Nuclear Engineering and Design最新文献_第8页

A review of the fundamentals and methods of accident analysis using the best estimate plus uncertainty approach in nuclear power plants

IF 1.9 3区工程技术

Nuclear Engineering and Design Pub Date : 2025-02-24 DOI: 10.1016/j.nucengdes.2025.113868

Mehdi Khoshmaram , Amir Saeed Shirani , Khashayar Sadeghi , Abbas SedghKerdar , Seyed Hadi Ghazaie , Ekaterina Sokolova

{"title":"A review of the fundamentals and methods of accident analysis using the best estimate plus uncertainty approach in nuclear power plants","authors":"Mehdi Khoshmaram , Amir Saeed Shirani , Khashayar Sadeghi , Abbas SedghKerdar , Seyed Hadi Ghazaie , Ekaterina Sokolova","doi":"10.1016/j.nucengdes.2025.113868","DOIUrl":"10.1016/j.nucengdes.2025.113868","url":null,"abstract":"<div><div>In 1989, the United States Nuclear Regulatory Commission (USNRC) revised the licensing rules for nuclear power plants (NPPs), allowing the conservative approach to be replaced by the Best Estimate Plus Uncertainty (BEPU) methodology. This replacement had two consequences: First, it became possible to use Best Estimate codes such as RELAP5 in licensing and design processes (previously, conservative codes were used). Second, methods were developed to study and quantify the uncertainty of these codes’ results and implement the BEPU approach according to the developer’s goal. The primary goal of the BEPU approach is to organize safety and thermal-hydraulics (TH) concerns for NPP licensing processes and frameworks. This approach is not uniform and various methods are used to implement it, but some concepts and basics are common. Some methods are pioneering and have initiatives within their structure, such as CSAU, GRS, and UMAE. Others improve the weaknesses of the pioneer methods (such as IMTHUA). This study aims to clarify the fundamentals, review the implementation methods, and assess the progress of studies based on the BEPU approach.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"435 ","pages":"Article 113868"},"PeriodicalIF":1.9,"publicationDate":"2025-02-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143474391","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

European SMR station blackout thermal–hydraulic analysis with the Apros system code

IF 1.9 3区工程技术

Nuclear Engineering and Design Pub Date : 2025-02-23 DOI: 10.1016/j.nucengdes.2025.113888

Marton Szogradi, Fares Alblouwy

{"title":"European SMR station blackout thermal–hydraulic analysis with the Apros system code","authors":"Marton Szogradi, Fares Alblouwy","doi":"10.1016/j.nucengdes.2025.113888","DOIUrl":"10.1016/j.nucengdes.2025.113888","url":null,"abstract":"<div><div>Recent years have seen the global development of small modular reactors (SMRs), introducing many innovative design concepts, particularly in safety systems focusing at the optimization of economic feasibility and passive reliability. Vendors, regulatory bodies and technical support organizations have been preparing for the deployment of various first-of-a-kind projects, along with international organizations who aim to streamline such efforts. The Euratom-funded ELSMOR project contributed to this work by developing the European SMR (E-SMR) dataset, which integrates publicly available information from different SMR designs. This dataset has been used to simulate various station blackout (SBO) and loss-of-coolant accident (LOCA) transients to better understand the safety aspects of design basis accidents in light-water SMRs, with a highlight on the performance of passive safety systems. This paper presents the analysis of an SBO scenario using the Apros code, showcasing the operation of a passive heat removal system, supported by the water wall and hydroaccumulators. The study also examines the interactions of these safety systems. Additionally, the paper discusses stratification processes in the water wall and other factors related to sensitivity analysis and performance optimization.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"435 ","pages":"Article 113888"},"PeriodicalIF":1.9,"publicationDate":"2025-02-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143471290","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

Effects of recrystallization on fission gas behavior in U3Si2 fuel at LWR temperature: A combination of phase-field method and rate theory

IF 1.9 3区工程技术

Nuclear Engineering and Design Pub Date : 2025-02-22 DOI: 10.1016/j.nucengdes.2025.113905

Zhenhong Ge , Xuxi Liu , Yanbo Jiang , Wenbo Liu , Di Yun

{"title":"Effects of recrystallization on fission gas behavior in U3Si2 fuel at LWR temperature: A combination of phase-field method and rate theory","authors":"Zhenhong Ge , Xuxi Liu , Yanbo Jiang , Wenbo Liu , Di Yun","doi":"10.1016/j.nucengdes.2025.113905","DOIUrl":"10.1016/j.nucengdes.2025.113905","url":null,"abstract":"<div><div>The not well-known fission gas behavior of U<sub>3</sub>Si<sub>2</sub> under light water reactor (LWR) conditions is a key limitation for its application as accident tolerant fuel (ATF) in commercial LWRs. In this paper, we developed a rate theory calculation model based on the kinetic rate theory framework originally developed in the GRASS-SST code, modified by the phase-field method, to investigate the influence of grain size on fission gas behavior in U<sub>3</sub>Si<sub>2</sub> fuel under LWR conditions. The phase=field model examines microstructural development, specifically, evolution in grain size, in U<sub>3</sub>Si<sub>2</sub> fuel. This model is then incorporated into the rate theory framework to analyze fission gas release and the retained fission gas bubble areal fraction during irradiation. The integration of these mesoscale models enhances our understanding of the impact of grain size evolution on fission gas behavior. The simulations of fission gas release show good agreement with post-irradiation examination (PIE) data, providing validation to the model and insights into the varying retained fission gas behavior observed in different regions of irradiated fuel pellet.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"435 ","pages":"Article 113905"},"PeriodicalIF":1.9,"publicationDate":"2025-02-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143464725","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

Investigation of burnup and temperature effects on the grain size of UO2 fuel along fission gas behavior

IF 1.9 3区工程技术

Nuclear Engineering and Design Pub Date : 2025-02-21 DOI: 10.1016/j.nucengdes.2025.113937

A. Sadeghnoedoost, A. Zolfaghari, A.S. Shirani

{"title":"Investigation of burnup and temperature effects on the grain size of UO2 fuel along fission gas behavior","authors":"A. Sadeghnoedoost, A. Zolfaghari, A.S. Shirani","doi":"10.1016/j.nucengdes.2025.113937","DOIUrl":"10.1016/j.nucengdes.2025.113937","url":null,"abstract":"<div><div>The fuel rod behavior at high burnups is in the center of attention and a clear trend over the last decades toward increasing fuel burnup in light water reactors can be observed. The implications of this initiative, however, have not been fully explored; hence the practical issues for high-burnup PWR fuels are needed for more treatment. The aim of this paper is to investigate the specific features of the high burnup structure and temperature of the irradiated nuclear fuel on grain size variation and fission gas behavior and to explore the various relevant parameters. In order to evaluate fission gases behavior such as intra-granular gas diffusion, inter-granular gas bubble growth, bubble coalescence and rate of fission gases release a program called SS is developed; and the grain growth models with temperature in low and high burnup are included to fission gas behavior in the program and obtained results compared with published data in literature; the comparison indicates results are in good agreement with each other in low burnup; however, in high burnup and low temperature region (HBS)<span><span><sup>1</sup></span></span> more experience and investigations are needed to exploit discrepancies.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"435 ","pages":"Article 113937"},"PeriodicalIF":1.9,"publicationDate":"2025-02-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143464724","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

A quantitative analysis of ATF surface characteristics on critical heat flux using Machine learning

IF 1.9 3区工程技术

Nuclear Engineering and Design Pub Date : 2025-02-21 DOI: 10.1016/j.nucengdes.2025.113924

Bruno P. Serrao , Ye Kwon Huh , Eliot Ciuperca , Elvan Sahin , Kaibo Liu , Juliana P. Duarte

{"title":"A quantitative analysis of ATF surface characteristics on critical heat flux using Machine learning","authors":"Bruno P. Serrao , Ye Kwon Huh , Eliot Ciuperca , Elvan Sahin , Kaibo Liu , Juliana P. Duarte","doi":"10.1016/j.nucengdes.2025.113924","DOIUrl":"10.1016/j.nucengdes.2025.113924","url":null,"abstract":"<div><div>The effects of surface characteristics on pool boiling Critical Heat Flux (CHF) are qualitatively understood based on previous investigations. However, more quantitative analyses are needed since the existing CHF correlations do not provide good predictions for modified surfaces. Using machine learning (ML) models as a tool, this study performed a quantitative analysis of relevant CHF parameters under pool boiling conditions: pressure, a dimensional feature, average roughness, static contact angle, surface orientation, and substrate thermal effusivity. A database was constructed by collecting accident tolerant fuels (ATF) CHF experimental data available from fourteen published studies. After hyperparameter optimization, the random forest (RF) model was selected for achieving the best fitting scores relative to other tested models. Feature importance models ranked static contact angle and pressure as the most important features, which is consistent with some of the literature CHF predictive models that take the surface characteristics into consideration. Finally, CHF predictions were obtained and compared to CHF experimental data. The effect of each feature on CHF was analyzed, while keeping other features fixed, by observing the experimental and predicted datapoints trends. The RF model demonstrated the ability to capture the experimental data trends, showing the RF model is suitable as a predictive pool boiling CHF model for this database.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"435 ","pages":"Article 113924"},"PeriodicalIF":1.9,"publicationDate":"2025-02-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143453643","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 safe disposal technology and progress of radioactive nuclear waste

IF 1.9 3区工程技术

Nuclear Engineering and Design Pub Date : 2025-02-21 DOI: 10.1016/j.nucengdes.2025.113934

Duo Dong , Ziqi Wang , Jingyu Guan , Yi Xiao

{"title":"Research on safe disposal technology and progress of radioactive nuclear waste","authors":"Duo Dong , Ziqi Wang , Jingyu Guan , Yi Xiao","doi":"10.1016/j.nucengdes.2025.113934","DOIUrl":"10.1016/j.nucengdes.2025.113934","url":null,"abstract":"<div><div>Nuclear energy as an important way to solve the energy crisis, has achieved multi-dimensional utilization in fields of power generation, heating, hydrogen production, seawater desalination, and isotope production. The safe disposal of radioactive waste directly affects the sustainable development of nuclear energy. The solidification of radioactive waste on specific substrates and deep geological disposal is an effective way to achieve permanent shielding of radioactive waste. The paper focuses on the latest developments in the disposal of radioactive waste, and comprehensively elaborating on various solidification disposal technologies for radioactive waste (cement solidification, asphalt solidification, polymer solidification, artificial rock solidification, glass solidification), as well as melting preparation processes (tank method, calcination + induction heating metal melting furnace, Joule heating ceramic melting furnace, cold crucible). In addition, the design principles, confinement mechanism, and application status of typical glass solidification technology were discussed, and the characteristics of typical borosilicate and phosphate glass matrices used to envelop radioactive nuclides were analyzed. Finally, the future development path of radioactive waste solidification disposal was pointed out, and providing reference for promoting the safe and efficient disposal of radioactive waste in the nuclear industry.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"435 ","pages":"Article 113934"},"PeriodicalIF":1.9,"publicationDate":"2025-02-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143453645","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

Development of an on-line structural integrity assessment system for the primary loop pipeline in NPPs

IF 1.9 3区工程技术

Nuclear Engineering and Design Pub Date : 2025-02-21 DOI: 10.1016/j.nucengdes.2025.113908

Mingya Chen , Fangjie Shi , Changjin Geng , Weiwei Yu , Quanjia Peng , Wanxian Zhao , Shuiyong Wang , Guanbin Ma , Yaolei Han

{"title":"Development of an on-line structural integrity assessment system for the primary loop pipeline in NPPs","authors":"Mingya Chen , Fangjie Shi , Changjin Geng , Weiwei Yu , Quanjia Peng , Wanxian Zhao , Shuiyong Wang , Guanbin Ma , Yaolei Han","doi":"10.1016/j.nucengdes.2025.113908","DOIUrl":"10.1016/j.nucengdes.2025.113908","url":null,"abstract":"<div><div>A comprehensive online structural integrity assessment (SIA) methodology that fully accounts for the actual aging conditions and real-time transient operating parameters of primary loop pipelines in nuclear power plants remains absent in the existing literature. This paper proposes a novel online SIA approach based on thermoelectric potential (TEP) and failure assessment diagram (FAD) technologies. Initially, the online SIA process is established, and a conversion method between TEP values and impact energy is explored. The findings demonstrate that the Seebeck coefficient is highly sensitive to microstructural changes in the material, and the variation trend of TEP values closely aligns with that of impact energy. Subsequently, a systematic conversion methodology for TEP values and fracture toughness is presented. The FAD for primary loop pipelines is developed and analyzed. Sensitivity analysis of the safety margin reveals that enhancing the flow stress strength of the material or reducing the structural load is an effective strategy for improving the safety margin of the primary loop pipeline. Finally, an online SIA software, which has been successfully applied in the assessment of a nuclear power plant, is introduced. The SIA-based results confirm that the pipeline remains safe during the actual startup process.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"435 ","pages":"Article 113908"},"PeriodicalIF":1.9,"publicationDate":"2025-02-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143453644","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

Formation of gas bubble superlattice in U-Mo alloys: A phase-field study

IF 1.9 3区工程技术

Nuclear Engineering and Design Pub Date : 2025-02-20 DOI: 10.1016/j.nucengdes.2025.113912

Yanbo Jiang , Shisen Gao , Yongxiao La , Wenbo Liu

{"title":"Formation of gas bubble superlattice in U-Mo alloys: A phase-field study","authors":"Yanbo Jiang , Shisen Gao , Yongxiao La , Wenbo Liu","doi":"10.1016/j.nucengdes.2025.113912","DOIUrl":"10.1016/j.nucengdes.2025.113912","url":null,"abstract":"<div><div>The impact of grain boundary (GB) on the formation and evolution of gas bubble superlattices (GBS) in U-Mo alloys under irradiation is critical for understanding the material behavior in nuclear environments. In this study, a phase-field model coupled Kim-Kim-Suzuki (KKS) model and explicit nucleation algorithm was developed to simulate GBS formation. The accumulation of vacancies and gas atoms led to bubble nucleation, with directional migration of interstitial atoms inducing a shadow effect and causing ordered bubble arrangements. The GBS exhibited stability, with bubble size and lattice constants remaining nearly constant at higher fission densities. The GB was shown to influence GBS formation significantly, with the surrounding region divided into a denuded zone and a peak zone. The width of the denuded zone is influenced by the GB properties. In this work, the relationship between the denuded zone width and the GB absorption strength was derived using a one-dimensional steady-state vacancy diffusion equation. It was found that the denuded zone width increases with an increase in the GB absorption coefficient. The phase-field simulation results were consistent with theoretical predictions. These findings contribute to a better understanding of how GBs affect irradiation-induced microstructural changes in nuclear materials.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"435 ","pages":"Article 113912"},"PeriodicalIF":1.9,"publicationDate":"2025-02-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143444782","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

Seismic performance analysis of suspended storage structure in lead-based reactor considering the coupled effects of liquid sloshing and soil condition

IF 1.9 3区工程技术

Nuclear Engineering and Design Pub Date : 2025-02-20 DOI: 10.1016/j.nucengdes.2025.113935

Yin Xunqiang, Chen Xu, Xu Shutong

{"title":"Seismic performance analysis of suspended storage structure in lead-based reactor considering the coupled effects of liquid sloshing and soil condition","authors":"Yin Xunqiang, Chen Xu, Xu Shutong","doi":"10.1016/j.nucengdes.2025.113935","DOIUrl":"10.1016/j.nucengdes.2025.113935","url":null,"abstract":"<div><div>LEAd-based Reactor (LEAR) has good inherent safety, potentially making it the first commercial application of the fourth-generation nuclear power system. Facing the complex inland seismic geological environment, the sloshing of liquid heavy metal coolant with pool layout will significantly influence the seismic performance of suspended storage structure. To improve the seismic safety of the LEAR, a comprehensive study of the effect of liquid sloshing and soil conditions was discussed by combining the Compact Viscoelastic (CV) element for soil-structure interaction analysis, fluid–structure interaction for sloshing analysis and refined simulation of suspended storage structure within the framework of finite elements. And then, the verification example of cylindrical liquid storage vessel was presented to demonstrate the accuracy and efficiency of the proposed fluid–structure interaction model. Finally, the analysis of displacement, acceleration, maximum interlayer displacement angles, and other dynamic responses are carried out to study the effect of liquid sloshing features and soil conditions. The results showed that the properties of the coolant and internal components affect the response of the suspended storage structure, and the soft soil significantly increases the sloshing wave height of the internal fluid, while the overall displacement patterns and amplitude variations are relatively modest. The findings of this study may provide theoretical support and technical foundation for seismic safety evaluation and optimization design of LEAR suspended storage structure under the complex soil site.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"435 ","pages":"Article 113935"},"PeriodicalIF":1.9,"publicationDate":"2025-02-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143453642","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

Buoyant-diffusive flow in the HTGR air ingress accident scenario

IF 1.9 3区工程技术

Nuclear Engineering and Design Pub Date : 2025-02-20 DOI: 10.1016/j.nucengdes.2025.113922

Zachary Welker , Annalisa Manera , Victor Petrov , Paolo Balestra

{"title":"Buoyant-diffusive flow in the HTGR air ingress accident scenario","authors":"Zachary Welker , Annalisa Manera , Victor Petrov , Paolo Balestra","doi":"10.1016/j.nucengdes.2025.113922","DOIUrl":"10.1016/j.nucengdes.2025.113922","url":null,"abstract":"<div><div>Experimental data from the Helium-Air Ingress gas-Reactor Experiment (HAIRE) has provided insight into an infrequently studied flow scenario where buoyant driven flow and molecular diffusion combine during an exchange flow. The combined buoyant-diffusive exchange flow occurs because of a transition region where buoyancy and molecular diffusion combine to create flow rates higher than the separate flow regimes would predict. The buoyo-diffusive flow is described by a dimensionless number which is used to quantitatively explain the results. The flow regime is of considerable importance in the small and medium-sized accident scenarios for High-Temperature Gas-cooled Reactors (HTGRs), where the flow regime will increase the air ingress rate in comparison to previously understood theory. For medium sized breaks the estimated increase in air ingress rate is up to 5% compared to the previous theory, and for small sized breaks the increase is either 5% or greater depending on the break size. This considerable increase in air ingress rates could affect the evolution of small- and medium-sized air ingress accidents and the overall damage to the HTGR’s graphite core. Buoyo-diffusive exchange flow could manifest in other areas where small physical scales and high mass diffusion are present.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"435 ","pages":"Article 113922"},"PeriodicalIF":1.9,"publicationDate":"2025-02-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143444784","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