiments began after individual and combination coil tests. In the plasma experiment, CS and EF coils operated only up to ±5 kA, much lower than their nominal current to stay within the limits of present withstand voltage performance. However,JT-60SA achieved the first plasma and a maximum plasma current of 1.2 MA. It was confirmed that the magnet's mechanical behavior was as expected. The cryogenic system operated stably. This paper describes the results of the magnet system operation and its impact on the cryogenic system.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114946"},"PeriodicalIF":1.9,"publicationDate":"2025-03-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685917","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Design and heat transfer analysis of new single-screw pellet injector for EAST tokamak","authors":"H.T. Qiu ,&nbsp;J.L. Hou ,&nbsp;G.Z. Zuo ,&nbsp;Y. Chen ,&nbsp;Y.W. Yu ,&nbsp;Q.C. Ren ,&nbsp;J. Fu ,&nbsp;J.S. Hu","doi":"10.1016/j.fusengdes.2025.114962","DOIUrl":"10.1016/j.fusengdes.2025.114962","url":null,"abstract":"<div><div>A new single-screw pellet injector based on Gifford-McMahon cryocoolers is under development to address the challenges of stable fuel supply and enhanced core plasma density for the EAST tokamak. This injector features a single-screw extruder, a pellet cutter with a launch mechanism, and a cryogenic system driven by three Gifford-McMahon cryocoolers. It is capable of producing hydrogen isotope pellets with a diameter and length of 2.5 mm at frequencies of up to 10 Hz. Meanwhile, comprehensive heat transfer analyses are conducted, covering fuel cooling, viscous dissipation during extrusion, and environmental heat exchange through conduction and radiation. Numerical simulations using ANSYS Polyflow provide additional analyses of viscous heating effects, further validating the system's performance. The system will provide valuable engineering experience for future fusion facilities like CFETR. Bench tests and performance comparisons with theoretical models are ongoing to ensure and enhance system reliability and performance.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114962"},"PeriodicalIF":1.9,"publicationDate":"2025-03-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685916","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":"Measuring the beamlet divergence in NBI systems for fusion: A diagnostic comparison","authors":"Niek den Harder ,&nbsp;Michael Barnes ,&nbsp;Andreas Döring ,&nbsp;Bernd Heinemann ,&nbsp;Bruno Laterza ,&nbsp;Isabella Mario ,&nbsp;Antonio Pimazzoni ,&nbsp;Carlo Poggi ,&nbsp;Alessandro La Rosa ,&nbsp;Emanuele Sartori ,&nbsp;Beatrice Segalini ,&nbsp;Gianluigi Serianni ,&nbsp;Alastair Shepherd ,&nbsp;Christian Wimmer ,&nbsp;Dirk Wünderlich ,&nbsp;Ursel Fantz","doi":"10.1016/j.fusengdes.2025.114951","DOIUrl":"10.1016/j.fusengdes.2025.114951","url":null,"abstract":"<div><div>The ITER Neutral Beam Injection (NBI) system is based on negative hydrogen ions, which are extracted and subsequently accelerated in 5 steps to the full beam energy of 1 MeV by a 7 grid system. A low beamlet divergence is crucial for the efficiency of the ITER-NBI systems, since it affects the transmission of the beam through the duct. The divergence describes the width of the angular distribution, but in practice is often diagnosed from the spatial profile, which requires assumptions on the propagation behaviour of the beam. The RF-driven BATMAN Upgrade testbed, hosted at the Max Planck Institute for Plasma Physics in Garching Germany (IPP), is 1/8 of the ITER source size, and has a 3 grid system that extracts and accelerates the beamlet particles up to 45 keV. In a joint campaign between IPP and Consorzio RFX, an Allison type emittance scanner was operated at BATMAN Upgrade. The emittance scanner, which was constructed and operated by Consorzio RFX, measures the spatial and angular distribution in one direction as well as correlations between them. The direct measurements of the divergence from the emittance scanner are compared to spatially resolved thermographic measurements of the beam footprint on a carbon fibre composite tile. Comparison between the two methods shows the error margin in the conversion from the spatial profile to a divergence. The combined spatial and angular distribution measured by the emittance scanner yields the Twiss parameters, which not only describe the spatial size and divergence, but also the beamlet propagation behaviour. The propagation behaviour provides insight into the limitations of a divergence estimation from a single spatial measurements close to the grid system, and provides input for the design of future diagnostics.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114951"},"PeriodicalIF":1.9,"publicationDate":"2025-03-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143644175","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}