Fusion Engineering and Design最新文献

{"title":"Neutronics analyses for EU-DEMO 2023 electron cyclotron port","authors":"Aljaž Čufar ,&nbsp;Bor Kos ,&nbsp;Dieter Leichtle ,&nbsp;Peter Spaeh","doi":"10.1016/j.fusengdes.2025.115240","DOIUrl":"10.1016/j.fusengdes.2025.115240","url":null,"abstract":"<div><div>One of the fundamental challenges in the development of a fusion power plant is to integrate all the systems required for the operation of the power plant into a machine that fulfills all the design requirements. This includes designing sufficient shielding against neutrons and gamma rays to ensure that the machine can operate reliably throughout its planned lifetime.</div><div>The electron cyclotron (EC) heating is one of the systems critical to heating and controlling the fusion plasma. In the EU-DEMO reactor, the EC system is integrated into an equatorial port. However, the challenge with this system is that the waveguides required for it to function act as neutron and gamma ray streaming paths, which makes controlling the nuclear loads inside and behind the EC port a challenge. This concerns both the components of the EC system itself and components and systems outside the equatorial port where the EC system is located, e.g. the superconducting toroidal field coils.</div><div>The latest iteration of the EU-DEMO EC heating system from 2023 was analyzed. The main nuclear loads have been calculated and the shielding performance optimized to ensure that the design limits are met. These analyses include calculations of nuclear heating in EC port, determination of peak nuclear heating in the toroidal field coils and peak neutron-induced damage (DPA) in the components exposed to the plasma neutrons.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115240"},"PeriodicalIF":1.9,"publicationDate":"2025-06-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144307187","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 of 1D carbon fiber composite tiles infrared diagnostic calorimeter for the CRAFT NNBI test platform","authors":"Yue Hu ,&nbsp;Yongjian Xu ,&nbsp;Tao Yang ,&nbsp;Yahong Xie ,&nbsp;Chundong Hu ,&nbsp;Lizhen Liang","doi":"10.1016/j.fusengdes.2025.115279","DOIUrl":"10.1016/j.fusengdes.2025.115279","url":null,"abstract":"<div><div>A novel bidirectional, remotely operable diagnostic calorimeter has been developed for the Comprehensive Research Facility for Fusion Technology (CRAFT) Negative Neutral Beam Injection (NNBI) test platform to evaluate beam uniformity and divergence. The system employs 1D-carbon fiber composite (CFC) tiles, selected for their exceptional thermal conductivity and high-temperature resistance, ensuring accurate diagnostics under extreme operating conditions. The calorimeter comprises a 4 × 4 array of CFC tiles, a robust support structure, and a precise linear motion system, enabling accurate positioning within the vacuum chamber. Integrated infrared (IR) cameras provide thermal imaging capabilities, while finite element analysis (FEA) confirms the thermodynamic performance of the CFC tile and the mechanical reliability of the design. Following successful fabrication and installation, the system was fully integrated into the NNBI test platform in early 2024. This diagnostic calorimeter offers a reliable solution for evaluating the characteristics of negative neutral beams and establishes a solid foundation for future experimental research in fusion technology.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115279"},"PeriodicalIF":1.9,"publicationDate":"2025-06-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144307188","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":"Real-time density profile simulations on ASDEX Upgrade and the impact of the edge boundary condition","authors":"D. Kropackova ,&nbsp;F. Pastore ,&nbsp;O. Kudlacek ,&nbsp;O. Sauter ,&nbsp;E. Fable ,&nbsp;P. David ,&nbsp;EUROfusion Tokamak Exploitation Team ,&nbsp;ASDEX Upgrade Team","doi":"10.1016/j.fusengdes.2025.115196","DOIUrl":"10.1016/j.fusengdes.2025.115196","url":null,"abstract":"<div><div>The plasma density is a crucial parameter of tokamak discharge as it impacts the fusion power, stability limits, influences detachment onset and impurities transport. The electron density profile shaping affects the deposition location of the external heating power, thereby playing a role, for instance, in NTM control. Therefore, the real-time estimation of the density profile is essential for high performance tokamak operation.</div><div>The real-time density profile reconstruction can be provided by the RAPDENS code (Blanken et al. 2018), which collects density measurements, like interferometers and Thomson scattering (Pastore et al. 2023) and combines them with the solution obtained by its 1.5D particle transport model using the Extended Kalman Filter technique. RAPDENS can be employed in various applications including real-time dynamic state observation, offline reconstruction of the electron density profile with diagnostics not available in real-time, density controller design (owing to its provision of analytical Jacobians), and fast offline density profile simulation.</div><div>This contribution presents the improvements made to its predictive model by introducing different boundary conditions, in particular a non-zero, time-varying density at the separatrix. Incorporating the dependence of separatrix density on gas fueling in the non-zero boundary condition improves the quality of the offline simulations used for controller design. Furthermore, this adjustment enhances the versatility of the RAPDENS predictive model, allowing for more efficient density profile reconstruction across a broader range of discharge scenarios and reducing the effort needed to find a suitable combination of tuning parameters to match the density profile at the edge.</div><div>A method using a real-time compatible empirical formula (Kallenbach et al. 2018) to determine the separatrix density as a boundary condition for AUG discharges is proposed, and the results of offline RAPDENS simulations are compared with the density profile reconstructed using integrated data analysis (IDA) (Fischer et al. 2010).</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115196"},"PeriodicalIF":1.9,"publicationDate":"2025-06-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144291029","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":"Hydraulic analysis of the DTT divertor module","authors":"Davide Caprini ,&nbsp;Morena Angelucci ,&nbsp;Emanuela Martelli ,&nbsp;Fabio Crescenzi ,&nbsp;Francesco Giorgetti ,&nbsp;Nicola Massanova ,&nbsp;Pietro Vinoni ,&nbsp;Domenico Marzullo ,&nbsp;Selanna Roccella","doi":"10.1016/j.fusengdes.2025.115234","DOIUrl":"10.1016/j.fusengdes.2025.115234","url":null,"abstract":"<div><div>Understanding coolant flow behaviour in the divertor module is critical for managing the high thermal loads encountered in Tokamak plasma scenarios. Effective cooling ensures system integrity, optimal performance, and prolonged component lifetime, especially in high-heat flux environments. This study investigates the hydraulic performance of the DTT (Divertor Tokamak Test) divertor module, focusing on achieving uniform flow distribution.</div><div>The DTT facility, under construction at ENEA C.R. Frascati, is designed to explore power exhaust solutions for DEMO. The initial DTT divertor comprises 54 water-cooled modules, each handling a total mass flow rate of 577 kg/s with water temperatures ranging here considered from 30 °C to 74 °C. Each module includes an Outer Target (OT), Inner Target (IT), and Central Target (CT), with coolant entering through an outboard manifold and flowing through nine OT tubes. Two of the external pipes return directly to the outlet manifold, while the remaining pipes continue through additional components, necessitating calibrated orifices to achieve balanced flow distribution.</div><div>A Computational Fluid Dynamics (CFD) model was developed to optimize orifice sizing in OT pipes and evaluate flow uniformity. Sensitivity analyses assessed the effects of bulk water temperature variations and manufacturing tolerances on orifice dimensions. The model also examined total pressure drops and localized losses caused by twisted tapes in the tubes promoting flow swirling. Finally, the impact of flow rate fluctuations on critical heat flux was analysed, offering insights into the hydraulic system robustness under variable conditions. Simulations were performed using ANSYS software, providing an evaluation of the divertor module cooling performance.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115234"},"PeriodicalIF":1.9,"publicationDate":"2025-06-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144289070","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":"Fusion alpha power control optimisation using RAPTOR","authors":"J. Mitchell ,&nbsp;A. Mitra ,&nbsp;S. Van Mulders ,&nbsp;F.J. Casson ,&nbsp;E. Tholerus ,&nbsp;K. Kirov ,&nbsp;S. Freethy ,&nbsp;F.E. Eriksson ,&nbsp;C.E. Contré ,&nbsp;O. Sauter ,&nbsp;M. Lennholm ,&nbsp;H. Meyer ,&nbsp;STEP Plasma Control Team","doi":"10.1016/j.fusengdes.2025.115202","DOIUrl":"10.1016/j.fusengdes.2025.115202","url":null,"abstract":"<div><div>The Spherical Tokamak for Energy Production (STEP) is a prototype fusion power plant planned to be operational in the 2040s. STEP’s interaction with the national grid and its responsiveness to demand hinges largely on the effective control of the energy released during the fusion burn phase, i.e., the alpha power, which acts as the dominant form of heating in STEP. This research explores novel trajectory optimisation and control methods to regulate the alpha power, while maintaining other global and local plasma parameters such as internal inductance and safety factor. The RApid Plasma Transport simulatOR (RAPTOR) code is used to self-consistently solve four coupled, 1D PDE equations for poloidal flux diffusion, electron thermal transport, ion thermal transport and electron particle transport. Since STEP has limited space for a central solenoid, the flattop stationary state must be sustained with 100% non-inductive sources (predominately bootstrap current and electron cyclotron heating and current drive). To this end we also introduce a new Dirichlet boundary condition (BC) for the flux diffusion equation which allows the plasma boundary flux to be used as an actuator rather than plasma current (Neumann BC). The RAPTOR code open loop optimisation framework is used to solve this multi-objective, constrained, non-linear, finite-time optimal control problem.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115202"},"PeriodicalIF":1.9,"publicationDate":"2025-06-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144280999","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":"Electromechanical characterization of REBCO twisted stack slotted-core cable under twisting and bending stress","authors":"Shu Tao ,&nbsp;Zekun Jin ,&nbsp;Xianfeng Xu ,&nbsp;Shijie Shi ,&nbsp;Xilong Yang ,&nbsp;Hongjun Ma ,&nbsp;Yi Shi ,&nbsp;Jinggang Qin ,&nbsp;Huajun Liu","doi":"10.1016/j.fusengdes.2025.115266","DOIUrl":"10.1016/j.fusengdes.2025.115266","url":null,"abstract":"<div><div>The rapid development of high-temperature superconducting (HTS) technology has led to the emergence of HTS cables based on REBCO tapes as a key solution for future fusion magnets. The development of stacked HTS cables has become a focal point of research due to their exceptional current-carrying capacity and mechanical properties. However, the cables are subjected to complex twisting and bending stresses during the fabrication of the coils. It is therefore imperative to investigate the effects of these stresses on the electromechanical behavior of Twisted Stack Slotted-core Cable (TSSC) in order to optimize the design of fusion magnets. This paper presents a theoretical analysis of the impact of mechanical deformation of REBCO tape on the critical current (<em>I_c</em>) under varying twist pitch and bending radius conditions. The bending radii corresponding to the no-slip and perfect-slip models are approximately 1100 mm and 300 mm, respectively, when the criterion is taken to be 95 % <em>I_c</em> retention. Furthermore, an experimental comparison of the performance changes of the samples under bending stress, both before and after vacuum soldering, is conducted to evaluate the effect of the soldering process on the bending performance. The experimental results demonstrate that the pre-bending-before-soldering process can effectively control the bending radius, thereby reducing the impact of stress concentration on the superconducting performance and significantly improving the stability of the cable under complex mechanical loads. This process not only improves the reliability of HTS TSSC in fusion magnet applications, but also provides a key technical support for the manufacture and application of large-scale superconducting cables in the future.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115266"},"PeriodicalIF":1.9,"publicationDate":"2025-06-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144281129","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 liquid spray neutralizer for neutral beam injection (NBI) for fusion devices","authors":"Sargis Ter-Avetisyan","doi":"10.1016/j.fusengdes.2025.115262","DOIUrl":"10.1016/j.fusengdes.2025.115262","url":null,"abstract":"<div><div>High energy negative ion and neutral atom beams have been observed by irradiating the liquid spray of sub-micron droplets with laser-accelerated positive ions, namely hydrogen and carbon. It is shown that the electron capture by positive ions in the spray environment enables the production of negative ions <span><math><msup><mrow><mi>H</mi></mrow><mo>−</mo></msup></math></span> and <span><math><msup><mrow><mi>C</mi></mrow><mo>−</mo></msup></math></span> and neutral atoms of <span><math><msup><mrow><mi>H</mi></mrow><mn>0</mn></msup></math></span> and <span><math><msup><mrow><mi>C</mi></mrow><mn>0</mn></msup></math></span>. The energy dependent conversion efficiency of positive ions to negative and neutral atoms is shown. For <span><math><msup><mrow><mi>C</mi></mrow><mn>0</mn></msup></math></span> and <span><math><msup><mrow><mi>C</mi></mrow><mo>−</mo></msup></math></span> at projectile energies above 600 keV, saturation is observed at about 40 % and 13 %, respectively, while for <span><math><msup><mrow><mi>H</mi></mrow><mn>0</mn></msup></math></span> and <span><math><msup><mrow><mi>H</mi></mrow><mo>−</mo></msup></math></span> the conversion efficiency decreases with increasing energy. This proof of principle experiment promises increased neutralization efficiency of positive ion beams in neutral beam injection beamlines. This much simple system as compared to gas neutralizers can be an attractive option and require further study.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115262"},"PeriodicalIF":1.9,"publicationDate":"2025-06-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144271502","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":"Application of the radio species transport model to the JSI water activation loop","authors":"Eduardo Masiá ,&nbsp;Francesca Cau ,&nbsp;Aljaz Kolsek ,&nbsp;Raúl Pampín ,&nbsp;Marco Fabbri ,&nbsp;Luka Snoj ,&nbsp;Domen Kotnik ,&nbsp;Rosaria Villari ,&nbsp;Alfredo Portone","doi":"10.1016/j.fusengdes.2025.115264","DOIUrl":"10.1016/j.fusengdes.2025.115264","url":null,"abstract":"<div><div>The development of analysis tools to calculate the activation of flowing water under irradiation is essential for fusion technology and for the ITER project. The Radio-Species Transport Model (RSTM) method is a simulation methodology developed by Fusion for Energy based on the Ansys Fluent® user-defined scalar (UDS) approach. It predicts the activation of a flowing fluid in domains where neutron fields and flow regimes require the coupling of activation and fluid dynamic effects. RSTM was successfully applied to ITER First Wall (FW) studies and benchmarked against experiments at the Frascati Neutron Generator (FNG).</div><div>This research focuses on the application of the RSTM to the KATANA closed water activation loop at the JSI TRIGA Mark II fission reactor, as part of the EUROfusion Preparation of ITER Operation (PrIO) programme. Future work will compare these results with experimental data and other predictive tools including ActiFlow, GammaFlow (by UKAEA) and FLUNED (by UNED).</div><div>In the next phase of operation, the KATANA facility aims to tackle experiments more relevant to ITER conditions. For this reason, Fusion for Energy is applying RSTM to design an alternative irradiation head that resembles the cooling circuit of an ITER First Wall panel, this being one of the main components where the water undergoes activation.</div><div>This study shows the results of the RSTM tool for the current configuration of the JSI KATANA water activation loop. Conclusions are drawn on the relevance of the alternative ITER-relevant irradiation head for the next phase of the JSI water activation loop.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115264"},"PeriodicalIF":1.9,"publicationDate":"2025-06-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144281130","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":"Electrical conductivity of zirconia for flow channel inserts in contact with liquid Pb-16Li","authors":"Jaroslav Kekrt,&nbsp;Roman Petráš,&nbsp;Adéla Gottfriedová,&nbsp;Vojtěch Svoboda,&nbsp;Ladislav Vála","doi":"10.1016/j.fusengdes.2025.115260","DOIUrl":"10.1016/j.fusengdes.2025.115260","url":null,"abstract":"<div><div>Flow channel inserts (FCI) as functional components are being developed for the Dual Coolant Lithium Lead breeding blanket. Since the aim is to electrically decouple the main flow of liquid lead lithium and a steel structure of the blanket, knowledge of electrical properties of the FCI materials is crucial. For this purpose, series of direct electrical current measurements were performed on oxide ceramic – <em>ZrO₂</em> in a form of yttria stabilized zirconia. Initially, the electrical conductivity was determined in temperature range of 240-520 °C in an inert oxygen-free atmosphere using two working electrodes on the opposite sides of a flat sample. Subsequently, the electrical properties of the samples were determined using liquid Pb-16Li as a substitution of one of the electrodes, under otherwise identical experimental conditions.</div><div>The electrical conductivity of materials in the given temperature range is well below the required limit of the Flow channel inserts.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115260"},"PeriodicalIF":1.9,"publicationDate":"2025-06-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144271501","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":"Conceptual studies for the EU-DEMO EC heating system transmission line","authors":"A. Bruschi ,&nbsp;M. Ciambella ,&nbsp;D. Dongiovanni ,&nbsp;F. Fanale ,&nbsp;P. Fanelli ,&nbsp;S. Garavaglia ,&nbsp;T. Glingler ,&nbsp;S. Marsen ,&nbsp;T. Pinna ,&nbsp;P. Platania ,&nbsp;N. Rispoli ,&nbsp;A. Salvitti ,&nbsp;A. Simonetto ,&nbsp;T. Stange ,&nbsp;M. Toussaint ,&nbsp;D. Wagner","doi":"10.1016/j.fusengdes.2025.115241","DOIUrl":"10.1016/j.fusengdes.2025.115241","url":null,"abstract":"<div><div>The Electron Cyclotron (EC) Heating system for the EU-DEMO tokamak, designed within the EUROfusion consortium activities as a device to demonstrate the feasibility of a Fusion Reactor, will inject power in different plasma locations to provide a series of tasks, including plasma current ramp-up and ramp-down, central (Bulk) Heating (BH), Neoclassical Tearing Modes (NTM) stabilization, Radiative Instability (RI) control. For fulfilling the tasks, a large amount of mm-wave power at different frequencies has to be generated, transmitted for more than hundred meters, and finally injected into the torus. The transmission line concept being developed is capable to carry multiple frequencies at the same time and can be adapted to final changes of the physics baseline made for optimizing the DEMO performances. The transmission line is arranged in a modular way, in order to be tailored to the final requests of power and reliability, determining the number of gyrotron sources and used ports. The basis of the organization of the system is the “cluster” of sources that share a single multi-beam (MB) transmission line, with one or two clusters sharing the same EC launcher in the equatorial port of DEMO. In this work the basic design and the layout of the transmission line is described, as well as the options for the routing, the MB mirror layout and the grouping in clusters based on reliability calculations. It also describes the work on the broadband polarizers with minimal losses, the coupling of the TEM00 beams to the waveguides, the MB mirror cooling design and the electromagnetic evaluations of transmitted beams to evaluate the coupling losses due to mirror thermal and gravity deformations.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115241"},"PeriodicalIF":1.9,"publicationDate":"2025-06-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144262366","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}