Fusion Engineering and Design最新文献

{"title":"Design and integration of the DTT water coolant systems","authors":"M. Utili ,&nbsp;A. Cucchiaro ,&nbsp;P. Fusco ,&nbsp;M. De Santis ,&nbsp;A. Iaboni ,&nbsp;P. Meller ,&nbsp;M. Micheletti ,&nbsp;N. Paganucci ,&nbsp;A. Pizzuto ,&nbsp;G.M. Polli","doi":"10.1016/j.fusengdes.2025.115347","DOIUrl":"10.1016/j.fusengdes.2025.115347","url":null,"abstract":"<div><div>The primary water cooling system of Divertor Tokamak Test (DTT) facility consists of the circuit which directly cool down the plasma face components of the tokamak, the Inner, TOP and Outboard First Wall and Divertor modules. The systems have been designed in order to handle the maximum plasma heating power of 32.2MW from the First Wall and 30MW for the Divertor modules for 100 s and to perform the baking of the FW and DIV modules. The FW Water Coolant System (WCS) is constituted by the pumping system, heat exchanger storage tanks placed in the auxiliary building (building 174) and pipe lines, pressuriser, instrumentation and valves, placed in the torus hall (building 185). The FW-WCS can manage the total mass flow rate of 381kg/s at 60 °C in five lines: Inner standard and limiter FW; Top FW and Outboard FW Port 2 and Port 3. During the Light Baking the system will be operated at 130 °C and 200 °C during the Strong Baking. Instead, the Divertor WCS is able to manage the total mass flow rate of 577kg/s for the 54 standard divertor modules.</div><div>The WCSs have been designed and integrated in the vacuum vessel, cryostat and torus hall taking into account the requirements of the Remote Handling System and diagnostics.</div><div>The paper describes the thermo-fluid dynamic design of the FW and DIV primary Water Cooling Systems, the sizing of main components and pipes network and the integration inside DTT facility. The P&amp;ID and 3D modeling in torus hall are presented.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115347"},"PeriodicalIF":2.0,"publicationDate":"2025-08-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144810149","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":"Upgrade and first measurements of the fast ion loss detector on the HL-3 tokamak","authors":"Y.X. Han ,&nbsp;J. Zhang ,&nbsp;J.L. Xie ,&nbsp;W. Chen ,&nbsp;H.B. Xu ,&nbsp;Y.P. Zhang ,&nbsp;C.X. Zhang ,&nbsp;Y.X. Zhu ,&nbsp;S. Xu ,&nbsp;Y.B. Dong ,&nbsp;Q.L. Yang ,&nbsp;J.Q. Wang ,&nbsp;X.W. Zhan ,&nbsp;Y.S. Zhang ,&nbsp;S. Guan ,&nbsp;G. Zhuang ,&nbsp;HL-3 Team","doi":"10.1016/j.fusengdes.2025.115361","DOIUrl":"10.1016/j.fusengdes.2025.115361","url":null,"abstract":"<div><div>The fast ion loss detector (FILD) on the HL-3 tokamak was upgraded in the experiments of 2024 Q1. A new dual-collimator detector was designed to reduce self-shadow. The effect of the rotation angle of the detector on self-shadow was analysed in order to determine the appropriate rotation angle. By inverting the orbits of lost ions in a three-dimensional model incorporating the components of the vacuum chamber, the external-shadow of the detector was analysed, and then the appropriate position of the detector was determined. Based on the upgrade of the FILD system described above, fast ion losses induced by MHD instabilities such as fishbone and sawtooth were observed in the experiments of 2024 Q1.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115361"},"PeriodicalIF":2.0,"publicationDate":"2025-08-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144781406","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":"One-dimensional simulations of nonlinear burn control in ITER","authors":"Vincent Graber,&nbsp;Eugenio Schuster","doi":"10.1016/j.fusengdes.2025.115362","DOIUrl":"10.1016/j.fusengdes.2025.115362","url":null,"abstract":"<div><div>Actively controlling the plasma temperature and density in future reactor-grade tokamaks will be a formidable challenge due to the multi-dimensional, coupled, and nonlinear characteristics of the burning-plasma dynamics. In ITER, the actuator systems that will be useful for temperature–density control (also known as burn control) include neutral beam injection, ion and electron cyclotron heating, pellet injection, and gas puffing. In this work, a nonlinear, model-based, burn-control algorithm is proposed. A model-based approach is attractive because it directly incorporates the complex plasma dynamics into the burn-control algorithm. Using Lyapunov techniques, the burn-control algorithm is synthesized from a control-oriented plasma model that is zero-dimensional (0-D). The reduced dimensionality of this plasma model renders the burn-control design more feasible. Nonetheless, this 0-D plasma model still captures the nonlinear response of the plasma energy and density to deuterium–tritium (D–T) fusion, radiation, auxiliary heating, external fueling, and other phenomena. More importantly, the control objective is indeed 0-D since the primary goal of a burn controller is usually to regulate volume-averaged properties of the plasma (e.g., overall fusion power <span><math><msub><mrow><mi>P</mi></mrow><mrow><mi>f</mi></mrow></msub></math></span> or fusion gain <span><math><mi>Q</mi></math></span>). This makes 0-D models appropriate for control synthesis. However, the assessment of the effect of the proposed 0-D burn-control algorithms on the spatio-temporal dynamics of the plasma is a critical step of the control-design process. This work presents a one-dimensional (1-D) plasma model that is used in closed-loop simulations. The presented simulation study demonstrates how the spatial profiles of the D–T fuel density, the fusion-born alpha-particle density, the ion energy density, and the electron energy density evolve temporally under 0-D burn control. By testing 0-D controllers in 1-D simulations, the effectiveness of 0-D burn-control techniques can be investigated before implementation in actual tokamaks. Through investigations of this kind, control issues can be identified and addressed, enabling iterative improvement of the burn-control designs.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115362"},"PeriodicalIF":2.0,"publicationDate":"2025-08-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144781407","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 distributed real-time diagnostic and control network for the TCV tokamak based on the Data Distribution Service","authors":"R. Masocco ,&nbsp;A. Tenaglia ,&nbsp;C. Galperti ,&nbsp;D. Carnevale ,&nbsp;S. Galeani ,&nbsp;TCV Team ,&nbsp;EUROfusion Tokamak Exploitation Team","doi":"10.1016/j.fusengdes.2025.115344","DOIUrl":"10.1016/j.fusengdes.2025.115344","url":null,"abstract":"<div><div>A novel communication network is being implemented on the machines composing the Système de Contrôle Distribué (SCD) that form the real-time architecture of the Tokamak à Configuration Variable (TCV), exploiting the capabilities of the Data Distribution Service (DDS) middleware. This work presents a new DataSource for the MARTe2 framework that integrates the eProsima Fast DDS implementation. Its design is discussed, providing tools to configure the behavior of the DDS middleware, and its validation is performed by benchmarks on the SCD nodes hardware. The advantages of this work are twofold. First, the intention is to expand the capabilities of the SCD, which originally relies on a reflective memory that, although deterministic, requires specialized hardware and offers limited bandwidth and scalability. Secondly, integration of the DDS into the SCD enables more diagnostics to work in real time, expanding the experimental capabilities of the TCV device.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115344"},"PeriodicalIF":2.0,"publicationDate":"2025-08-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144770801","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":"Influence of the iron core on three-dimensional magnetic field in the J-TEXT tokamak","authors":"Hao Man,&nbsp;Nengchao Wang,&nbsp;Zhengkang Ren,&nbsp;Yangbo Li,&nbsp;Feiyue Mao,&nbsp;Xinchen Yao,&nbsp;Chuanxu Zhao,&nbsp;Chengshuo Shen,&nbsp;Song Zhou,&nbsp;Yonghua Ding,&nbsp;the J-TEXT Team","doi":"10.1016/j.fusengdes.2025.115374","DOIUrl":"10.1016/j.fusengdes.2025.115374","url":null,"abstract":"<div><div>The ferromagnetic materials non-axisymmetrically installed in tokamaks can induce three-dimensional (3D) errors to the axisymmetric magnetic field, i.e., the error field (EF). On the J-TEXT tokamak, the two-limb iron core induced EF is measured in the experiments, which defined its toroidal mode number <em>n</em> = 2. By including the 3D iron core model, the finite element analysis (FEA) reproduces the experimental measurement, further reveals characteristics of this EF and evaluates its potential impact on plasma experiments. The influence of the two-limb iron core on the magnetic field from the <em>n</em> = 2 helical coils, called external rotational transform coils (Li Y B et al. 2024 <em>Fusion Eng. Des.</em> <strong>206</strong> 114,591), is also studied, along with a qualitative discussion on the saturation effect of iron core.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115374"},"PeriodicalIF":2.0,"publicationDate":"2025-08-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144767044","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Thermal-hydraulic analysis of WCLL BB First-Wall mock-up in Water Loop facility under transient conditions","authors":"G. Mongiardini ,&nbsp;A. Vannoni ,&nbsp;C. Ciurluini ,&nbsp;P. Maccari ,&nbsp;B. Gonfiotti ,&nbsp;P. Arena ,&nbsp;M. Eboli ,&nbsp;F. Giannetti ,&nbsp;A. Del Nevo","doi":"10.1016/j.fusengdes.2025.115375","DOIUrl":"10.1016/j.fusengdes.2025.115375","url":null,"abstract":"<div><div>The EUropean DEMOnstration Power Plant (EU-DEMO) represents a milestone in nuclear fusion research, serving as crucial step towards the realization of commercial fusion energy production by bridging the gap between current research efforts and future industrial-scale deployment. A key component of the reactor is the Breeding Blanket (BB) that must perform several essential functions for the proper DEMO operation. Two primary concepts for BB have been proposed for DEMO: the Water Cooled Lithium Lead (WCLL) and the Helium Cooled Pebble Bed (HCPB). Both concepts are going to be tested under realistic fusion reactor conditions in ITER, in the form of Test Blanket Modules (TBMs). In this framework, at the ENEA R.C. Brasimone, the construction of an experimental infrastructure called W-HYDRA is ongoing. It is dedicated to the investigation of the water and lithium-lead technologies applied to the fusion research field. As part of the W-HYDRA infrastructure, Water Loop facility will investigate WCLL BB components, such as a First-Wall (FW) test section. The design characteristics and performance of the mock-up will be assessed to provide valuable experimental results in view of DEMO operation. The present paper is focused on the thermal-hydraulic numerical study of the WCLL BB FW test section within Water Loop facility using RELAP5/Mod3.3. Specifically, the study investigates expected operating transients (i.e., pulse-dwell and dwell-pulse transients) and accidental scenarios (i.e., Loss Of Feedwater Accident, LOFA), with the aim of supporting the design phase by providing preliminary results on the Water Loop facility and on the mock-up operation.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115375"},"PeriodicalIF":2.0,"publicationDate":"2025-08-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144757912","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":"Neutronic effects of the pebble bed model on tritium breeding calculations for fusion blankets","authors":"Shiteng Zhang,&nbsp;Haibing Guo","doi":"10.1016/j.fusengdes.2025.115377","DOIUrl":"10.1016/j.fusengdes.2025.115377","url":null,"abstract":"<div><div>In the design of fusion blankets, the tritium breeding region is typically filled with a large number of lithium ceramic particles, forming a pebble bed with a complex porous structure. This configuration facilitates fast tritium release and online extraction while mitigating thermal stress in the lithium ceramics. Due to the complexity of the pebble bed structure, it is difficult to directly model the pebble bed structure in neutronic calculations. The homogenized model is usually used to macroscopically approximate the pebble bed structure in neutronic calculations. However, the deviation of neutronic performance introduced by homogenization has not been fully evaluated. In this paper, two regular packing pebble bed models and a random packing pebble bed model were constructed by using OpenMC. The accuracy of the random packing pebble bed was verified by comparing the calculated results of different models with the experimental results of the Li₂O blanket mockup. This comparison demonstrated that the random packing pebble bed model better represents the spatial distribution of tritium production rate in the real pebble bed structure, with the C/E value deviation from 1.0 reduced by 20 %. Subsequently, the pebble bed models were applied to the solid breeder pebble bed blanket. Take the homogenized model as a reference, a systematic evaluation was conducted to assess the impact of the pebble bed model on tritium breeding neutronic calculations. Local variation of the packing factor was found to cause significant differences in neutronic characteristics in the near-wall regions, while the overall tritium generation rate deviation in the entire region is relatively small. In the thermal neutron energy range, the pebble bed model exhibits significant differences compared to the homogenized model.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115377"},"PeriodicalIF":2.0,"publicationDate":"2025-08-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144757911","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":"Calibration of a novel near-infrared phase contrast imaging on the HL-3 Tokamak","authors":"Hao Xu ,&nbsp;Shaobo Gong ,&nbsp;Yi Yu ,&nbsp;Chenyu Xiao ,&nbsp;Min Xu ,&nbsp;Tao Lan ,&nbsp;Zhibin Wang ,&nbsp;Zhongbing Shi ,&nbsp;Lin Nie ,&nbsp;Rui Ke ,&nbsp;Guangyi Zhao ,&nbsp;Hao Liu ,&nbsp;Yixuan Zhou ,&nbsp;Zihao Yuan ,&nbsp;Jian Chen ,&nbsp;Wulv Zhong","doi":"10.1016/j.fusengdes.2025.115340","DOIUrl":"10.1016/j.fusengdes.2025.115340","url":null,"abstract":"<div><div>An original near-infrared phase contrast imaging (NI-PCI) diagnostic has recently been developed on the HL-3 tokamak. This diagnostic obtains the frequency–wavenumber spectrum of plasma density perturbations by measuring the phase shift of a near-infrared laser beam at a wavelength of 1550 nm as it traverses through the plasma, enabling broad spectrum turbulence measurements in HL-3 tokamak experiments. A prototype system of the NI-PCI diagnostic was constructed and calibrated using acoustic waves. Calibration results indicate that the system’s wavenumber measurement range is from <span><math><mrow><mn>5</mn><mo>.</mo><mn>24</mn><mspace></mspace><msup><mrow><mi>cm</mi></mrow><mrow><mo>−</mo><mn>1</mn></mrow></msup></mrow></math></span> to <span><math><mrow><mn>35</mn><mo>.</mo><mn>32</mn><mspace></mspace><msup><mrow><mi>cm</mi></mrow><mrow><mo>−</mo><mn>1</mn></mrow></msup></mrow></math></span>, with a wavenumber resolution reaching <span><math><mrow><mn>1</mn><mo>.</mo><mn>51</mn><mspace></mspace><msup><mrow><mtext>cm</mtext></mrow><mrow><mo>−</mo><mn>1</mn></mrow></msup></mrow></math></span> and a temporal resolution better than <span><math><mrow><mn>1</mn><mspace></mspace><mi>μ</mi><mi>s</mi></mrow></math></span>. Compared to conventional PCI diagnostics, the upper limit of the wavenumber measurement for NI-PCI has been increased by 2.6 times under the same device conditions.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115340"},"PeriodicalIF":2.0,"publicationDate":"2025-08-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144749541","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":"Computing material volume fractions on a superimposed mesh as applied to Monte Carlo particle transport simulations","authors":"Paul K. Romano ,&nbsp;Samuel Pasmann ,&nbsp;Patrick C. Shriwise ,&nbsp;Charles P.S. Swanson","doi":"10.1016/j.fusengdes.2025.115364","DOIUrl":"10.1016/j.fusengdes.2025.115364","url":null,"abstract":"<div><div>We present a newly implemented ray tracing algorithm in OpenMC for efficiently computing material volume fractions on superimposed meshes in complex geometries. By firing rays along each coordinate direction through the geometry, the approach accumulates track-length data in each mesh element, thereby determining the fractional composition of each material. Storing the accumulated track-length data using an open-addressed hash table minimizes the potential memory footprint and, when paired with lock-free atomic compare-and-swap probing, removes thread contention to enable efficient parallel execution. Scaling studies on three different models—a random tetrahedra configuration, the Frascati Neutron Generator ITER dose rate benchmark, and a stellarator design—show excellent parallel performance, with nearly linear speedup on modern multi-threaded and distributed-memory systems. An analysis of the residual error relative to high-resolution reference solutions demonstrated that under optimal conditions it decreases as 1/<span><math><mi>R</mi></math></span>, where <span><math><mi>R</mi></math></span> is the number of rays fired, making it straightforward to achieve user-prescribed accuracy. This new functionality enables practical, mesh-based approaches for detailed nuclear analyses in production Monte Carlo workflows without resorting to expensive, fully conformal or unstructured meshing.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115364"},"PeriodicalIF":2.0,"publicationDate":"2025-08-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144749542","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Thermal-hydraulic analysis of the CORCⓇ conductor for the DEMO CS coil","authors":"Monika Lewandowska ,&nbsp;Aleksandra Dembkowska ,&nbsp;Rafał Ortwein ,&nbsp;Arend Nijhuis ,&nbsp;Giulio Anniballi ,&nbsp;Lorenzo Giannini ,&nbsp;Danko C. van der Laan ,&nbsp;Jeremy Weiss ,&nbsp;Gianluca De Marzi ,&nbsp;Davide Uglietti","doi":"10.1016/j.fusengdes.2025.115368","DOIUrl":"10.1016/j.fusengdes.2025.115368","url":null,"abstract":"<div><div>Conductors using High Temperature Superconductor (HTS) tapes are considered as a very promising solution for future high-field fusion magnets. Various HTS cable concepts, such as e.g. twisted stack cable, cross-conductor (CroCo), Roebel assembled coated conductor (RACC), conductor on round core (CORC^Ⓡ), HTS cable-in-conduit conductor (CICC), aligned stacks transposed in Roebel arrangement (ASTRA) have been proposed. Some of them are already considered for potential use in some components of the EU-DEMO magnet system. Recently a design of a conductor based on the CORC^Ⓡ concept for the innermost layer of the hybrid Central Solenoid (CS) coil of EU-DEMO was proposed. In the present work we simulated, using the THEA code by Cryosoft, normal operation of this conductor during the current cycle. Two variants of the CS1 geometry were considered: a single CS1 module, and a CS1 module split into two sub-modules (CS1L and CS1U) located one above the other. Taking into account heat loads due to the hysteresis and coupling losses, resulting from time evolution of the magnetic field profile along the conductor, we estimated the minimum temperature margin in the conductor, to verify if it fulfills the performance criterion: min(Δ<em>T_marg</em>) &gt; 1.5 K. The results obtained with the 1D THEA model were complemented by the results of simulations with the ANSYS Mechanical APDL model (3D solid + 1D fluid) aimed at the assessment of radial temperature gradients in the conductor cross-section.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115368"},"PeriodicalIF":2.0,"publicationDate":"2025-08-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144749544","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}