International Journal of Advanced Nuclear Reactor Design and Technology最新文献

Vibration response simulation of centrifuge excited by liquid medium based on SPH-FEM 基于SPH-FEM的液体介质激励下离心机振动响应仿真

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-06-18 DOI: 10.1016/j.jandt.2025.06.006

Kan Chen , Lu Chaoran , Guo Mingchao

引用次数: 0

Research on temperature composite control system for radioactive waste incineration equipment 放射性废物焚烧设备温度复合控制系统的研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-06-06 DOI: 10.1016/j.jandt.2025.06.004

Zhiyong Wang , Yao Cui , Jing Ma , Bo Zhang , Liudong Hou , Haili Li

{"title":"Research on temperature composite control system for radioactive waste incineration equipment","authors":"Zhiyong Wang , Yao Cui , Jing Ma , Bo Zhang , Liudong Hou , Haili Li","doi":"10.1016/j.jandt.2025.06.004","DOIUrl":"10.1016/j.jandt.2025.06.004","url":null,"abstract":"<div><div>This paper presents a multi-mode control scheme for the temperature regulation of radioactive waste incineration equipment, integrating modern and fuzzy control theories. Separate controllers were designed for the preheating and operating stages. In preheating phase, a mathematical model was developed using mechanism modeling, enabling automatic control through sequential and proportional-integral-derivative control. For operation phase, a composite control approach combining fuzzy control and special variable ratio control was proposed. The fuzzy controller used temperature difference, changing rate and acceleration as inputs, adjusting oxygen concentration to regulate combustion temperature. Experimental results demonstrated 27 h of stable automatic control with a maximum temperature deviation of 9.1 °C and an error rate of 1.65 %. The proposed scheme provides specific control strategies with quantifiable performance indicators, proving its effectiveness in maintaining temperature stability in radioactive waste incineration.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 3","pages":"Pages 209-216"},"PeriodicalIF":0.0,"publicationDate":"2025-06-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144480525","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","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 direct measurement method for trace plutonium in samples from spent fuel reprocessing 乏燃料后处理样品中痕量钚的直接测定方法研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-06-04 DOI: 10.1016/j.jandt.2025.06.001

Li Li , Han Yang , Yingtong Fang , Xianlong Chang , Yuning Niu , Guodu Jiang , Songtao Yang , Zhiheng Wang , Zhaoqing Zhang , Yurong Li , Quanwei Liu

{"title":"Study on the direct measurement method for trace plutonium in samples from spent fuel reprocessing","authors":"Li Li , Han Yang , Yingtong Fang , Xianlong Chang , Yuning Niu , Guodu Jiang , Songtao Yang , Zhiheng Wang , Zhaoqing Zhang , Yurong Li , Quanwei Liu","doi":"10.1016/j.jandt.2025.06.001","DOIUrl":"10.1016/j.jandt.2025.06.001","url":null,"abstract":"<div><div>To directly, rapidly, and accurately measure trace plutonium in reprocessing samples, two α scintillation counters were developed for the direct measurement of liquids and solids after source preparation. An analytical method for directly determining trace plutonium in process samples was established. Both counters used ZnS(Ag) crystals sprayed onto light-guiding plexiglass as detectors for measuring α nuclide activity concentrations in complex samples containing simultaneous α, β, and γ nuclides. Test results indicated a 75.2 % detection efficiency for the first α scintillation counter for <sup>239</sup>Pu surface sources with good linearity over the concentration range 5 × 10<sup>−6</sup> g/L to 1 × 10<sup>−3</sup> g/L in aqueous plutonium solutions. It could also directly measure the α activity concentration in aqueous Pu solutions without source preparation. The second α scintillation counter, used a baking-dish measurement method. It exhibited excellent linearity for aqueous plutonium concentrations over 1.0 × 10<sup>−5</sup> to 1 × 10<sup>−3</sup> g/L with ≤1 % precision in the 5 × 10<sup>−5</sup> to 1 × 10<sup>−2</sup> g/L range. Both systems featured rapid and simple operation.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 3","pages":"Pages 195-202"},"PeriodicalIF":0.0,"publicationDate":"2025-06-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144470284","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Numerical study on the factors affecting natural ventilation cooling and structural optimization of glass curing body temporary storage 玻璃固化体暂存自然通风冷却影响因素及结构优化的数值研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-06-01 DOI: 10.1016/j.jandt.2025.05.005

Yuan Gao , Sihan Liu , Tianci Han , Kai Ma

{"title":"Numerical study on the factors affecting natural ventilation cooling and structural optimization of glass curing body temporary storage","authors":"Yuan Gao , Sihan Liu , Tianci Han , Kai Ma","doi":"10.1016/j.jandt.2025.05.005","DOIUrl":"10.1016/j.jandt.2025.05.005","url":null,"abstract":"<div><div>Glass curing technology is a mature and effective technical means to deal with high level liquid waste produced by spent fuel reprocessing. The dry storage technology of glass curing body is a developing trend. In the natural ventilation cooling of glass curing body temporary storage, the structural design is crucial, which directly affects the safety and stability of the temporary storage. This paper investigates the effects of various structural parameters and the application of insulating materials on the natural ventilation cooling effectiveness of the temporary storage based on Computational Fluid Dynamics (CFD). The goal is to enhance natural ventilation and reduce the thermal impact of the glass curing body on the concrete structure of the temporary storage. The results show that the height of exhaust shaft, the number of exhaust shaft, the shape of exhaust shaft, annular gap between shaft and glass products, inclination angle of baffle inside intake shaft, the dimensions of intake shaft and ventilation mode are the key factors affecting the ventilation cooling of temporary storage. The cross-sectional area of the air inlet and outlet, and the transverse pitch of glass products have little impact on the ventilation and heat exchange in the temporary storage. The optimal structural arrangement is obtained. The natural ventilation cooling effect is optimal when insulating materials are installed on the top and all four side walls of the temporary storage. The research provides a theoretical basis for the structural design and optimization of glass curing body temporary storage.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 2","pages":"Pages 128-138"},"PeriodicalIF":0.0,"publicationDate":"2025-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144189875","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Performance of sodium cooled traveling wave reactor core with axial fuel shuffling strategy 轴向燃料混流策略下钠冷却行波堆芯的性能

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-06-01 DOI: 10.1016/j.jandt.2025.05.007

Meiyin Zheng , Ping Chen , Dalin Zhang , Wenxi Tian , Guanghui Su

{"title":"Performance of sodium cooled traveling wave reactor core with axial fuel shuffling strategy","authors":"Meiyin Zheng , Ping Chen , Dalin Zhang , Wenxi Tian , Guanghui Su","doi":"10.1016/j.jandt.2025.05.007","DOIUrl":"10.1016/j.jandt.2025.05.007","url":null,"abstract":"<div><div>A prototype sodium cooled traveling wave reactor core with axial fuel shuffling, consist of an ignition and breeding region, was designed in this paper. Neutronic and depletion calculation was performed by MCORE with data library of ENDF/B-VII. A self-developed code SAST was used to perform steady state thermal-hydraulic behavior analysis. The results show that the fluctuation of the reactivity and power peak factor is too big, thus the ignition process should be optimized. The initial nuclide density distribution was adjusted and the axial fuel shuffling option was used to optimize the core ignition process. Results show that the maximum reactivity and radial power peak factor fluctuation are reduced to 1.04 % and 11.76 %; the power density distribution and neutron flux distribution move in the opposite direction of the fuel shuffling; power density, neutron flux and nuclide density are shaped like crescents in the core radial direction during equilibrium cycle; the discharged burn-up of the core is non-uniform, the maximum and minimum discharged burn-up of the outer and inner core are 17.7 % and 70.3 %, respectively. The core flow distribution analysis was based on the end of equilibrium cycle (EOEC) power distribution. Results show that maximum and minimum relative power flow ratio during the whole core life are 1.11 and 0.88; maximum fuel and cladding temperature are 676.9 °Cand 560.0 °C during the whole core life, which have a large safety margin to the design values.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 2","pages":"Pages 177-186"},"PeriodicalIF":0.0,"publicationDate":"2025-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144212543","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","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 fault diagnosis method for nuclear power plants rotating machinery based on MoCo Siamese neural network 基于MoCo - Siamese神经网络的核电站旋转机械故障诊断方法研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-06-01 DOI: 10.1016/j.jandt.2025.04.010

Xia Yubo , Zhao Yanan , Zhao Pengcheng , Zhao Zhengcheng , Yu Tao

{"title":"Research on fault diagnosis method for nuclear power plants rotating machinery based on MoCo Siamese neural network","authors":"Xia Yubo , Zhao Yanan , Zhao Pengcheng , Zhao Zhengcheng , Yu Tao","doi":"10.1016/j.jandt.2025.04.010","DOIUrl":"10.1016/j.jandt.2025.04.010","url":null,"abstract":"<div><div>Rotating machinery is a kind of significant equipment that widely used in nuclear power plants (NPPs). The harsh operating environment and long-term continuous operation of the rotating machinery can cause various faults due to wear, vibration et al., that threatens the safety of the NPPs. Intelligent fault diagnosis techniques can timely discover the abnormality of the rotating machinery, that received extensively attention in recent years. A fault diagnosis method for NPPs rotating machinery based on MoCo siamese neural network is proposed to address the issues of high noise, small sample, and low accuracy in fault diagnosis under actual operating conditions. The wavelet transform is used to denoise the sensor signals of rotating machinery and extract time-frequency features. The training samples are encoded by the siamese neural network method. The momentum contrast (MoCo) method is used to update the encoder of the siamese neural network. The cosine similarity is used to measure the similarity of sample coding features. The dataset of rotating machinery from Machinery Failure Prevention Technology (MFPT) is adopted to validate the effectiveness and accuracy of the MoCo siamese neural network method. The results shows that the proposed fault diagnosis method has strong noise resistance capability and can accurately diagnose rotating machinery in small sample conditions, demonstrating the potential application value in the fault diagnosis of NPPs rotating machinery.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 2","pages":"Pages 187-194"},"PeriodicalIF":0.0,"publicationDate":"2025-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144253998","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","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 applicability of containment test data for HPR1000 based on phenomena scaling 基于现象标度的HPR1000围堵试验数据适用性研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-06-01 DOI: 10.1016/j.jandt.2025.04.001

Liu Yusheng , Qiao Xuedong , Tan Sichao , Jing Jianping , Wang Ting , Zhu Yuanbing

{"title":"Research on applicability of containment test data for HPR1000 based on phenomena scaling","authors":"Liu Yusheng , Qiao Xuedong , Tan Sichao , Jing Jianping , Wang Ting , Zhu Yuanbing","doi":"10.1016/j.jandt.2025.04.001","DOIUrl":"10.1016/j.jandt.2025.04.001","url":null,"abstract":"<div><div>The volume of the nuclear power plant containment is huge, making it difficult to conduct equal-scale or large-scale thermal-hydraulic tests. Currently the test data mainly come from small-scale tests. To address the applicability of small-scale containment test data in validation process of the containment performance analysis code, the analysis method for applicability of experimental data is proposed and developed on the basis of similarity analysis of the pressure response process in the containment. The applicability study of the test data, which are produced by some scaled containment facilities such as the HDR, Battelle and CVTR, is carried out in combination with the test parameters. The applicability of each test case isobtained respectively when they are applied to validate the containment code in case of the Large Break Loss of Coolant Accident (LBLOCA) and Main Steam Line Break Accident (MSLB) of HPR1000 nuclear power plant. The results show that the similarity criteria for pressure response process and key phenomena within the containment vessel under accident conditions can be employed to analyze the applicability of different containment tests to specified power plant. The test dataoriginating fromHDR ISP-16 and HDR ISP-23can represent the pressure transient process, results of coupling phenomena such as mass and energy release at the break, condensation near the containment shell and internals, within the HPR1000 containment in case of LBLOCA or MSLB. The distortion is either within the acceptable range or conservative for design limits of containment pressure, so that the small-scale containment test data could be suitable for verification and validation of the HPR1000 containment thermal hydraulic response analysis code.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 2","pages":"Pages 120-127"},"PeriodicalIF":0.0,"publicationDate":"2025-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144189919","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

A study on data analysis utilizing the K-edge absorption spectroscopy in mixed thorium and uranium solutions 钍铀混合溶液中k边吸收光谱数据分析研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-06-01 DOI: 10.1016/j.jandt.2025.04.009

Han Yang , Li Li , Quanwei Liu , Yingjie Ma , Jianbin Zhou , Liudong Hou , Yongquan Qin , Yantao Hu , Jing Ma

{"title":"A study on data analysis utilizing the K-edge absorption spectroscopy in mixed thorium and uranium solutions","authors":"Han Yang , Li Li , Quanwei Liu , Yingjie Ma , Jianbin Zhou , Liudong Hou , Yongquan Qin , Yantao Hu , Jing Ma","doi":"10.1016/j.jandt.2025.04.009","DOIUrl":"10.1016/j.jandt.2025.04.009","url":null,"abstract":"<div><div>X-ray absorption spectroscopy stands as a non-destructive assay technique commonly employed in nuclear fuel reprocessing plants to analyze the concentration of elements such as uranium, plutonium,thorium.The processing of absorption spectroscopy directly affects the measurement outcomes. In this study, an experimental setup for <em>K</em>-edge absorption spectrum has been established. Acknowledging the constraints of conventional <em>K</em>-edge absorption spectrum analysis, two improved methods are proposed, including the optimized method, and the cumulative counting method. A mixed sample of thorium and uranium was utilized to conduct an experimental study. Upon analyzing and experimental results, it was determined that the cumulative counting method offers better accuracy and simplicity in processing the absorption spectrum. During the spectrum processing, adopting a wide region of interest enhances the precision of results and reduce relative deviations, while omitting background subtraction aids in simplifying the process. The cumulative counting method can also be extended to the <em>L</em>-edge absorption spectrum.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 2","pages":"Pages 156-165"},"PeriodicalIF":0.0,"publicationDate":"2025-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144196414","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Experimental progress of 209Bi(n,G)210gBi cross-section measurement based on polonium self-deposition technique 基于钋自沉积技术的209Bi(n，G)210gBi截面测量实验进展

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-06-01 DOI: 10.1016/j.jandt.2025.05.008

Feng Xu , Yushou Song , Size Chen , Jinlong wang , Guobing Yu , Deyun Wen , Dan Xiao , Yong Guo , Lei Ren

{"title":"Experimental progress of 209Bi(n,G)210gBi cross-section measurement based on polonium self-deposition technique","authors":"Feng Xu , Yushou Song , Size Chen , Jinlong wang , Guobing Yu , Deyun Wen , Dan Xiao , Yong Guo , Lei Ren","doi":"10.1016/j.jandt.2025.05.008","DOIUrl":"10.1016/j.jandt.2025.05.008","url":null,"abstract":"<div><div>Lead bismuth eutectic alloy (LBE:44.5 wt%Pb+55.5 wt%Bi) is an important coolant candidate for fourth-generation reactors due to its good physical and chemical properties. However, the risk of radioactive polonium radiation protection caused by liquid lead-bismuth alloy as the main coolant of the reactor has become an important problem that must be paid attention to in the development of the lead-bismuth reactor. The <sup>209</sup>Bi(n,γ)<sup>210g</sup>Bi reaction is a key source term for <sup>210</sup>Po generation in lead-bismuth reactors. Accurate measurement of the <sup>209</sup>Bi(n,γ)<sup>210g</sup>Bi cross section is important for assessing the risk of radioactive polonium release from lead-bismuth reactors. At present, the reaction cross section can be measured by the online method of directly measuring the cascade prompt gamma rays of the capture reaction or the offline method of measuring <sup>210g</sup>Bi decay product <sup>210</sup>Po. To solve this problem, a<sup>210</sup>Po self-plating enrichment method based on isotope dilution α energy spectrometry with electrode movement is proposed. By optimizing the key conditions of the self-plating process, the enrichment rate of <sup>210</sup>Po is effectively improved, which will help solve the problem of insufficient sensitivity of the direct measurement method of <sup>209</sup>Bi(n,γ)<sup>210g</sup>Bi low yield. The experimental results show that this technique is suitable for <sup>209</sup>Bi(n,γ)<sup>210g</sup>Bi post-processing measurement, and is of great significance for the study of neutron irradiation products of lead-bismuth eutectic alloys.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 2","pages":"Pages 139-146"},"PeriodicalIF":0.0,"publicationDate":"2025-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144189797","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Numerical simulation study on oxygen transport in the natural circulation process of liquid lead–bismuth eutectic 液态铅铋共晶自然循环过程中氧输运的数值模拟研究

International Journal of Advanced Nuclear Reactor Design and Technology Pub Date : 2025-06-01 DOI: 10.1016/j.jandt.2025.04.008

Xiangdong Wang , Wentao Guo , Shengfei Wang , Haicai Lv , Fang Liu , Zhangpeng Guo

{"title":"Numerical simulation study on oxygen transport in the natural circulation process of liquid lead–bismuth eutectic","authors":"Xiangdong Wang , Wentao Guo , Shengfei Wang , Haicai Lv , Fang Liu , Zhangpeng Guo","doi":"10.1016/j.jandt.2025.04.008","DOIUrl":"10.1016/j.jandt.2025.04.008","url":null,"abstract":"<div><div>The lead-cooled fast reactor uses liquid lead–bismuth eutectic (LBE) as the coolant. In accident conditions, a passive cooling system is used to remove the heat from the reactor core to avoid meltdown. Therefore, the natural circulation ability of liquid LBE directly affects the inherent safety of the lead-cooled fast reactor. Due to the certain corrosiveness of LBE to the metal pipe wall, oxygen control technology needs to be used to avoid corrosion. So it is of great significance to understand the transport characteristics of oxygen concentration in LBE with natural circulation. In order to study the oxygen transport characteristics of LBE in natural circulation circuit, this article uses FLUENT software to conduct CFD simulation using the oxygen transport model. The mass flow rate of natural circulation under different power conditions in the cold and hot sections was discussed. The effects of different LBE temperatures and different inlet velocities of the expansion tank on oxygen transport were discussed in a classified manner. Based on this, the simulated values were fitted to obtain the Sh number relationship (oxygen transport relationship) for different flow patterns in the expansion tank under natural circulation conditions. The simulation results can provide a reference for the design and research of lead-cooled fast reactors.</div></div>","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"7 2","pages":"Pages 166-176"},"PeriodicalIF":0.0,"publicationDate":"2025-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144196415","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0