Annals of Nuclear Energy最新文献

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Decoupling control for pressurizer pressure and water level in nuclear power plants based on a Proportional–Integral–Derivative Neural Network 基于比例-积分-导数神经网络的核电站稳压器压力与水位解耦控制
IF 1.9 3区 工程技术
Annals of Nuclear Energy Pub Date : 2025-07-04 DOI: 10.1016/j.anucene.2025.111687
Guofeng Fan, Shengyu Shen, Chunhui Dai
{"title":"Decoupling control for pressurizer pressure and water level in nuclear power plants based on a Proportional–Integral–Derivative Neural Network","authors":"Guofeng Fan,&nbsp;Shengyu Shen,&nbsp;Chunhui Dai","doi":"10.1016/j.anucene.2025.111687","DOIUrl":"10.1016/j.anucene.2025.111687","url":null,"abstract":"<div><div>The pressurizer plays a crucial role in nuclear power plants, ensuring reactor safety by maintaining stable pressure and water levels. It is characterized by nonlinearity, time-varying dynamics, and strong coupling. Conventional single-loop PID control systems often fail to decouple pressure and water level effectively, resulting in suboptimal performance, particularly under large load variations. To address these challenges, this study presents a novel decoupling control system based on a Proportional–Integral–Derivative Neural Network (PIDNN). The PIDNN is employed to mitigate the intense coupling effects between control loops. Furthermore, the Dung Beetle Optimizer (DBO) algorithm is integrated to optimize the initial weights of the PIDNN. A three-region pressurizer model is developed in MATLAB/Simulink for validation. The simulation results demonstrate that the proposed method significantly enhances the control performance and dynamic response speed of the pressurizer’s pressure and water level under typical load rejection transients in nuclear power plants, compared to traditional PID control. This method also exhibits advantages in robustness, adaptability, and engineering applicability, offering an innovative and effective solution for the decoupling control of pressurizers in nuclear power plants.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111687"},"PeriodicalIF":1.9,"publicationDate":"2025-07-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144557042","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}
引用次数: 0
Study on the mechanism of temperature fluctuation induced by coaxial jets in nuclear power systems 核电系统中同轴射流引起的温度波动机理研究
IF 1.9 3区 工程技术
Annals of Nuclear Energy Pub Date : 2025-07-03 DOI: 10.1016/j.anucene.2025.111669
Guo-Yan Zhou , Ling-Hao Liu , Xue-Yao Xiong , Xing Luo , Shan-Tung Tu
{"title":"Study on the mechanism of temperature fluctuation induced by coaxial jets in nuclear power systems","authors":"Guo-Yan Zhou ,&nbsp;Ling-Hao Liu ,&nbsp;Xue-Yao Xiong ,&nbsp;Xing Luo ,&nbsp;Shan-Tung Tu","doi":"10.1016/j.anucene.2025.111669","DOIUrl":"10.1016/j.anucene.2025.111669","url":null,"abstract":"<div><div>The mixing of fluid with different temperatures in the upper plenum results in temperature fluctuations, which can propagate to adjacent structures, potentially inducing fatigue damage. Current research primarily focuses on the temperature fluctuation characteristics of fluids and the mechanism of temperature fluctuation is still unclear. In this study, the mixing process of fluids in the upper plenum is modeled as a coaxial jet by using large eddy simulation (LES). The simulation model and method are experimentally validated. Then the distribution characteristics of the time-averaged velocity, pressure, temperature and RMS temperature at different directions and different heights are numerically obtained, respectively. By analyzing the transient temperature field, the formation mechanism of temperature fluctuation is clarified, that is, the oscillation of the central position of the cold fluid, the expansion and contraction of its control region and the changes in the shape of the region lead to the instability of the flow field.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111669"},"PeriodicalIF":1.9,"publicationDate":"2025-07-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144535867","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}
引用次数: 0
Research on flow and heat transfer characteristics of built-in cooling system in shaft sealed reactor coolant pump 轴封式反应堆冷却剂泵内置冷却系统的流动与传热特性研究
IF 1.9 3区 工程技术
Annals of Nuclear Energy Pub Date : 2025-07-03 DOI: 10.1016/j.anucene.2025.111698
Kun Tang , Yizhu Yang , Bin Yin , Xiyuan Cao , Wei Fu , Liang Zhao , Hui Dong
{"title":"Research on flow and heat transfer characteristics of built-in cooling system in shaft sealed reactor coolant pump","authors":"Kun Tang ,&nbsp;Yizhu Yang ,&nbsp;Bin Yin ,&nbsp;Xiyuan Cao ,&nbsp;Wei Fu ,&nbsp;Liang Zhao ,&nbsp;Hui Dong","doi":"10.1016/j.anucene.2025.111698","DOIUrl":"10.1016/j.anucene.2025.111698","url":null,"abstract":"<div><div>The built-in cooling system (BCS) constitutes a critical component of reactor coolant pump (RCP), whose structure is fundamentally determined by the nuclear reactor. Four-bearing mechanical-seal centrifugal pump is widely used in RCP. Operating parameters significantly influence the flow and heat transfer mechanisms in BCS, thereby affecting the service life and operational stability of RCP. Current research on the flow and heat transfer characteristics of BCS lacks comprehensive numerical simulations, which results in insufficient understanding of RCP fundamental operational mechanisms. Therefore, it is necessary to analyze the flow and heat transfer characteristics of BCS. A numerical simulation model established to simulate accurately the multi-passage large-span variable cross-section geometric structural characteristics of BCS in a certain RCP. An experimental platform is constructed for verification, and the flow and heat transfer patterns in BCS under standard operating conditions are obtained. Consequently, the influences of operational parameters on resistance and internal flow distribution are investigated.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111698"},"PeriodicalIF":1.9,"publicationDate":"2025-07-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144535866","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}
引用次数: 0
Accuracy analysis of different numerical methods on thermal stratification prediction of liquid metal 不同数值方法对液态金属热分层预测的精度分析
IF 1.9 3区 工程技术
Annals of Nuclear Energy Pub Date : 2025-07-03 DOI: 10.1016/j.anucene.2025.111690
Shuai Zhang , Yunqing Bai , Wenbo Li , Ming Jin , Tinyu Li , Mei Huang , Qiaoyan Chen , Fenglei Niu
{"title":"Accuracy analysis of different numerical methods on thermal stratification prediction of liquid metal","authors":"Shuai Zhang ,&nbsp;Yunqing Bai ,&nbsp;Wenbo Li ,&nbsp;Ming Jin ,&nbsp;Tinyu Li ,&nbsp;Mei Huang ,&nbsp;Qiaoyan Chen ,&nbsp;Fenglei Niu","doi":"10.1016/j.anucene.2025.111690","DOIUrl":"10.1016/j.anucene.2025.111690","url":null,"abstract":"<div><div>The study of thermal stratification is of significant importance for the safety analysis of pool-type sodium fast reactors, and numerical simulation is an essential tool for investigating thermal stratification phenomena. This work evaluates the effectiveness of a couple of CFD solvers in predicting thermal stratification. It compares the impact of different discretization schemes on solution accuracy and analyzes the reasons for observed discrepancies. Several discretization schemes effectively capture thermal stratification, with the high-resolution scheme showing an average error of 4.2 % and a maximum temperature error of 7.7 K, while the second-order upwind scheme shows an average error of 2.59 % and a maximum temperature error of 6.9 K. Additionally, this study investigates the impact of different order difference schemes on the simulation results of thermal stratification. For conditions where the Richardson number (<em>Ri</em>) is greater than 0.82, the simulation results of the first-order upwind scheme are similar to those of the second-order upwind scheme.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111690"},"PeriodicalIF":1.9,"publicationDate":"2025-07-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144548690","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}
引用次数: 0
Study on flow characteristics and formation mechanism of air-water periodic flooding in two 3 × 3 rod bundle channels 2个3 × 3杆束通道气-水周期性驱流特性及形成机理研究
IF 1.9 3区 工程技术
Annals of Nuclear Energy Pub Date : 2025-07-03 DOI: 10.1016/j.anucene.2025.111706
Guangyuan Jin , Weilian Li , Jinghu Bai , Rui Wang
{"title":"Study on flow characteristics and formation mechanism of air-water periodic flooding in two 3 × 3 rod bundle channels","authors":"Guangyuan Jin ,&nbsp;Weilian Li ,&nbsp;Jinghu Bai ,&nbsp;Rui Wang","doi":"10.1016/j.anucene.2025.111706","DOIUrl":"10.1016/j.anucene.2025.111706","url":null,"abstract":"<div><div>The research on the characteristics and mechanisms of periodic flooding are important for the emergency treatment of nuclear power plants. Experimental investigations were carried out on the flooding phenomenon, the duration of various flooding regions, force analysis, and flow instability in two rod bundle channels. The flooding region can be divided into the onset flooding region and the completed flooding region. The average duration of flooding regions in Channel 1 is greater than that in Channel 2, so the channel with a smaller diameter provided larger waves, longer existence times, and expanded flooding conditions. Four forces acting on the liquid film are combined in different flooding regions to explain the formation mechanism of periodic flooding. The Kelvin–Helmholtz and Rayleigh-Taylor instabilities observed in the flooding and deflooding regions are shown to analyze the influence of interfacial instability on periodic flooding in different rod bundle channels.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111706"},"PeriodicalIF":1.9,"publicationDate":"2025-07-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144548689","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}
引用次数: 0
High-precision eigenvalues of the neutron transport equation by the Carlvik method 用Carlvik方法计算中子输运方程的高精度特征值
IF 1.9 3区 工程技术
Annals of Nuclear Energy Pub Date : 2025-07-02 DOI: 10.1016/j.anucene.2025.111672
Paolo Saracco , Nicolò Abrate , Sandra Dulla , Piero Ravetto
{"title":"High-precision eigenvalues of the neutron transport equation by the Carlvik method","authors":"Paolo Saracco ,&nbsp;Nicolò Abrate ,&nbsp;Sandra Dulla ,&nbsp;Piero Ravetto","doi":"10.1016/j.anucene.2025.111672","DOIUrl":"10.1016/j.anucene.2025.111672","url":null,"abstract":"<div><div>High-precision results for solutions of neutron transport problems are important as a guidance to code developers and to understand the impact of physical and numerical approximations. The aim of this work is the determination of the eigenvalues of the transport equation in plane geometry, reaching results as accurate as one may desire, with practically no limitation in the number of exact digits required. The method proposed by Carlvik is re-visited and implemented through appropriate analytical manipulations within the <span>Mathematica</span>™ framework, exploiting some specific features of this software to keep a full control of the numerical precision throughout the whole calculation procedure. The Wynn-<span><math><mi>ɛ</mi></math></span> acceleration scheme is also used to improve the convergence trend. Some selected high-precision results are presented to illustrate the performance of the algorithm.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111672"},"PeriodicalIF":1.9,"publicationDate":"2025-07-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144535865","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}
引用次数: 0
Introducing the SLICE Method for estimating pebble-bed reactor inventories at equilibrium operation with SCALE 介绍了用SCALE估计球床反应器平衡运行库存的SLICE方法
IF 1.9 3区 工程技术
Annals of Nuclear Energy Pub Date : 2025-07-02 DOI: 10.1016/j.anucene.2025.111684
Friederike Bostelmann, Steven E. Skutnik, William A. Wieselquist
{"title":"Introducing the SLICE Method for estimating pebble-bed reactor inventories at equilibrium operation with SCALE","authors":"Friederike Bostelmann,&nbsp;Steven E. Skutnik,&nbsp;William A. Wieselquist","doi":"10.1016/j.anucene.2025.111684","DOIUrl":"10.1016/j.anucene.2025.111684","url":null,"abstract":"<div><div>This paper introduces the SCALE Leap-In method for Cores at Equilibrium (SLICE) for estimating pebble-bed reactor equilibrium core isotopic inventories using capabilities in the SCALE code system, requiring only a small computational cluster and a few days of computation. This method uses an iterative approach that relies on (1) a surrogate spectrum model that captures spatial and time-dependent spectral conditions, (2) a multi-pass model that captures the pebble’s evolving nuclide inventory as a function of location and time in the core, and (3) a full-core model that captures the core’s spatial neutron flux distribution.</div><div>The SLICE approach is applied to a generic fluoride salt–cooled high-temperature reactor, demonstrating fuel inventory convergence through nuclide concentration inspection across iterations and comparisons for core realizations with varying discretizations. Results agree within <span><math><mo>∼</mo></math></span>5% with another state-of-the-art code, with differences attributed to input parameter or modeling assumption variations in the equilibrium generation methods.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111684"},"PeriodicalIF":1.9,"publicationDate":"2025-07-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144523822","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}
引用次数: 0
Performance evaluation of a surrogate model to predict effective dose under hypothesized severe accidents of pressurized water reactor based on neural network 基于神经网络的压水堆严重事故有效剂量预测代理模型性能评价
IF 1.9 3区 工程技术
Annals of Nuclear Energy Pub Date : 2025-07-01 DOI: 10.1016/j.anucene.2025.111701
Chang Hyun Song , Wonjun Choi , Sung Joong Kim
{"title":"Performance evaluation of a surrogate model to predict effective dose under hypothesized severe accidents of pressurized water reactor based on neural network","authors":"Chang Hyun Song ,&nbsp;Wonjun Choi ,&nbsp;Sung Joong Kim","doi":"10.1016/j.anucene.2025.111701","DOIUrl":"10.1016/j.anucene.2025.111701","url":null,"abstract":"<div><div>Numerous studies utilizing severe accident analysis codes have been conducted to evaluate the effectiveness of various mitigation strategy combinations. However, due to various sensitivity factors such as the execution time and characteristics of system performance, an exhaustive analysis of all scenarios is infeasible. Interestingly, recent studies have shown that application of the machine learning technique is beneficial for reducing the calculation cost and this study developed a deep neural network-based surrogate model to assess the effectiveness of a severe accident management strategy. The effectiveness of the strategy was evaluated based on the effective dose over a 72 hrs, which is an ultimate standard for measuring the ability to mitigate a severe accident. Additionally, the model’s performance was further improved by incorporating input parameters that can capture the progression of accident, such as the timing of major events and accident classification based on event branches using a source term grouping method.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111701"},"PeriodicalIF":1.9,"publicationDate":"2025-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144523821","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}
引用次数: 0
Butterfly valve performance factors using the multiphysics object oriented simulation environment 蝶阀性能因素采用面向多物理场对象的仿真环境
IF 1.9 3区 工程技术
Annals of Nuclear Energy Pub Date : 2025-07-01 DOI: 10.1016/j.anucene.2025.111671
Daniel Yankura, Matthew Anderson
{"title":"Butterfly valve performance factors using the multiphysics object oriented simulation environment","authors":"Daniel Yankura,&nbsp;Matthew Anderson","doi":"10.1016/j.anucene.2025.111671","DOIUrl":"10.1016/j.anucene.2025.111671","url":null,"abstract":"<div><div>Butterfly valves are typically used in nuclear reactors to control incompressible fluid flow with high inlet velocities. Performance factors for butterfly valves include the pressure drop across the valve and the loss coefficient from which hydrodynamic torque and flow coefficients can be computed. This work explores a computational fluid dynamics approach for butterfly valve performance factors using the open-source Multiphysics Object Oriented Simulation Environment (MOOSE) framework. While MOOSE is often used in the nuclear energy modeling and simulation community for simulations ranging from fuel characterization to heat pipe simulation, this work employs the MOOSE open-source Navier–Stokes solver capability for simulating butterfly valve performance factors and compares those to experimentally measured results from the Advanced Test Reactor at Idaho National Laboratory at Reynolds numbers in the order of <span><math><mrow><mn>1</mn><msup><mrow><mn>0</mn></mrow><mrow><mn>6</mn></mrow></msup></mrow></math></span> for the partially opened configuration. The MOOSE framework results are compared against experimentally measured butterfly valve performance factors across five valve opening angles using meshes with order <span><math><mrow><mn>1</mn><msup><mrow><mn>0</mn></mrow><mrow><mn>4</mn></mrow></msup></mrow></math></span> – <span><math><mrow><mn>1</mn><msup><mrow><mn>0</mn></mrow><mrow><mn>5</mn></mrow></msup></mrow></math></span> elements. This validation serves to enable MOOSE-based multiphysics simulations incorporating the open-source Navier–Stokes module.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111671"},"PeriodicalIF":1.9,"publicationDate":"2025-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144523889","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}
引用次数: 0
Emergency evacuation model of nuclear power plant pedestrians considering emotional infection 考虑情绪感染的核电站行人应急疏散模型
IF 1.9 3区 工程技术
Annals of Nuclear Energy Pub Date : 2025-06-30 DOI: 10.1016/j.anucene.2025.111683
Yujie Sun , Tao Wu , Honglai Ren , Ben Ding , Xiang Chai
{"title":"Emergency evacuation model of nuclear power plant pedestrians considering emotional infection","authors":"Yujie Sun ,&nbsp;Tao Wu ,&nbsp;Honglai Ren ,&nbsp;Ben Ding ,&nbsp;Xiang Chai","doi":"10.1016/j.anucene.2025.111683","DOIUrl":"10.1016/j.anucene.2025.111683","url":null,"abstract":"<div><div>To examine how panic affects the efficiency of pedestrians evacuation during nuclear power plant emergencies, the emotional infection model, based on the heat dissipation principle, is combined with the social force model. This integration simulates the spread of panic among evacuees in these critical situations. First, the intensity of emotional infection among evacuees is defined based on the social force model. An emergency evacuation model is then developed, incorporating dynamic emotion-driven by quantifying panic levels and including device factors. Additionally, the OCEAN personality model is applied to establish the rules governing emotional infection and to guide the simulation of crowd evacuation. Then, simulation environments for both unit spaces and nuclear power plants are created to analyze how factors including pedestrians density, emotional infection intensity, device factor influence, and the number of exit points affect evacuation efficiency. The results show that the dynamic emotion-driven evacuation model of nuclear power plant pedestrians aligns well with individual movement behaviors during evacuations. In the fixed space scenario, when pedestrians density reaches 0.7/m<sup>2</sup>, the slope of evacuation time is significantly steeper. In low-density scenarios, emotional infection can enhance evacuation efficiency. Conversely, in medium to high-density situations, once emotional infection intensity surpasses a certain threshold, it negatively impacts evacuation efficiency. Notably, device factors can mitigate emotional infection intensity and improve evacuation outcomes in these denser scenarios. In the emergency evacuation scenario of nuclear power plant, the dynamic emotion-driven model outperforms the traditional social force model, resulting in evacuation efficiency.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111683"},"PeriodicalIF":1.9,"publicationDate":"2025-06-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144523820","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}
引用次数: 0
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