Progress in Nuclear Energy最新文献

{"title":"The preliminary design of emergency core cooling scheme and loss-of-coolant accident analysis for Tsinghua high flux reactor","authors":"Zhuang Wang ,&nbsp;Wei Xu ,&nbsp;Heng Xie","doi":"10.1016/j.pnucene.2024.105453","DOIUrl":"10.1016/j.pnucene.2024.105453","url":null,"abstract":"<div><div>This paper proposes the preliminary emergency core cooling scheme for Tsinghua High Flux Reactor. According to the thermohydraulic characteristics of high flux reactors, forced circulation needs to be maintained by emergency pumps in the early stage. When the decay power is low enough, natural circulation between core and the reactor pool is initiated to remove the residual core heat. The sources of safety injection are accumulators and reactor pool. Accumulator injection can ensure core safety in the early stage and reactor pool injection can maintain long time stable forced circulation. To avoid emptying the reactor pool, the waterproof zone needs to be built. The waterproof zone consists of reactor pool and several finite volume dry pools. All pipelines and equipment in the reactor coolant system are placed in the dry pools. Once break accident occurs, the dry pool where the break is located can collect the leaked coolant. With the increase of break back pressure, the break flow is restricted. The current scheme is modeled by Relap5 and different size breaks at four locations (namely core inlet, core outlet, primary heat exchanger inlet and main pump inlet) are assumed. According to the response characteristics of the scheme, the accident process can be divided into five stages: non-shutdown stage, high-injection stage, low-injection stage, stable forced circulation stage and natural circulation stage. Critical heat flux predicted by Sudo CHF correlations is adopted as the primary safety criterion. Through analysis, a success path is found to maintain core safety for a wide range of loss-of-coolant accident scenarios.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105453"},"PeriodicalIF":3.3,"publicationDate":"2024-09-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142312485","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":"Adsorption of strontium from aqueous solution using ethyl butyl phosphonate (EBP) silica","authors":"Sarah E. Pepper ,&nbsp;Thomas J. Robshaw ,&nbsp;James T.M. Amphlett ,&nbsp;Laura R. Ruder ,&nbsp;Laurence M. Harwood ,&nbsp;Taek Seung Lee ,&nbsp;Karl R. Whittle ,&nbsp;Mark D. Ogden","doi":"10.1016/j.pnucene.2024.105458","DOIUrl":"10.1016/j.pnucene.2024.105458","url":null,"abstract":"","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105458"},"PeriodicalIF":3.3,"publicationDate":"2024-09-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142312487","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":"Systematic derivation of GSP3(0) equations, its discretization using GTIN method and development of a switchable SP3 to GSP3(0) neutron transport solver","authors":"Abhishek Mishra ,&nbsp;Aditi Ray ,&nbsp;Tej Singh","doi":"10.1016/j.pnucene.2024.105422","DOIUrl":"10.1016/j.pnucene.2024.105422","url":null,"abstract":"<div><div>The Generalized Simplified Spherical Harmonics (GSP_N) method has drawn recent interest owing to the fact that theoretically, it is equivalent to the P_N and does not rely on any assumption other than piecewise homogeneity. Its level wise approach to P_N offers an agreeable balance between the accuracy and computational efficiency making it a valuable mathematical tool for analyzing neutron transport problems pertaining to nuclear engineering and reactor physics. The lowest level approximation for <em>N</em> = 3, expressed as <span><math><mrow><msubsup><mtext>GSP</mtext><mn>3</mn><mrow><mo>(</mo><mn>0</mn><mo>)</mo></mrow></msubsup></mrow></math></span>, offers reducing the complexity while still capturing the essential physics. In the current work, <span><math><mrow><msubsup><mtext>GSP</mtext><mn>3</mn><mrow><mo>(</mo><mn>0</mn><mo>)</mo></mrow></msubsup></mrow></math></span> equations are derived along with the interface and boundary conditions for linear anisotropic scattering. These equations are then discretized using the generalized transverse integration nodal method for a two-dimensional system of piecewise homogeneous rectangular regions. The discretization is done with an option kept for reducing the <span><math><mrow><msubsup><mtext>GSP</mtext><mn>3</mn><mrow><mo>(</mo><mn>0</mn><mo>)</mo></mrow></msubsup></mrow></math></span> formalism to the conventional SP₃. Subsequently, a computer code has been developed to solve these discretized equations in the multigroup structure for vacuum, reflective or albedo boundaries. At present, this switchable SP₃/<span><math><mrow><msubsup><mtext>GSP</mtext><mn>3</mn><mrow><mo>(</mo><mn>0</mn><mo>)</mo></mrow></msubsup></mrow></math></span> code has the capability of estimating <em>k</em>-eigenvalue and position dependent scalar neutron flux within a given two-dimensional rectangular geometry. The code has been verified by solving SP₃, <span><math><mrow><msubsup><mtext>GSP</mtext><mn>3</mn><mrow><mo>(</mo><mn>0</mn><mo>)</mo></mrow></msubsup></mrow></math></span> and other benchmark problems from available literature. The results obtained from our code demonstrate that <span><math><mrow><msubsup><mtext>GSP</mtext><mn>3</mn><mrow><mo>(</mo><mn>0</mn><mo>)</mo></mrow></msubsup></mrow></math></span> is superior to the conventional SP₃ and comparable to the recently proposed SDP_N (N = 1,2,3) [M. Nazari, A. Zolfaghari, M. Abbasi, Prog. Nucl. Energy, 2023; <strong>166</strong>, 104,933] in terms of accuracy as well as computation time.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105422"},"PeriodicalIF":3.3,"publicationDate":"2024-09-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142312486","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":"Development of advanced AI-based segmentation and prediction method for air entrainment in plunging water jets","authors":"Wen Zhou ,&nbsp;Shuichiro Miwa ,&nbsp;Susumu Yamashita ,&nbsp;Koji Okamoto","doi":"10.1016/j.pnucene.2024.105441","DOIUrl":"10.1016/j.pnucene.2024.105441","url":null,"abstract":"<div><p>Understanding air entrainment phenomena induced by plunging water jets is critical in the fields of nuclear and hydraulic engineering. Air entrainment is one of the key safety design parameters for nuclear systems. However, most existing studies rely on empirical correlations or curve-fitting models to estimate bubble penetration depth, and no agreed-upon calculation principle exists for varying jet conditions. To address these limitations, this research developed two advanced AI approaches: an improved YOLOv5 for segmenting air entrainment and the NSGA-III-BPNN method for predicting penetration depth. The improved YOLOv5 enables real-time segmentation and extraction of air entrainment motion and dynamics under diverse conditions, demonstrating high scalability and robustness. The penetration depth estimated using the improved YOLOv5 shows greater accuracy compared to conventional empirical correlationsand is more efficient than traditional image post-processing techniques for classifying shape regimes based on dynamic air entrainment patterns. To overcome the limitations of object segmentation, which typically relies on video or image data, the NSGA-III-BPNN method predicts maximum penetration depths with greater accuracy than YOLOv5, offering a more effective prediction model for air entrainment penetration depth. By leveraging advanced AI techniques, the research not only provides valuable segmentation data for refining computational fluid dynamics (CFD) modeling but also paves the way for significant advancements in both nuclear and hydraulic engineering.</p></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105441"},"PeriodicalIF":3.3,"publicationDate":"2024-09-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S0149197024003913/pdfft?md5=d9256c2ad7dd95d6ee94c75c0b50fd2c&pid=1-s2.0-S0149197024003913-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142270904","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Design challenges and response plans for intelligent decision support systems for Korean nuclear power plants under normal and abnormal conditions","authors":"Gwi-sook Jang,&nbsp;Seo Ryong Koo","doi":"10.1016/j.pnucene.2024.105442","DOIUrl":"10.1016/j.pnucene.2024.105442","url":null,"abstract":"<div><p>In nuclear power plants (NPPs), an intelligent decision support system (IDSS) aids the decision-making process of main control room operators. It achieves this by monitoring and diagnosing conditions, predicting progress, and providing preventive advice during both normal and abnormal operations. Despite ongoing research in Korea, few IDSS for NPPs have been effectively applied and verified. Furthermore, established designs and validation guidelines for IDSSs for Korean NPPs remain lacking. To address this gap, this study systematically identifies problems and corresponding countermeasures for applying artificial intelligence-based design and validation technologies, while complying with licensing regulatory standards. The aim is to develop a practical and effective IDSS. This study identifies design challenges in the practical application of fundamental IDSS technology, outlining necessary design and validation technologies. Additionally, it suggests technology-specific response plans for the identified design challenges.</p></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105442"},"PeriodicalIF":3.3,"publicationDate":"2024-09-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142270903","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":"Synthesis of polymer composites using cryogenic grinding and study of their mechanical characteristics and theoretcal calculations for neutron-protective parameters","authors":"N.I. Cherkashina ,&nbsp;V.I. Pavlenko ,&nbsp;A.V. Noskov ,&nbsp;D.S. Romanyuk ,&nbsp;V.M. Gavrish ,&nbsp;T.V. Chayka","doi":"10.1016/j.pnucene.2024.105449","DOIUrl":"10.1016/j.pnucene.2024.105449","url":null,"abstract":"<div><p>The article deals with the problems of creating composite materials for neutron shielding. A method for creating a composite material is proposed and described based on polyethylene and B₄C boron carbide. For the first time, the possibility of synthesizing composites of the proposed composition using cryogenic grinding under low-temperature processing conditions was established in this article. The main physical-mechanical, thermal and neutron-protective properties of the composite material were studied depending on the content of B₄C. A composite containing 30% boron carbide synthesized using cryogenic grinding has the following mechanical characteristics: flexural strength - 5.96 MPa, flexural strain at flexural strength 8.56 %, Vickers microhardness, 7.7 ± 0.8 HV₂₀₀.</p></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105449"},"PeriodicalIF":3.3,"publicationDate":"2024-09-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142244178","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Experimental study on flow patterns and pressure gradient of decaying swirling gas-liquid flow in a horizontal pipe","authors":"Shuo Chen ,&nbsp;Shuai Liu ,&nbsp;Li Liu ,&nbsp;Yamin Li ,&nbsp;Jiarong Zhang ,&nbsp;Tenglong Cong ,&nbsp;Hanyang Gu","doi":"10.1016/j.pnucene.2024.105445","DOIUrl":"10.1016/j.pnucene.2024.105445","url":null,"abstract":"<div><p>The utilization of swirling flow in multiphase flow devices is prevalent for purposes such as mixing, separation, stabilization, and heat transfer enhancement, primarily owing to its characteristic of inducing low-pressure drop. In the nuclear industry, for example, two-phase swirling flow is applied in the nuclear gas generator to improve gas quality. In this study, an experimental investigation was conducted on the decaying swirling flow of gas-liquid in a horizontal pipe equipped with a vane-type swirler. The flow patterns were visually examined, and the pressure gradients along the test pipe and across the swirler were measured. The findings suggest the presence of four distinct swirling flow patterns at the swirler outlet (z/D = 0), namely chain flow, swirling gas column flow, swirling intermittent flow, and swirling annular flow. Because of swirl decay, these swirling flows recover their original pattern approximately 70<em>D</em> downstream from the swirler, with the exception of the swirling gas column flow. The flow regime maps at <em>z</em>/<em>D</em> = 10, 40, 70 and 100 are proposed and the pattern-based pressure gradient characteristics are analyzed. It is shown that the pressure gradient rises as both gas superficial velocity (<em>j</em>_g) and liquid superficial velocity (<em>j</em>_l) increase. The largest pressure gradient occurs within the swirler section, while the lowest is found upstream of the swirler. Near the swirler outlet (<em>z</em>/<em>D</em> = 0–33), the pressure gradient is approximately 1.5–2.3 times higher than at <em>z</em>/<em>D</em> = 33–67. Further downstream, at <em>z</em>/<em>D</em> = 67–100, it is 2.2–3.5 times greater, depending on the flow patterns.</p></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105445"},"PeriodicalIF":3.3,"publicationDate":"2024-09-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142244175","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 Uneven characteristics and mechanism investigation of multiple jet droplets in space","authors":"Fulong Zhao ,&nbsp;Kang Zhao ,&nbsp;Ruixuan Wei ,&nbsp;Yuan Zhao ,&nbsp;Sichao Tan ,&nbsp;Ruifeng Tian","doi":"10.1016/j.pnucene.2024.105417","DOIUrl":"10.1016/j.pnucene.2024.105417","url":null,"abstract":"<div><p>The liquid droplet radiator (LDR) system can achieve a maximum heat transfer capacity of ten times that of traditional heat pipe heat exchangers per unit mass, which is very advantageous for the use of future space equipment. LDR mainly consists of a droplet generator, droplet layer, droplet collector, circulation pump, and corresponding pipelines, among which the droplet generator is the key equipment for generating the droplet layer. By using numerical and computational fluid dynamics methods, a droplet flow calculation model is developed to simulate the generation of droplets through high-frequency disturbance jet breakup in a thin atmosphere, without considering gravity. This model aims to replicate the operation of a droplet generator. After verification, the calculation result has an error of about 5%. Analyze the working fluids of silicone oil and liquid metal lithium, examining the parameters of droplet diameter <em>d</em>, droplet spacing <em>s</em>, and droplet uniformity generated by the jet under varying jet velocities, disturbance frequencies, and other working conditions. Additionally, assess the impact of each condition on the results. The results show that the diameter <em>d</em> of the droplet is directly proportional to the surface tension and the initial velocity of the jet, and inversely proportional to the disturbance frequency. The droplet spacing <em>s</em> and droplet polydispersity index <em>λ</em> are inversely proportional to the disturbance frequency and directly proportional to the jet velocity. The increase in surface tension and disturbance frequency can improve the uniformity of droplet flow, and the minimum droplet polydispersity index can be reduced to around 1%. Priority should be given to adjusting the jet velocity to obtain more uniform droplets to determine the working fluid. After leaving the nozzle, the jet will generate vortices, which will affect the subsequent droplet velocity. The average velocity of the droplet is about 80% of the undisturbed velocity of the jet. The analysis of jet motion characteristics and the variation patterns of droplet diameter and uniformity can provide a basis for the design of droplet generators.</p></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105417"},"PeriodicalIF":3.3,"publicationDate":"2024-09-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142244177","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":"Combination of two-fluid model and delayed equilibrium model for the critical flow in a slit","authors":"Yuxiang He ,&nbsp;Weiguo Gu ,&nbsp;Dezhong Wang","doi":"10.1016/j.pnucene.2024.105406","DOIUrl":"10.1016/j.pnucene.2024.105406","url":null,"abstract":"<div><p>Accurately predicting the mass flux, pressure profile, and velocity profile of the critical flow in a slit is essential for analyzing the breaking process of the liquid phase and calculating the aerosol source term for leak-before-break (LBB) monitoring and Loss of Coolant Accident (LOCA) risk analysis. A new critical flow model combining Two-fluid Model (TFM) and Delayed Equilibrium Model (DEM) is built to get accurate profiles while avoiding the same phase velocity in DEM and the arbitrary critical flow criterion in TFM. The new model is verified using past experiments of the critical flow in a slit. It proves to be accurate in mass flux but not in critical pressure, with maximum relative errors of around 25% in mass flux and around 80% in critical pressure. The new model is optimized for higher accuracy in critical pressure. The empirical equation of saturated phase mass flow rate fraction gradient is optimized by conducting approximate pressure profile calculation and regression analysis. The maximum relative error decreases little while the ratio of critical pressure relative errors lying in the range of ±40% increases after optimization. In contrast, the difference in the average abstract relative error of pressure between original TFM-DEM and DEM is much larger, for the maximum relative error of mass flux and critical pressure are around 25% and 110%. The comparison between the original and optimized TFM-DEM proves that the new critical flow model is accurate in mass flux and can be optimized to raise pressure calculation accuracy. The comparison between the original TFM-DEM and DEM proves that the phase velocity difference is the major source of accuracy improvement in the pressure profile.</p></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105406"},"PeriodicalIF":3.3,"publicationDate":"2024-09-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142233901","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":"Data and modeling sensitivity analysis for molten salt fast reactor benchmark – Static calculations","authors":"Rihan Ali ,&nbsp;Saeed A. Alameri ,&nbsp;Mohammad Alrwashdeh ,&nbsp;Sümer Şahin ,&nbsp;Khurrum Saleem Chaudri","doi":"10.1016/j.pnucene.2024.105446","DOIUrl":"10.1016/j.pnucene.2024.105446","url":null,"abstract":"<div><p>The Molten Salt Reactor (MSR) idea is increasingly being recognized in the nuclear field due to its potential safety, sustainability, and economic efficiency advantages. The Molten Salt Fast Reactor (MSFR) benchmark, introduced in 2019, highlighted variations in results tied to different neutron cross-section libraries. This study investigates the impact of utilizing the ENDF/B-VIII.0 and JEFF-3.3 cross-section libraries for MSFR benchmark assessment compared to the ENDF/B-VII.1 database. Monte Carlo based open source code OpenMC is used for the analyses. Rigorous sensitivity analyses assess the influence of individual components, including the cross-section database, resonance elastic scattering, and Thermal Scattering Law (TSL). Beyond the criticality assessments, parameters such as delayed neutron fraction, temperature coefficient of reactivity, and neutron spectrum are compared for different cross-section libraries. Our analyses reveal that incorporating new evaluations for ²³³U (n,γ) and fission cross-sections in ENDF/B-VIII.0 significantly alters criticality results, i.e., more than 1700 pcm difference is seen between libraries. Similarly, critical concentration using ENDF/B-VII.1 and JEFF-3.3 is over-predicted by approximately 3%. The variations in Thermal Scattering Law (TSL) files do not yield substantial differences in outcomes due to the fast spectrum of the reactor. In some cases, the treatment of resonance elastic scattering leads to reactivity differences greater than 50 pcm. The benchmark compares ²³³U-started and Minor Actinide (MA)-started core. From the reactor physics point of view, the MA-started core leads to a 29% higher (n, γ) reaction rate than the ²³³U-started core. A 3–4% smaller value of thermal reactivity coefficient is obtained using the ENDF/B-VIII.0 library compared to the ENDF/B-VII.1 value. Using the ENDF/B-VIII.0 for the MSFR benchmark signifies using newer and better data for the GEN-IV reactors neutron physics calculations.</p></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"177 ","pages":"Article 105446"},"PeriodicalIF":3.3,"publicationDate":"2024-09-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142243553","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}