Fusion Engineering and Design最新文献

{"title":"Feasibility study of gamma-ray spectroscopy for the determination of the fusion power at the SPARC tokamak","authors":"Simone Lorenzo Fugazza ,&nbsp;Giulia Marcer ,&nbsp;Massimo Nocente ,&nbsp;Alessandro Ciurlino ,&nbsp;Gabriele Croci ,&nbsp;Marco Dalla Rosa ,&nbsp;Andrea Dal Molin ,&nbsp;Erik Gallo ,&nbsp;Giuseppe Gorini ,&nbsp;Miriam Parisi ,&nbsp;Prasoon Raj ,&nbsp;Marica Rebai ,&nbsp;Matthew Reinke ,&nbsp;Davide Rigamonti ,&nbsp;Federico Scioscioli ,&nbsp;Marco Tardocchi ,&nbsp;JET Contributors","doi":"10.1016/j.fusengdes.2025.115403","DOIUrl":"10.1016/j.fusengdes.2025.115403","url":null,"abstract":"<div><div>SPARC is a high-field, compact tokamak aiming to obtain a fusion gain Q<span><math><mo>&gt;</mo></math></span>1 in Deuterium-Tritium (DT) plasmas for the first time in a magnetic confinement fusion reactor. Fusion power measurement is a key diagnostic requirement. In this work we present a scoping study of a gamma-ray spectrometer for the determination of the fusion power at SPARC. Measurements are based on the detection of the 16.7 MeV and <span><math><mo>∼</mo></math></span> 14 MeV gamma-rays produced by the weak secondary channel <span><math><mrow><mi>T</mi><msup><mrow><mrow><mo>(</mo><mi>D</mi><mo>,</mo><mi>γ</mi><mo>)</mo></mrow></mrow><mrow><mn>5</mn></mrow></msup><mi>He</mi></mrow></math></span> of the DT fusion reaction, whose branching ratio has been recently measured at the JET tokamak. Starting from the numerical calculation of the DT gamma source and a first evaluation of the sources of background radiation, we determine the fusion power range where measurements are possible at SPARC. We find that the fusion power can be determined in the broad range of 0.2 MW to 140 MW, when different neutron and gamma-ray attenuators are employed depending on the operational conditions. Potential additional applications of the gamma-ray detector scoped in this work are also briefly discussed.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115403"},"PeriodicalIF":2.0,"publicationDate":"2025-09-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145050172","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-hydraulic analysis for CN HCCB TBM regarding ITER new baseline scenario","authors":"Xinghua Wu,&nbsp;Qixiang Cao,&nbsp;Fengchao Zhao,&nbsp;Long Zhang,&nbsp;Xiaoyu Wang","doi":"10.1016/j.fusengdes.2025.115427","DOIUrl":"10.1016/j.fusengdes.2025.115427","url":null,"abstract":"<div><div>Demonstration of tritium breeding blanket technique is one of the engineering goal of International Thermonuclear Experimental Reactor (ITER). Among the different blanket concepts, China decided to develop Helium-cooled Ceramic-Breeder Test Blanket Module (HCCB TBM) and tested in ITER specific TBM port. Currently CN HCCB TBM design is under preliminary design (PD) phase. In 2023, regarding some engineering and technical issues, ITER proposed to modify previous baseline scenario, with less than 1% of total neutron fluence in DT-1 phase, and reduced plasma pulse parameters. Regarding the testing goals of TBM programme, additional electrical heater was proposed to put inside TBM module, so as to achieve relatively high temperature for tritium release. In this paper, steady-state and transient thermo-hydraulic analysis was performed for HCCB TBM typical component, and the overall temperature distribution was achieved, which will be input for structural analysis and dynamic tritium transport analysis in the next step.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115427"},"PeriodicalIF":2.0,"publicationDate":"2025-09-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145050171","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 impact of argon addition on hydrogen superpermeation through palladium alloy metal foil pumps during direct internal recycling","authors":"Caroline L. Hufnagel ,&nbsp;Vitor Camacho ,&nbsp;Thomas F. Fuerst ,&nbsp;Adam Rutkowski ,&nbsp;J․Douglas Way ,&nbsp;Colin A. Wolden","doi":"10.1016/j.fusengdes.2025.115428","DOIUrl":"10.1016/j.fusengdes.2025.115428","url":null,"abstract":"<div><div>Metal foil pumps (MFPs) are a leading technology for the direct internal recycling (DIR) of hydrogen isotopes from the plasma exhaust of fusion devices. MFPs rely on the concept of superpermeation, where plasma-generated atomic hydrogen absorbs into the metal foil, rapidly diffuses, and desorbs downstream. To date, studies of superpermeation have predominantly employed pure hydrogen or in some cases trace levels of impurities. In practice the plasma exhaust may contain significant levels of plasma enhancement gases such as argon, an inert gas with metastable states that can enhance the plasma. In this work, we systematically study the impact of Ar addition on the performance of PdCu and PdAg MFPs at low temperature. Performance was strongly dependent on the DIR fraction. At negligible DIR levels Ar addition did not significantly improve the flux over dilution effects. However, under appreciable DIR operation the flux was enhanced up to 90 % relative to pure H₂, with the optimal concentration range being 5–10 % Ar exiting the system. Beyond 15 % addition plasma enhancement benefits were offset by dilution. Performance correlated with the atomic H emission, and benefits were more pronounced for PdAg than PdCu. Operation at significant DIR levels dramatically alters the flow dynamics resulting in concentration gradients near the MFP, creating plasma conditions that promote H₂ dissociation.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115428"},"PeriodicalIF":2.0,"publicationDate":"2025-09-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145050170","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":"Assessing the impact of pre-ionization technique on the homogeneity and stability of the current sheath layer in dense plasma focus device","authors":"A. Hosseinzadeh ,&nbsp;N. Vosoughi ,&nbsp;T.D. Mahabadi ,&nbsp;D. Piriaei","doi":"10.1016/j.fusengdes.2025.115429","DOIUrl":"10.1016/j.fusengdes.2025.115429","url":null,"abstract":"<div><div>In this research, the pre-ionization technique was applied using an optimal shunt resistor on a Dense Plasma Focus (DPF) device filled with deuterium as the working gas. The effects of this technique on the properties of the current sheath layer, particularly its homogeneity and stability, which are crucial factors in the quality of nuclear fusion, have been investigated. Time-frequency wavelet analysis of pulses obtained from Mirnov coils in two different configurations (toroidal and poloidal arrangements) indicated the effect of this technique on improving the homogeneity of the magnetic field intensity produced by the current sheath layer. Time-Integrated Analysis (TIA) and Frequency-Integrated Analysis (FIA) of the Mirnov circuit pulses, along with the evaluation of the magnetic field intensity ratios of these coils placed at specific azimuthal angles (particularly 0 and 180 degrees) and different orientations (particularly radial and axial), demonstrated the positive effect of the current sheath's homogeneity on the quantitative convergence of these ratios. This convergence indicates the beneficial effect of the pre-ionization technique in reducing the stresses, asymmetries, and instabilities of the current sheath layer, which subsequently leads to an improvement in the efficiency of the nuclear fusion reaction in the DPF system.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115429"},"PeriodicalIF":2.0,"publicationDate":"2025-09-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145027148","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":"Link deformation prediction and compensation of heavy-duty manipulator for fusion reactor","authors":"Yang Cheng ,&nbsp;Kun Lu ,&nbsp;Hongtao Pan ,&nbsp;Yong Cheng ,&nbsp;Hao Han","doi":"10.1016/j.fusengdes.2025.115420","DOIUrl":"10.1016/j.fusengdes.2025.115420","url":null,"abstract":"<div><div>The extreme operating environment of the fusion reactor (such as radiation, and magnetic fields) makes manual direct maintenance unfeasible. Remote handling has become the core means of in-vessel components maintenance. For the in-vessel components with heavy payload, the heavy-duty manipulator is a key maintenance equipment. When carrying heavy load in-vessel components, the links of the long cantilever manipulator will suffer deformation problem and therefore, makes the end position and posture accuracy low. To improve the end position and posture accuracy, a new method combines the Newton-Euler method and the neural network method was proposed. The Newton-Euler method is used for link force calculation and the neural network is adopted to learning the link deformation. The deformation model of the heavy-duty manipulator is established and the end error is compensated by the pseudo-inverse Jacobian method. The proposed methods are applied on the heavy-duty manipulator, and the link deformation prediction and compensation model are verified. The results show that the link deformation under different payloads can be predicted and compensated. After compensation, the maximum position and posture error can be reduced to 3.18 mm and 1.67 <span><math><mrow><mo>×</mo><msup><mrow><mn>10</mn></mrow><mrow><mo>−</mo><mn>3</mn></mrow></msup></mrow></math></span>rad, respectively. The end position and posture errors can be reduced by 63.4 % and 78.1 %, respectively. The proposed model can be used for the link deformation prediction and compensation of the real heavy-duty manipulator assembly in the future to further validate the accuracy improvement.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115420"},"PeriodicalIF":2.0,"publicationDate":"2025-09-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145027147","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":"Neutral beam attenuation in the HL-3 Tokamak: simulation and experimental analysis of BES diagnostic performance","authors":"X.Q. Yang ,&nbsp;Y. Yu ,&nbsp;C.Y. Xiao ,&nbsp;R. Ke ,&nbsp;S.B. Gong ,&nbsp;R. Jin ,&nbsp;W.W. Cheng ,&nbsp;S.J. Zhu ,&nbsp;Z.B. Wang ,&nbsp;J. Chen ,&nbsp;M. Xu","doi":"10.1016/j.fusengdes.2025.115419","DOIUrl":"10.1016/j.fusengdes.2025.115419","url":null,"abstract":"<div><div>Neutral beam (NB) attenuation represents a critical factor for evaluating energy deposition in tokamaks, offering essential references both for plasma discharge operations and for plasma density diagnostics. This study theoretically calculates NB attenuation coefficients and Doppler shifted Balmer Dα photon flux levels for the newly installed 32-channel Beam Emission Spectroscopy (BES) system on the HL-3 tokamak, utilizing the ADAS (Atomic Data and Analysis Structure) database with actual NB injection parameters and plasma profile data. The calculation methodology is validated through experimental comparisons with BES-measured photon flux profiles. Simulation results demonstrate adequate line intensity for proposed 128-channel BES implementation under typical HL-3 operating conditions characterized by elevated plasma densities and electron temperatures. This analytical approach enables direct evaluation of NB energy deposition via attenuation coefficients or photon flux peak analysis, providing rapid assessment of NBI heating efficiency during shot-to-shot intervals. Furthermore, this work highlights BES diagnostics' significant potential for optimizing heating efficiency and plasma current drive performance.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115419"},"PeriodicalIF":2.0,"publicationDate":"2025-09-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145026334","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":"Operational planning of magnetic confinement fusion power plants using a MIP unit-commitment model","authors":"Larissa Breuning ,&nbsp;Anđelka Kerekeš ,&nbsp;Alexander von Müller ,&nbsp;Julia Gawlick ,&nbsp;Soner Candas ,&nbsp;Hartmut Zohm ,&nbsp;Thomas Hamacher","doi":"10.1016/j.fusengdes.2025.115316","DOIUrl":"10.1016/j.fusengdes.2025.115316","url":null,"abstract":"<div><div>Once magnetic confinement fusion power plants are commercialized, they have to compete with other energy supply technologies. Energy system planning models can give insights into the operation and interaction of such supply technologies. Due to their specific operational behavior and power requirements, fusion power plants need dedicated consideration in energy system modeling. In this work, we present an approach for multi-state techno-economic modeling of fusion power plants to enable the estimation of their optimal dispatch. Models of tokamak and stellarator type plants have been developed in a mixed-integer programming framework for unit commitment, which optimizes the operation of a complex of power plants by minimizing their variable costs. Multiple reactor states - hot, dwell, production-start and production - and their corresponding losses are defined. The operation is first validated in a simplified single-node model. Next, the conclusions are transferred to a European power system model for the year 2050 of much higher spatial and structural complexity. The impact of various design pathways on operational strategy is examined. The results show that both reactor types would operate in a load-following mode. By using assumed 20 GW_el of installed fusion power, 20 % of CO₂ emissions can be saved in the European electricity market compared to a scenario without fusion. Significant seasonal differences in the fusion power plant operation are observed. The tokamak reactor operates on average 4,043 cycles per year (2 h pulse length), while the stellarator reactor operates on average 474 cycles per year.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115316"},"PeriodicalIF":2.0,"publicationDate":"2025-09-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145026333","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":"Overview of university-class Tokamak TRUST: Preliminary characterization of plasma scenario and disruption studies","authors":"S. Carusotti,&nbsp;M. Scarpari,&nbsp;R. Lombroni,&nbsp;M. Notazio,&nbsp;L. Balbinot,&nbsp;F. Crisanti,&nbsp;P. Fanelli,&nbsp;G. Calabrò","doi":"10.1016/j.fusengdes.2025.115416","DOIUrl":"10.1016/j.fusengdes.2025.115416","url":null,"abstract":"<div><div>TRUST (Tuscia Research University Small Tokamak) is a new University-scale tokamak currently under design at the University of Tuscia (UNITUS). This paper gives an overview of the TRUST conceptual design, for a first stage of operation to achieve the target single null plasma configuration with the following main parameters: R₀ = 0.3 m, <em>A</em> = 2.5, I_pla = 0.110 MA, B_t = 0.8 T, q₉₅ = 3.2. One of the main aims of this experiment is to realise a flexible and low-cost university-class experiment, to train the next generation of fusion engineers and physicists ready to study the power exhaust issues on a long-time scale, according to the scientific program of EU-DEMO and DTT proposals. The system is designed to allow easy replacement of the plasma facing components and testing innovative technologies (i.e., meta-materials) including a feasible upgrade of the poloidal field coils with high temperature superconductors (HTS) working at 77 K. Moreover, TRUST Alternative Magnetic Layout (AML) conceptual design will be explained including the proposed solution for the assembly/disassembly phases. Three distinct plasma configurations for future TRUST operations are foreseen: Single Null (SN), Double Null (DN), and Upper Single Null (USN). Detailed analyses are presented for each plasma scenario, with a particular focus on optimizing active coil currents during characteristic pulse phases to achieve the desired magnetic field configuration with suitable plasma parameters. A preliminary estimation of the thermal loads and plasma temperatures at the first wall and divertor has been made from EM scenario analysis, together with a first analysis on TRUST vertical stability. Additionally, a preliminary plasma disruption database is presented, comprising a collection of EM numerical simulations covering various plasma dynamic conditions within the operational space.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115416"},"PeriodicalIF":2.0,"publicationDate":"2025-09-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145020846","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":"Predictive control of NPC three-level inverter model based on current increment","authors":"Chenlei Xie ,&nbsp;Yan Shen ,&nbsp;Liansheng Huang ,&nbsp;Xiaojiao Chen ,&nbsp;Tao Chen ,&nbsp;Sheng Dou","doi":"10.1016/j.fusengdes.2025.115418","DOIUrl":"10.1016/j.fusengdes.2025.115418","url":null,"abstract":"<div><div>This paper proposes a Current Increment Model Predictive Control (CI-MPC) strategy for three-level inverters to address limitations in current tracking performance and computational burden associated with conventional methods. Unlike traditional Finite-Control-Set MPC (FCS-MPC) and Optimal Switch Sequence MPC (OSS-MPC), CI-MPC reformulates the control objective using current increments, significantly improving dynamic current tracking accuracy. The strategy incorporates a large-sector state transition matrix and upward vector rounding, reducing the number of required vector evaluations per control cycle to fewer than 2. This contrasts with 27 evaluations for FCS-MPC and 10 for OSS-MPC, substantially decreasing computational load. Simulation and experimental results demonstrate that CI-MPC outperforms FCS-MPC and OSS-MPC. Specifically, its dynamic current response speed is approximately 50 % faster than FCS-MPC and 80 % faster than OSS-MPC. The current total harmonic distortion (THD) under CI-MPC is reduced to 1.92 %, compared to 4.52 % for FCS-MPC and 3.01 % for OSS-MPC. Additionally, controller optimization time is reduced from 2.4µs (OSS-MPC) to 1.2µs, improving algorithm efficiency by approximately 50 %.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115418"},"PeriodicalIF":2.0,"publicationDate":"2025-09-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145020845","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 systematic and general nonlinear optimization strategy for integrated structural-sealing design of large and complex vacuum components in fusion reactors","authors":"Qingzhou Yu ,&nbsp;Genmu Shi ,&nbsp;Qingxi Yang ,&nbsp;Hao Xu ,&nbsp;Xinyuan Qian ,&nbsp;Jose Lorenzo ,&nbsp;Shilin Chen ,&nbsp;Zhaoxi Chen ,&nbsp;Guillaume Vitupier ,&nbsp;Thierry Schild ,&nbsp;Mohit Jadon","doi":"10.1016/j.fusengdes.2025.115402","DOIUrl":"10.1016/j.fusengdes.2025.115402","url":null,"abstract":"<div><div>The standardization of fusion engineering technologies is a major trend in the development of the fusion field. One of the key technologies is the reliable design of large and complex vacuum components (LCVCs) under intricate loads, which determines the safe and stable operation of fusion devices. To meet the requirements for accurate, efficient, and systematic design of LCVCs in future fusion reactors, this paper proposes a systematic optimization method called the NOVACS strategy. It establishes a general phased nonlinear multi-objective optimization approach for both the LCVC body and its seals, collaboratively planning the optimization process by leveraging a parameter input set to drive structural updates, thereby improving design accuracy, efficiency, and integrity. To demonstrate the advantages of the strategy, the cryostat of the ITER Magnet Cold Test Bench (MCTB) is chosen for systematic optimization. Compared to the trial-and-error method, it can enhance optimization efficiency by approximately 33% through an established multi-computer linkage mode for multi-objective experimental design and analysis, even when the optimization process is nonlinear. Additionally, the optimization results concerning mass and deformation objectives are improved, yielding an economical design while ensuring structural reliability. Further design is conducted on the seal at the largest interface of the cryostat using this strategy, resulting in an O-ring with a profile diameter of Φ45 mm and approximately 55.8 m in circumference, optimized according to the leakage rate function. It exhibits good contact characteristics, effectively sealing large flanges with a maximum flatness tolerance of up to 4 mm. Moreover, even in the worst-case sealing scenario, the O-ring will not fail, with a maximum leakage rate of 6.26 × 10⁻⁷ Pa·m³/s. The proposed NOVACS strategy provides feasible technical guidance for the full-process optimization design of LCVCs in fusion devices, facilitating the establishment of its standardized design.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115402"},"PeriodicalIF":2.0,"publicationDate":"2025-09-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145005189","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}