Progress in Nuclear Energy最新文献

{"title":"Effect of tip injection on performance of high-load helium compressor cascade in high temperature gas-cooled reactor","authors":"Zhitao Tian ,&nbsp;Xinle Wang ,&nbsp;Yuyang Chen ,&nbsp;Hai Zhang ,&nbsp;Huawei Lu","doi":"10.1016/j.pnucene.2024.105595","DOIUrl":"10.1016/j.pnucene.2024.105595","url":null,"abstract":"<div><div>The helium compressor's high-load design approach causes more significant tip-leakage and secondary flow in the passage. Tip injection can effectively restrain the growth of leakage vortex and improve the diffuser capacity of the cascade. In this paper, numerical simulation and wind tunnel experiment are employed to investigate the impact of tip injection on cascade aerodynamic performance in two aspects: axial deflection angles and pitch angles. Under the optimal combination of the injection angle, the effect of tip injection on the cascade performance at different relative positions of guide-rotor blades is investigated. The numerical results demonstrate that an appropriate axial deflection angle enables the leakage vortex with the high-energy fluid to fade on the pressure surface of the adjacent blade, thereby weakening its impact on the downstream flow field. A suitable pitch angle diminishes the strength of the passage vortex formed at the guide vane's trailing edge, which minimizes its mixing with the tip leakage vortex and leakage flow. The injected high-energy flow facilitates the dissipation of the vortex system. The experimental results indicate that tip injection has positive effects on different relative positions of guide-rotor blades, and Case-4 has the most significant improvement effect, with a loss rate of 8.22%.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105595"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141594","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Design and optimization of a 500 kW multi-cylinder double-acting free piston stirling engine for deep-sea nuclear power system","authors":"Siyi Guo,&nbsp;Yongqi Lan,&nbsp;Gen Li","doi":"10.1016/j.pnucene.2024.105588","DOIUrl":"10.1016/j.pnucene.2024.105588","url":null,"abstract":"<div><div>Given the increasing demand for deep-sea exploration, nuclear power system is attracting great interest for electricity supply due to its long-time operation with one refuelling. Double-acting free piston Stirling engine (DAFPSE) is a promising energy conversion system for nuclear power considering its long operation life, low vibration and little maintenance. However, the research on the DAFPSE design and optimization for deep-sea nuclear power system is scarce, which requires high volumetric power density. In this study, a practical isothermal model for designing multi-cylinder DAFPSE was established with the validation against the experiment. Also, the influences of structure parameters, operating parameters and heat exchanger parameters on the DAFPSE performance were investigated. The results indicated that the maximum deviation between the calculation and the experimental result was 8.75%. The compression ratio had significant influence on power density but less influence on efficiency. Specifically, the power density increased by 109.8% and the efficiency decreased by 11.7% respectively when the compression ratio changed from 1.5 to 2. As the engine frequency increased, power density first increased and then decreased, and the maximum power density of 10.71 MW‧m⁻³ was obtained at the frequency of 21 Hz. With the increase of regenerator porosity, the engine efficiency and power density had similar change trends, which showed that the maximum efficiency of 36.6% and the maximum power density of 10.35 MW‧m⁻³ were achieved at the regenerator porosity of 0.8 and 0.9, respectively. The engine efficiency and power density had linear variations with both the hot end temperature and the inlet temperature of cooling water. After the sensitivity investigation of the design parameters, multi-objective optimizations were performed for the structures with different cylinders. The four-cylinder DAFPSE obtained better overall engine performance, in which the optimal scheme was determined from the Pareto optimal frontier with output power of 500.64 kW, power density of 14.00 MW‧m⁻³ and efficiency of 38.02%.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105588"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141804","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":"Reinforcement learning: Application to PWR's core power level control","authors":"Hamza Boubacar Kirgni","doi":"10.1016/j.pnucene.2025.105644","DOIUrl":"10.1016/j.pnucene.2025.105644","url":null,"abstract":"<div><div>This paper presents the design and implementation of an adaptive dynamic programming (ADP) based controller for pressurized water reactors (PWRs) with unknown dynamic. The control design process begins with the transformation of the reactor's unknown nonlinear dynamic into a normal form. Subsequently, an ADP-based control technique, a class of reinforcement learning, is applied to this model. An algorithm is established to determine the controller's gain. The stability of the system is thoroughly analyzed, and it is demonstrated that the resulting controller exhibits L2 performance. The efficacy of the designed controller is evaluated through numerical simulations and compared with proportional-integral-derivative (PID) and linear quadratic gaussian (LQG) controllers. The results emphasize the potential of the ADP-based controller in managing complex systems such as PWRs with unknown dynamics.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105644"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141806","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":"Numerical & experimental study of single-phase flow in helically coiled pipes for laminar & turbulent regimes","authors":"Alok Prakash,&nbsp;D.K. Chandraker","doi":"10.1016/j.pnucene.2025.105637","DOIUrl":"10.1016/j.pnucene.2025.105637","url":null,"abstract":"<div><div>The primary objective of this study is to conduct a numerical analysis of the single-phase friction factor in curved tubes, specifically concerning helical coil once-through steam generators designed for small modular reactors (SMRs). Numerical simulations were performed over a broad range of Reynolds numbers to encompass laminar and turbulent flow regimes.</div><div>As reported in the literature, helical configurations influence flow behaviour in contrast to straight tubes due to the introduction of centrifugal forces within the flow field. Hence, the impact of centrifugal forces on flow structure and the resultant pressure drop during laminar flow in helical coils with circular cross-section tubes has been systematically analysed for a wide range of coil pitch circle diameter (PCD) and helical pitch. This investigation examines the pressure drop across a helical coil through numerical simulations across an extensive range of Reynolds numbers. The numerical study is validated against the experimentally measured pressure drop over a wide range of Reynolds numbers. The friction factor derived from the numerical simulations is compared with predictions from various empirical correlations documented in the literature. A new empirical correlation for the estimation of single-phase flow through helical coils is proposed for the laminar regime, taking into account the effect of coil curvature as well as the pitch of the helix.</div><div>For the turbulent regime, three distinct turbulence models—k-ε, RNG k-ε, and Realizable k-ε—were evaluated, and their effectiveness in predicting pressure drop in helical coils was compared.</div><div>The findings indicate that centrifugal forces markedly affect the velocity profile across the cross-section of helical tubes. Similar observations were reported earlier by the author [36] for square cross-section helical paths with very tight curvature with d/D = 1/3. Here, the studies are carried out for d/D ranging from 1/12 to 1/70. Various combinations of pitch and coil PCD were studied during numerical analysis. The experimental studies were carried out for three different helical coil PCDs (150 mm, 339 mm &amp; 877 mm) and two different pitch values (105 mm &amp; 245 mm). Helical tubes exhibit a velocity maximum that shifts toward the extrados of the tube cross-section. This shift increases with the Reynolds number for a given coil diameter. An increase in velocity shift towards the extrados of the tube cross-section with an increase in Reynolds number is found to be significant for the ratio d/D considered in the study (1/12 to 1/70). In the case of turbulent flow, all three turbulence models—k-ε, RNG k-ε, and Realizable k-ε—employing standard wall functions yielded results that closely align with empirical correlations proposed by Ito and Mishra &amp; Gupta, provided that the Y+ value is maintained above 11.25.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105637"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141000","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":"Numerical simulation study of liquid sodium contact angle on gradient sodium-philic nanostructure surface based on Lattice Boltzmann method for heat pipe rector application","authors":"Simiao Tang ,&nbsp;Zaiyong Ma ,&nbsp;Yu Liang ,&nbsp;Lin Zou ,&nbsp;Xiao Liu ,&nbsp;Ran Zhang ,&nbsp;Can Wang","doi":"10.1016/j.pnucene.2024.105581","DOIUrl":"10.1016/j.pnucene.2024.105581","url":null,"abstract":"<div><div>As an efficient heat transfer element, high-temperature heat pipes have broad application prospects in various fields such as nuclear energy and aerospace. The heat transfer characteristics of high-temperature heat pipe mainly depend on the capillary effect of the wick. The main factors determining the capillary force of the wick are the contact angle of alkali-metal and the effective capillary radius of the wick. It is crucial to explore the utilization of nanostructures to reduce the apparent contact angle and enhance the wetting characteristics. In this paper, the modified Lattice Boltzmann Method (LBM) is developed to simulate the contact angle of liquid sodium on gradient nanostructure surfaces. To simulate high-density ratio conditions and ensure program stability when incorporating gradient nanostructures, the multi-relaxation model, Li-MRT model, and the surface tension adjustment model have been developed. The simulation accuracy of the code is verified and validated through comparisons with Laplace's law and smooth wall contact angles. The wetting and spreading processes of liquid sodium on microcolumn nanostructure surfaces are simulated. By changing the height, spacing, and width of the microcolumns to form gradient nanostructures, the influence of geometric parameters of the nanostructure on the contact angle of liquid sodium is studied. The results show that when the microcolumn height is between 2 and 6 lu, the static contact angle of liquid sodium gradually decreases with the increase in height. When the height exceeds 6 lu, the impact of the microcolumn height on the contact angle becomes minimal. When the spacing and width are increased, the contact angle gradually increases. On gradient surfaces, the spacing has a greater impact than the width. The droplet spontaneously moves towards the side with smaller spacing, and the spreading speed is faster on the side with smaller spacing. This work has important guiding significance for improving the heat transfer performance of heat pipes through the nanostructured wick design.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105581"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141583","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":"Research on multi-objective optimization design of the nuclear island cold chain system in HPR1000 based on a new hybrid genetic algorithm","authors":"Weiguang Zhao ,&nbsp;Pei Yu ,&nbsp;Xiaobo Zeng ,&nbsp;Guangming Fan ,&nbsp;Zhaoming Meng ,&nbsp;Changqi Yan","doi":"10.1016/j.pnucene.2025.105613","DOIUrl":"10.1016/j.pnucene.2025.105613","url":null,"abstract":"<div><div>Currently, the design of the cold chain system for the HPR1000 nuclear island does not take a unified approach and largely relies on the design experience of the respective designers. The various subsystems contain numerous devices, and the cumulative design margins often result in many unreasonable parameters in the original design scheme of the cold chain system. To address this issue, this paper establishes a mathematical model for the cold chain system to assist in its design. Based on genetic algorithms and the simplex algorithm, adaptive relaxation constraint dominance relations and two improved NSGA-II multi-objective handling methods are introduced, leading to the development of a new hybrid multi-objective genetic algorithm. The performance of this algorithm is verified using optimized benchmark testing functions, thus allowing for the scientific optimization of the cold chain system design scheme. A sensitivity analysis is conducted on the design parameters of the ventilation system, refrigeration system, component cooling system, and seawater system within the cold chain system to explore the impact of these parameters on performance indicators. Optimization design calculations for the cold chain system are performed under safe and feasible conditions, resulting in an optimization scheme. The results indicate that the developed algorithm is effective in addressing the complex optimization problems of the cold chain system, and the optimized cold chain system can reduce weight by up to 18.4 %, volume by up to 18.6 %, investment costs by up to 5.7%, and system energy consumption by up to 7.5 %.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105613"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141781","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 <1–2> passes printed circuit heat exchanger with lead-bismuth and supercritical carbon dioxide as working fluids","authors":"Jia-tao Meng ,&nbsp;Shuang-qing Chen ,&nbsp;Yong-gang Cao ,&nbsp;Ji-yue Liang ,&nbsp;Sheng-hui Liu ,&nbsp;Peng-rui Qiao ,&nbsp;Xiao-liang Zhu","doi":"10.1016/j.pnucene.2025.105612","DOIUrl":"10.1016/j.pnucene.2025.105612","url":null,"abstract":"<div><div>Printed Circuit Heat Exchanger (PCHE) has emerged as a promising choice for heat exchangers in lead-bismuth cooled fast reactors coupled with supercritical carbon dioxide Brayton cycle, due to its high compactness, high power density, and capability to operate under high temperature and pressure conditions. This study establishes a model for the &lt;1–2&gt; passes PCHEs utilizing lead-bismuth and supercritical carbon dioxide as working fluids, and includes the development and verification of the associated design calculation tool. The influence of lateral heat conduction on thermal-hydraulic simulation outcomes was examined, demonstrating a considerable impact on local temperature distributions but a minimal effect on overall thermal-hydraulic parameters. A comparative analysis was conducted between the &lt;1–2&gt; passes arrangements and conventional cross-flow arrangements in terms of pressure drop and power density, to identify the advantages and disadvantages inherent to different arrangements. The ε-NTU characteristic curve for the &lt;1–2&gt; passes PCHEs was proposed, and a modified ε-NTU relationship was fitted based on the Drake correlation. The optimization process was conducted with power density and inlet-outlet pressure drop as the objectives, employing the Non-dominated Sorting Genetic Algorithm II. A Pareto front analysis was employed for the optimization of the heat exchanger, demonstrating that a smaller diameter of the hot-side channels yields superior performance improvements within the permissible range. Finally, the design limitations were discussed, and the selection of hot-side and cold-side channels diameters, as well as the number of layers, was analyzed.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105612"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141785","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":"An improved extended CREAM model using a 2-tuple linguistic and DANP in nuclear power plants","authors":"Shengyuan Yan,&nbsp;Xiaodan Zhang,&nbsp;Xin Liu","doi":"10.1016/j.pnucene.2025.105627","DOIUrl":"10.1016/j.pnucene.2025.105627","url":null,"abstract":"<div><div>Human reliability analysis (HRA) is critical to avoid safety accidents in the advanced rooms of nuclear power plants. The cognitive reliability and error analysis method (CREAM) is a widely used approach to human reliability analysis. The extended CREAM considers the contexts and uses the common performance conditions (CPCs) to adjust nominal human error probabilities (HEPs). However, the extended CREAM lacks a systematic method for analyzing tasks, evaluates CPC information ambiguously, and there is a certain correlation between CPC factors. This paper's improved extended CREAM model quantitates analyzing human errors in the advanced rooms. Firstly, the improved extended CREAM combines the goals, operations, methods, and selection rules (GOMS) with the extended CREAM to systematically analyze the tasks to get the CPC status in the advanced rooms. Secondly, the improved extended CREAM takes the 2-tuple linguistic to evaluate the tasks and the relationship of CPCs. The approach analyzes the dependencies among the CPCs by the decision-making trial and evaluation laboratory (DEMATEL) gets the relative weights by the analytic network process (ANP), and gets the modified situation specific weights of the CPCs. Finally, we calculate the HEPs according to the modified situation specific weights of the CPCs. The hot shutdown case verifies that the improved extended CREAM model is correct and sensitive.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105627"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143140941","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 social factors considered in site selection for nuclear power plants: A case study of Borneo Island, Indonesia","authors":"Ade Gafar Abdullah ,&nbsp;Novalda Salsabila Khairunnisa ,&nbsp;Mohammad Ali Shafii ,&nbsp;Rida SN. Mahmudah ,&nbsp;Dadang Lukman Hakim ,&nbsp;Topan Setiadipura","doi":"10.1016/j.pnucene.2025.105626","DOIUrl":"10.1016/j.pnucene.2025.105626","url":null,"abstract":"<div><div>Many countries choose Nuclear Power Plants (NPPs) as their baseload energy source because they can operate continuously, unaffected by weather fluctuations or other environmental factors. However, NPPs have significant safety risks, primarily related to the potential for radioactive leaks that can threaten human life and the environment. The location of the NPPs is crucial because it can affect the safety and lives of the surrounding population if an incident occurs. This study investigated the integration of the analytical hierarchy process (AHP) and elimination and choice translating reality (ELECTRE) in the decision-making process concerning the location of NPPs, emphasizing social aspects. Ten nuclear experts from Indonesia participated in a focus group discussion (FGD) to justify and validate the selection of seven criteria based on social factors most important by researchers who have published work in international journals. The AHP method concluded that safety was the most crucial criterion, followed by the transportation network and legal considerations. While, for NPPs’ development, the ELECTRE method is recommended by the West Kalimantan province over East Kalimantan. This study introduces a comprehensive framework for multi-criteria decision-making (MCDM) methods that supports consistency analysis and effectively handles uncertainty. This framework can serve as a relevant reference for engineering consultants in addressing MCDM problems. By incorporating social aspects, this study contributes to identifying the optimal location for NPPs in Indonesia.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105626"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143140997","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":"On the conception of pseudo-cross sections for neutron escape in physical Monte Carlo simulations in finite domains","authors":"D.G. Benvenutti,&nbsp;B.E.J. Bodmann","doi":"10.1016/j.pnucene.2024.105574","DOIUrl":"10.1016/j.pnucene.2024.105574","url":null,"abstract":"<div><div>The physical approach of the Monte Carlo method in neutron transport enables, mainly due to its versatility, the construction of pseudo-cross sections for neutron escape and thus allows for quantifying escape pseudo-interactions in finite domains, such as in nuclear reactors. An intrinsic characteristic of these pseudo-cross sections is that they tend towards infinity at the surfaces of the studied domain and can, theoretically, simulate a surface by initially considering an infinite domain, simplifying and facilitating the treatment of neutron transport problems. In this work, this geometric characteristic is validated for stochastic approaches. For this purpose, the pseudo-cross section for neutron escape for a specific configuration, similar to the configurations of the early criticality studies in spherical medium, was obtained from a Monte Carlo simulation. Subsequently, a similar simulation was performed, however, considering an infinite domain and using only the pseudo-cross section to handle the boundaries of the spherical medium. Comparing results, i.e. the neutron spectral flux and the effective multiplication factor, a good agreement was observed between the usual approach, in which a boundary is defined in the simulation, and the proposed approach, in which an infinite domain is considered and only the escape cross section is used to treat the boundaries of the medium. The good results pave the way for similar studies considering more complex geometries and their feedback to deterministic approaches.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105574"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141589","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}