Progress in Nuclear Energy最新文献

{"title":"Influence of network modifiers on the physical, structural, elastic, thermal properties of lead boroaluminate glasses for advanced radioactive waste management","authors":"M. Vijayakumar ,&nbsp;J. Inico Valanarasi ,&nbsp;K. Ramachandran ,&nbsp;M.S. Al-Buriahi ,&nbsp;Nada Alfryyan ,&nbsp;P. Devendran ,&nbsp;K. Maheshvaran","doi":"10.1016/j.pnucene.2025.106187","DOIUrl":"10.1016/j.pnucene.2025.106187","url":null,"abstract":"<div><div>In this study, a series of europium ions incorporated lead boroaluminate glasses containing a composition of 69B₂O₃+5Al₂O₃+10PbO+15MO+1Eu₂O₃ (where M = Li₂O, Na₂O, K₂O, MgO, CaO, SrO in wt%) were synthesized and characterized to evaluate their potential for radiation shielding applications. The influence of various alkali and alkaline earth modifiers on physical, structural, thermal and elastic properties was systematically examined. Density showed a clear compositional dependence, increasing from 3.155 g/cm³ (K) to 3.897 g/cm³ (Sr), while the molar volume varied between 18.375 and 25.416 cm³/mol, reflecting the combined effects of cation size and field strength on network packing. The refractive index increased steadily from n_d = 1.632 (Li) to n_d = 1.881 (Sr), consistent with enhanced polarizability in heavier modifier-containing glasses. FTIR spectral analysis revealed significant structural changes, including the transformation of BO₃ to BO₄ units and a reduction in non-bridging oxygens, confirming enhanced polymerization. Mechanical studies showed that Sr²⁺- and Ca²⁺-rich glasses exhibited superior Young's, shear, and bulk moduli, reflecting better mechanical strength and rigidity. Thermal analysis through TG/DSC indicates the well-defined glass transition and crystallization events, with T_g and ΔT values strongly dependent influenced by the modifiers. Radiation shielding performance was evaluated using parameters such as mass attenuation coefficient (MAC), mean free path (MFP), half-value layer (HVL), electron density (N_eff) and effective atomic number (Z_eff). The radiation-shielding performance improved across the series, with MAC decreasing from 0.090 to 0.063 cm²/g, HVL reducing from 3.23 to 3.04 cm, and MFP shortening from 5.02 to 4.11 cm at 1 MeV while incorporating different modifiers from Li to Sr in the present compositions. Glasses containing Ca and Sr demonstrated enhanced photon interaction probabilities and reduced penetration depths compared to conventional shielding concretes. Moreover, buildup factor analysis and fast neutron removal cross-sections (FNRC) confirmed the dual-mode shielding capability of these glasses. The performance of the prepared glasses is benchmarked against commercial glass types such as RS 253, RS 360, RS 520, and RS G18/G19 and shielding concretes. The findings establish that careful selection of modifier oxides, especially Sr²⁺ and Ca²⁺, significantly enhances both structural and shielding efficiency, positioning these glasses as promising alternatives for compact and efficient radiation shielding materials in the advance nuclear waste management amenities.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"192 ","pages":"Article 106187"},"PeriodicalIF":3.2,"publicationDate":"2025-12-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145681060","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":"Experimental study on discharge behavior in automatic depressurization system: High pressure two phase discharge characteristics of pipeline","authors":"Zhengrun Shang ,&nbsp;Dufeng Lv ,&nbsp;Zhongning Sun ,&nbsp;Zhaoming Meng ,&nbsp;Pei Yu","doi":"10.1016/j.pnucene.2025.106184","DOIUrl":"10.1016/j.pnucene.2025.106184","url":null,"abstract":"<div><div>To investigate the high pressure two phase discharge characteristics within the multi-stage pipelines of automatic depressurization system (ADS) under actual operating conditions, this study conducted experimental research on high pressure two phase discharge in multi-stage pipelines. The results shows that with an increase the number of depressurization stages, the pressure drop percentage of the discharge main pipeline increases, and the pressure drop percentage of ADS valve package decreases. Additionally, the position of the maximum pressure drop percentage in the valve package migrates upstream with the increase of depressurization stages. When the equilibrium quality is 90∼100 % and the pressure is 2–13.6 MPa, the equilibrium quality along the flow direction initially decreases and then increases, and as the inlet pressure increases, the inflection point gradually moves downstream. In the other conditions, the equilibrium quality shows an upward trend. When the equilibrium quality is 10–90 %, the pressure is 0–13.6 MPa and the equilibrium quality is 0–10 %, the pressure is 2–13.6 MPa, the equilibrium quality changes significantly along the pipeline. And other conditions is not obvious.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"192 ","pages":"Article 106184"},"PeriodicalIF":3.2,"publicationDate":"2025-12-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145681056","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":"Same events, different trajectories: why countries reacted differently to the oil crisis, Chernobyl and Fukushima","authors":"Giacomo Dei,&nbsp;Giorgio Locatelli,&nbsp;Caterina Francescangeli,&nbsp;Sara Nanni","doi":"10.1016/j.pnucene.2025.106171","DOIUrl":"10.1016/j.pnucene.2025.106171","url":null,"abstract":"<div><div>Nuclear energy is a low-carbon technology playing a critical role in present and future energy systems. Yet, historically, national nuclear systems have followed strikingly divergent paths (some expanding and consolidating, while others phasing out) despite facing similar events, such as oil crises or nuclear accidents, occurring abroad. Understanding the reasons behind these divergent paths is an empirically relevant and academically underexplored area of research. This paper addresses this gap by investigating the factors that shape the resilience and continuity of national nuclear large technological systems (LTSs) (i.e., complex socio-technical configurations comprising both physical and non-material elements), analysing four European LTSs: France, the UK, Germany, and Italy. Through a multiple-case study approach, this paper examines how socio-economic, political, technological, socio-cultural, and environmental factors have shaped national responses to three key exogenous events, i.e., the 1970s oil crisis and the Chernobyl and Fukushima nuclear accidents. The analysis reveals that the pre-event configuration of factors within each nuclear LTS plays a critical role in shaping its post-event trajectory. While France and the UK maintained and reinforced their nuclear systems, Germany and Italy experienced destabilization and phase-out. This study presents a novel framework for understanding nuclear LTS resilience based on the dynamic alignment of key factors empirically identified in the four countries' LTS. Our results have broader implications for understanding the necessary interventions in a nuclear LTS to increase its resilience by investigating and assessing the configuration of factors and their evolution.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"192 ","pages":"Article 106171"},"PeriodicalIF":3.2,"publicationDate":"2025-12-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145681040","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":"Experimental and numerical study on the flow characteristics of perforated plates for Pellet bed reactor","authors":"Congqiang Si ,&nbsp;Kai Huang ,&nbsp;Nan Yang ,&nbsp;Dawen Zhong ,&nbsp;Yu Ji ,&nbsp;Jun Sun","doi":"10.1016/j.pnucene.2025.106177","DOIUrl":"10.1016/j.pnucene.2025.106177","url":null,"abstract":"<div><div>This study investigates the flow resistance characteristics of thick perforated plates (with relative thickness <em>t/d</em> ≥ 1.0) in a Pellet Bed Reactor (PeBR) for nuclear electric propulsion (NEP) through experiments and simulations. Experimental results show that pressure drop and flow resistance increase with higher inflow velocity. The hexagonal hole arrangement induces two distinct sizes of recirculation vortices near the wall downstream of the plate, which enhances flow resistance and energy dissipation. Additionally, the pressure loss coefficient is positively influenced by both a decrease in porosity <em>n</em> and an increase in relative thickness <em>t/d</em>. At a Reynolds number <em>Re</em> = 30,000, the pressure loss coefficient varies by 368.33 (<em>n</em> = 0.108–0.456, <em>t/d</em> = 1) and by 59.25 (<em>n</em> = 0.108, <em>t/d</em> = 1–10), demonstrating a greater sensitivity to <em>n</em>. A predictive model for the pressure loss coefficient, incorporating <em>n</em>, <em>t/d</em> and <em>Re</em>, was developed and achieved a prediction error within ±9 %. At high <em>Re</em>, due to the inability to rapidly reduce pressure, a Mach disk forms downstream of the perforated plates, weakening the plates throttling ability. When the ratio of local pressure to back pressure is greater than 0.86, the Mach disk is no longer observed. The study's findings provide critical insights for structural design and optimization of perforated plates in PeBR.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"192 ","pages":"Article 106177"},"PeriodicalIF":3.2,"publicationDate":"2025-12-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145681057","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 review of structural material compatibility in sodium-cooled nuclear reactors","authors":"Xiaoqiang Liu ,&nbsp;Xujia Wang ,&nbsp;Feng Wang ,&nbsp;Yiheng Wu ,&nbsp;Ziqiao Gong ,&nbsp;Zhao Shen ,&nbsp;Xiaoqin Zeng","doi":"10.1016/j.pnucene.2025.106179","DOIUrl":"10.1016/j.pnucene.2025.106179","url":null,"abstract":"<div><div>In response to growing global energy demands and specialized power needs in the marine, aerospace, and defense sectors, sodium-cooled heat pipe microreactors (SHPRs) have emerged as a key innovation in nuclear technology. This review systematically examines the development, technical characteristics, and material compatibility advances essential to the longevity and reliability of alkali metal heat pipe systems. It analyzes material degradation mechanisms in liquid sodium environments—focusing on dissolution corrosion kinetics, carbon migration-induced decarburization and carburization, and thermodynamic compatibility—to clarify corrosion behavior and its governing factors. By integrating material selection criteria, operational experience, and mechanistic models, this work provides a foundation for optimizing material performance under extreme thermal and chemical conditions. Ultimately, it supports the sustainable deployment of SHPRs to meet diverse energy challenges.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"192 ","pages":"Article 106179"},"PeriodicalIF":3.2,"publicationDate":"2025-12-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145681058","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":"Steady-state characteristics of a passive heat transfer system integrated with two-phase loop thermosyphon for SMRs","authors":"Xubin Wu,&nbsp;Wentao Hao,&nbsp;Wenwen Zhang,&nbsp;Weihua Li,&nbsp;Zhenlei Liu","doi":"10.1016/j.pnucene.2025.106094","DOIUrl":"10.1016/j.pnucene.2025.106094","url":null,"abstract":"<div><div>This study proposes a novel passive heat transfer system for Small Modular Reactors (SMRs), where a Two-Phase Loop Thermosyphon (TPLT) is integrated as an intermediate heat exchanger between the primary and secondary circuits. A RELAP5 model is developed to evaluate steady-state performance and sensitivity to key design parameters. Operating conditions results revealed that core power plays a decisive role in system performance. Besides, excessive feedwater flow or low core power prevents superheated steam generation at the steam generator outlet. Sensitivity results show that evaporator and condenser lengths strongly influence primary circuit temperatures, height difference controls TPLT circulation, and filling ratio significantly affects vapor void fraction. The baseline design achieves a core outlet temperature of 278.0 °C, a primary coolant flow of 5.7 kg/s, and superheated steam at 209.6 °C, with each thermosyphon carrying about 0.2 % of the core power. The study provides preliminary insights into the feasibility of this configuration for future SMR applications.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"192 ","pages":"Article 106094"},"PeriodicalIF":3.2,"publicationDate":"2025-12-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145924388","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":"Multi-physics coupling simulation of an electrorefiner for pyroprocessing of spent nuclear fuel","authors":"Wenzhou Sun ,&nbsp;Yiqun Xiao ,&nbsp;Yanhong Jia ,&nbsp;Liuming Yan ,&nbsp;Baohua Yue","doi":"10.1016/j.pnucene.2025.106182","DOIUrl":"10.1016/j.pnucene.2025.106182","url":null,"abstract":"<div><div>This paper presents the multi-physics coupling simulation for the precise control and optimization of the temperature and flow fields in an electrorefiner for pyroprocessing of spent nuclear fuel. The coupling temperature and flow fields in multi-domain of molten salt, argon gas atmosphere, electrodes, and stirring rod are systematically investigated using a multi-domain, multi-step and multi-physics modeling methodology. In argon gas atmosphere, the flow pattern with a maximum velocity at 157 mm s⁻¹ is mainly induced by the natural convection between the cooling cover at 300 K and the hot furnace at 773 K. In molten salt, the flow pattern with a maximum velocity at 25.1 mm s⁻¹ is driven essentially by the stirring instead of natural convection. The temperature difference is significant in the molten salt as it decreases from 773 K in contact with crucible to 719.1 K in contact with stirrer. Though increasing the stirring speed and height of the space between the molten salt and the cooling cover can improve significantly the temperature uniformity, the maximum temperature difference improves much slower than the average temperature difference. The great maximum temperature differences, at −33.5 K and −18.0 K, respectively, in the molten salt and at the electrode surfaces with a stirring speed at 300 rpm, will hinder the enlargement of an experimental scale electrorefiner to an engineering scale electrorefiner. Addition, the precise temperature field in molten salt adjacent to the electrodes is affected by Joule heat and electrochemical heat of electrorefining. Therefore, our multi-physics coupling simulation is significant for the precise control and optimization of pyroprocessing of spent nuclear fuel.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"192 ","pages":"Article 106182"},"PeriodicalIF":3.2,"publicationDate":"2025-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145681039","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":"Response of steam generator thermal-hydraulic characteristics under seismic loading","authors":"Xu Chen ,&nbsp;Yanjun Li ,&nbsp;Xin Zhang ,&nbsp;Jie Yang ,&nbsp;Guoxing Yu ,&nbsp;Yuanshao Sun ,&nbsp;Baozhi Sun ,&nbsp;Jianxin Shi ,&nbsp;Xin Zhou","doi":"10.1016/j.pnucene.2025.106161","DOIUrl":"10.1016/j.pnucene.2025.106161","url":null,"abstract":"<div><div>To address the challenge of predicting the thermal-hydraulic behavior of a steam generator (SG) under seismic excitation, this study developed an integrated numerical simulation methodology. Based on the SG design of the Daya Bay Nuclear Power Plant (DBNPP), a refined unit tube bundle model was constructed. The computational framework incorporates the coupling of multiphase flow equations with the Multiple Size Group model using Computational Fluid Dynamics (CFD), and the boiling heat transfer model under oscillatory conditions was validated via a User-Defined Function (UDF). Seismic loading was simulated by applying tri-directional accelerations based on the EI Centro seismic record, and the variation in thermal-hydraulic characteristics under multiple working conditions was systematically investigated by controlling the peak ground acceleration. The results demonstrate that: the frequency-domain response of the vapor mass fraction at the outlet under both transverse and longitudinal waves is predominantly concentrated in the low-frequency region; an increase in vapor fraction along the flow path significantly intensifies velocity fluctuations in both vapor and liquid phases; the overall system temperature stability and thermal inertia of the tube bundle effectively suppress drastic temperature fluctuations at the outlet; the coalescence and fragmentation of bubbles of varying sizes are identified as the mechanism causing fluctuations in vapor-related parameters at the secondary-side outlet. This study provides a theoretical foundation for the seismic design and safety assessment of SGs in nuclear power plants.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"192 ","pages":"Article 106161"},"PeriodicalIF":3.2,"publicationDate":"2025-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145681134","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":"Experimental simulations of aerosols produced during the Fukushima unit-3 in-vessel core degradation","authors":"Bence Mészáros ,&nbsp;Jana Sklenka ,&nbsp;Ayumi Itoh ,&nbsp;Jan Hrbek ,&nbsp;Mykhaylo Paukov ,&nbsp;Yoshinao Kobayashi ,&nbsp;Václav Tyrpekl","doi":"10.1016/j.pnucene.2025.106180","DOIUrl":"10.1016/j.pnucene.2025.106180","url":null,"abstract":"<div><div>Nowadays, several years after the severe accident triggered by the Tohoku earthquake in 2011 in Fukushima, Japan, significant efforts are targeted at the decommissioning and decontamination of the consequent radiological deposits. For a better understanding and prediction of the decommissioning works, we have focused on the accidental progression of the Unit 3 (BWR-4, Mark I) reactor of the Fukushima plant. In two large-scale experiments, we simulated the in-vessel core degradation, including the melting phase, and generated aerosols from the main components (UO₂-ZrO₂-Zr-Fe-B₄C system). We used cold crucible technology to melt the material reflecting the Unit 3 active zone composition, and we collected the deposited material from the surface of a hermetic steel compartment around the furnace. The aerosol deposits were analyzed using solid-state analysis (e.g., electron microscopy, crystal structure determination, and chemical composition). The majority of released material was composed of U₃O_8-y and UO_2+x that crystallized from the UO_z volatile species. This means that the fuel itself was the main volatile carrier. The reaction of B₄C powder with the in-vessel corium melt triggered the melt mixing and volatility of some compounds. Such data serves to predict the nature of deposits in the containment of Unit 3, facilitating the decommissioning efforts.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"192 ","pages":"Article 106180"},"PeriodicalIF":3.2,"publicationDate":"2025-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145681135","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":"Study on evolution of interface microstructure of SS304L/Zr-2.5 %Nb diffusion bonded joints processed using Ni and Ti interlayers","authors":"V. Srikanth ,&nbsp;Vishal Singh ,&nbsp;H. Donthula ,&nbsp;A. Laik ,&nbsp;R. Tewari","doi":"10.1016/j.pnucene.2025.106159","DOIUrl":"10.1016/j.pnucene.2025.106159","url":null,"abstract":"<div><div>Joining Zr-based alloys to stainless steels remains a technological challenge due to their chemical incompatibility. However, such joints are critically important for nuclear engineering applications. In this study, a solid-state diffusion bonding approach was developed to successfully join SS 304L and Zr-2.5 %Nb alloy using a composite interlayer of Ni and Ti. The bonding parameters were optimized by systematically varying the temperature and bonding duration from 1098 K to 1123 K and from 60 to 120 min, respectively. A maximum shear strength of 254 MPa was achieved at 1123 K for 60 min, attributed to enhanced coalescence and controlled intermetallic growth. However, extended durations or higher temperatures led to excessive growth of brittle intermetallic phases namely Ni₃Ti, NiTi, and NiTiZr resulting in reduced joint strength. Microstructural investigations revealed a diffusion-driven evolution of interfacial phases, with Ni diffusing more rapidly than Zr and forming Ni-rich intermetallics. Notably, NiTiZr evolved from a discontinuous phase into a well-defined intermetallic layer with increasing bonding time and temperature, emphasizing the role of diffusion kinetics in phase transformation and stability. Energy-dispersive spectroscopy (EDS) and X-ray diffraction (XRD) confirmed the interfacial phase composition and fracture characteristics, revealing Ni, Ni₃Ti, and NiTiZr on both fracture surfaces. Growth kinetics of intermetallic layers provided insights into optimizing bonding conditions to balance diffusion and intermetallic formation. This work highlights the importance of understanding the mechanism of microstructural evolution during bonding and presents a pathway to develop robust joints between chemically incompatible materials.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"192 ","pages":"Article 106159"},"PeriodicalIF":3.2,"publicationDate":"2025-12-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145681131","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}