Fusion Engineering and Design最新文献

{"title":"Engineering tool for the optimization of leading edges in a tungsten-based divertor in W7-X: How to optimize adjacent chamfers","authors":"Antara Menzel-Barbara ,&nbsp;Joris Fellinger ,&nbsp;Rudolf Neu ,&nbsp;Dirk Naujoks ,&nbsp;Michael Endler","doi":"10.1016/j.fusengdes.2025.115439","DOIUrl":"10.1016/j.fusengdes.2025.115439","url":null,"abstract":"<div><div>Leading edges on the divertor surface of fusion devices are typically mitigated through tilting or chamfering the target components, so as to keep the potential leading edge unexposed to the particle flux. However, for neighboring components subjected to impinging particles from opposite direction, chamfering one component can lead to an increased size of leading edge on the neighboring component. The Wendelstein 7-X (W7-X) fusion device is particularly sensitive to this issue, as it features a great variety of magnetic configurations, each with a unique particle deposition pattern. This study uses thermal finite element method (FEM) simulations to analyze the thermal performance and design parameters of symmetric and asymmetric chamfering in divertor targets. For symmetric load cases, the effect of chamfer length and depth on maximum temperature is investigated. Key chamfer design trends are established to optimize the temperature by making the chamfer deep enough to avoid a leading edge while making the chamfer long enough to keep the heat load on the chamfer under a limit threshold. Based on these findings, an iterative algorithm is presented for asymmetric chamfer configurations, ensuring feasible solutions under different thermal loads. This work introduces a novel geometric classification of asymmetric chamfering scenarios in stellarator divertors, and presents the first practical algorithm capable of identifying feasible chamfer geometries under asymmetric bi-directional loading—an issue not addressed in existing tokamak-focused literature. It forms a part of a more comprehensive divertor design and optimization tool for W7-X under development.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115439"},"PeriodicalIF":2.0,"publicationDate":"2025-09-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145096619","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 a low-frequency magnetic probe array for the quasi-axisymmetric stellarator CFQS-T","authors":"H. Lan ,&nbsp;J.D. Li ,&nbsp;Y.H. Cao ,&nbsp;J.F. Shen ,&nbsp;J.C. Li ,&nbsp;Y. Xu ,&nbsp;T.F. Sun ,&nbsp;M.Y. He ,&nbsp;Y.X. Feng ,&nbsp;D.N. Wu ,&nbsp;J. Cheng ,&nbsp;H.F. Liu ,&nbsp;A. Shimizu ,&nbsp;X.Q. Wang ,&nbsp;W.M. Xuan ,&nbsp;M.Y. Zhang ,&nbsp;Q. Zou ,&nbsp;X. Zhang ,&nbsp;H. Liu ,&nbsp;J. Huang ,&nbsp;C.J. Tang","doi":"10.1016/j.fusengdes.2025.115442","DOIUrl":"10.1016/j.fusengdes.2025.115442","url":null,"abstract":"<div><div>The quasi-axisymmetric magnetic configuration and the subsequent experimental campaign were successfully achieved in the first experimental phase of the Chinese First Quasi-axisymmetric Stellarator (CFQS) in 2024, which is also called CFQS-Test, abbreviated as CFQS-T. A first low-frequency magnetic probe array (LFMPA) diagnostic has been developed for measuring the magnetic field and fluctuations in the CFQS-T. The LFMPA diagnostic is composed of 12 identical three-dimensional magnetic probes, and each magnetic probe can provide toroidal, poloidal, and radial magnetic field and fluctuation measurements. The dedicated mechanical system, electric system, data acquisition, and control system of the LFMPA are developed based on the CFQS-T experimental conditions, which are briefly described in this paper. The calibrations of effective area and in-situ frequency response of each LFMPA magnetic probe have been done, which are important for quantitatively studying the magnetic field and fluctuations (of frequency <span><math><mrow><mi>f</mi><mo>≤</mo><mn>50</mn><mspace></mspace><mi>k</mi><mi>H</mi><mi>z</mi></mrow></math></span>) measured by the LFMPA. Preliminary application of the LFMPA in CFQS-T experiments shows that the LFMPA works well for the magnetic field measurements, as partially verified by the simulation results of the three-dimensional equilibrium code VMEC. And the LFMPA diagnostic, without connecting the integrator, works well for measuring the magnetic fluctuations. A low-frequency coherent mode is first observed by the LFMPA and briefly reported in this article. The LFMPA can be a useful diagnostic for various physical topic studies on CFQS-T.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115442"},"PeriodicalIF":2.0,"publicationDate":"2025-09-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145096615","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":"Cavity design and interaction computation of a tri-frequency 42-85-94 GHz gyrotron","authors":"Ravinder Beemagani ,&nbsp;S. Yuvaraj ,&nbsp;A.K. Jha ,&nbsp;M.V. Kartikeyan","doi":"10.1016/j.fusengdes.2025.115443","DOIUrl":"10.1016/j.fusengdes.2025.115443","url":null,"abstract":"<div><div>This article presents the design of RF interaction assembly of a gyrotron proposed for generating millimeter waves at three distinct frequencies: 42 GHz, 85 GHz, and 94 GHz. The gyrotron is designed to deliver an output power exceeding 200 kW at each frequency, with an efficiency of approximately 40%. These frequencies are chosen to support various RF heating and sensing requirements of nuclear fusion tokamak systems. RF behavior analysis carried out in this work includes: mode-selection procedure, cold cavity analysis, single-mode analysis and time-dependent multi-mode analysis. The analyses and design are performed using our in-house software package Gyrotron Design Studio (GDS V. 2024). Comprehensive numerical simulations are carried out to design the interaction cavity geometry and determine the nominal beam parameters for supporting multi-frequency operation.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115443"},"PeriodicalIF":2.0,"publicationDate":"2025-09-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145096617","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":"Public acceptance of fusion energy in Europe","authors":"Christian Oltra ,&nbsp;Alessio Giacometti ,&nbsp;Vanja Čok ,&nbsp;Giuseppe Pellegrini ,&nbsp;Gaston Meskens ,&nbsp;Catrinel Turcanu ,&nbsp;Zoltan Ferencz ,&nbsp;Piotr Stankiewicz ,&nbsp;Maria Teresa Orlando ,&nbsp;Chiara Bustreo","doi":"10.1016/j.fusengdes.2025.115430","DOIUrl":"10.1016/j.fusengdes.2025.115430","url":null,"abstract":"<div><div>This study examines public attitudes toward fusion energy in Europe through a comprehensive cross-national survey involving a sample of 19,144 respondents. Following a multidimensional analytical approach, we investigate the distribution of public attitudes, analyse predictive factors influencing support, and assess the impact of information provision on perception. Results reveal predominantly favourable attitudes toward fusion energy, with 57% of participants reporting positive perceptions, 58% expressing acceptance, and 53% supporting expansion following exposure to informational materials. Multiple regression analyses identify several significant predictors of support: pre-existing attitudes toward conventional nuclear power demonstrate substantial predictive influence, while affective responses and perceived environmental benefits emerge as critical determinants. Experimental manipulation of information provision produces statistically significant effects on attitudinal distributions, with recipients of detailed information on the technology's consequences demonstrating higher support (55.4% vs. 51.6%) compared to those receiving general information. More substantially, support increases significantly from baseline to post-information assessment (mean support on a 1–5 scale rose from <em>M</em> = 3.06 to <em>M</em> = 3.52). These findings illuminate the complex interplay of factors shaping public evaluations of fusion energy and carry implications for communication strategies and public engagement initiatives as the research on this technology progresses toward the commercialization phase.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115430"},"PeriodicalIF":2.0,"publicationDate":"2025-09-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145096712","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":"Fusion reactor manipulator coupling error analysis and virtual-real interaction control","authors":"Congju Zuo ,&nbsp;Pucheng Zhou ,&nbsp;Feng Wang ,&nbsp;Guodong Qin ,&nbsp;Shijie Liu ,&nbsp;Xiaoyan Qin ,&nbsp;Ruijuan Zhao ,&nbsp;Jing Yu ,&nbsp;Ling Ma ,&nbsp;Zhixin Yao","doi":"10.1016/j.fusengdes.2025.115441","DOIUrl":"10.1016/j.fusengdes.2025.115441","url":null,"abstract":"<div><div>This paper introduces a cross-platform virtual-real interaction control system architecture for enhancing the working accuracy and human-machine interaction performance of the fusion reactor manipulator (FRM) under extreme environments inside a fusion building. The FRM error model is established by combining the modified Denavit-Hartenberg parameters and the dynamic rigid-flexible coupling error analysis results. To present the intrinsic unobservable behaviors and characteristics (stress, strain, temperature, etc.) of FRM, a cross-platform virtual-real interaction control system architecture for FRM is constructed based on Unity 3D and digital twin technology. An algorithm development platform based on MATLAB/Simulink-ROS integration is proposed to facilitate the rapid verification and integration of new algorithms for FRM. A data fusion-based design method for the FRM morphology deformation prediction system is designed. Finally, a 1:6 scale FRM prototype system is developed, and the experimental results show that the maximum position error of the compensated FRM is &lt;1.2 mm, and the virtual-real follow mapping, and collision warning are realized.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115441"},"PeriodicalIF":2.0,"publicationDate":"2025-09-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145096713","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":"Study on acceptable air concentration limit in helium gas inside the test cell in fusion neutron source A-FNS","authors":"Shunsuke Kenjo ,&nbsp;Shogo Honda ,&nbsp;Hideya Nakanishi ,&nbsp;Saerom Kwon ,&nbsp;Makoto Oyaidzu ,&nbsp;Kentaro Ochiai ,&nbsp;Satoshi Sato ,&nbsp;Kai Masuda","doi":"10.1016/j.fusengdes.2025.115445","DOIUrl":"10.1016/j.fusengdes.2025.115445","url":null,"abstract":"<div><div>Fusion Neutron Source A-FNS, which accelerates a deuteron beam on a liquid lithium (Li) target, aims to acquire material properties under neutron irradiation—essential for the realization of the JApan’s DEMOnstration fusion reactor. Neutron irradiation is performed in a Test Cell (TC) surrounded by thick concrete shielding. Since the atmospheric condition inside the TC consists of helium gas at negative pressure, some air in-leakage into the TC is inevitable. In this study, we evaluated acceptable air concentrations in helium gas within the TC and air in-leak rates to prevent Li ignition and atmospheric activation. Based on our recent R&amp;D activity, we established an air concentration limit in helium gas as 5 vol.% to prevent Li ignition in the event of a Li leak. Air activation calculations using the FISPACT code reveal that the tritium production amount (2.8 × 10⁶ Bq/h) is the main contribution to the tritium inventory in the TC. This tritium is primarily produced via the ¹⁴N (n,t) reactions. The air in-leak rates were determined by modeling the helium purification process and developing start-up procedures for the liquid Li target system and TC. Based on these findings, we proposed the design requirements for the TC, interlock (Machine Protection System), and detritiation system in the circulating helium purifier.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115445"},"PeriodicalIF":2.0,"publicationDate":"2025-09-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145096673","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":"Online un-supervised tearing mode detection with sequentially discounting algorithms for JT-60SA","authors":"Tatsuya Yokoyama,&nbsp;Shizuo Inoue,&nbsp;Shinichiro Kojima,&nbsp;Takuma Wakatsuki,&nbsp;Maiko Yoshida","doi":"10.1016/j.fusengdes.2025.115440","DOIUrl":"10.1016/j.fusengdes.2025.115440","url":null,"abstract":"<div><div>A non-empirical tearing mode detector model based on statistical anomaly detection with sequentially discounting algorithms has been developed, and its prediction performance has been demonstrated with experiment data in the JT-60SA initial operation phase. Detection and prediction of the occurrence of disruptions is an important issue to protect the tokamak device from the damage caused by disruptions, and empirical models using machine learning techniques are being developed. A non-empirical model based on anomaly detection is one possible solution to an inherent problem of uncertainty as to whether such empirical models can be extrapolated to future tokamaks. The developed detector model has shown a good prediction performance, and its processing time was smaller than the control cycle time of the JT-60SA without any advanced devices such as GPUs. The result suggests that the statistical anomaly detection with sequentially discounting algorithms is a good choice to be implemented in the plasma controller not only in the JT-60SA but also in the future devices such as ITER and DEMO.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115440"},"PeriodicalIF":2.0,"publicationDate":"2025-09-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145096616","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":"EU ITER first wall panel CuCrZr material procurement and characterization","authors":"Margherita Sardo ,&nbsp;Samuli Heikkinen ,&nbsp;Jose Pacheco ,&nbsp;Emir Örer ,&nbsp;Taner Hergül ,&nbsp;Can Uzel Osman ,&nbsp;Hayao Eguchi ,&nbsp;Masato Arai ,&nbsp;Marta Freitas ,&nbsp;Nuno A. Marques ,&nbsp;Sergio A. Reis ,&nbsp;Mónica Mendes Reis","doi":"10.1016/j.fusengdes.2025.115417","DOIUrl":"10.1016/j.fusengdes.2025.115417","url":null,"abstract":"<div><div>Precipitation hardened CuCrZr is one of the materials for the ITER First Wall Panel (FWP) application. It is used as an intermediate layer between the stainless-steel structure and the W armour facing the plasma, with embedded water-cooling channels. Because of its high thermal conductivity combined with high strength this alloy is used as the FWP heatsink. Within the European Normal Heat Flux FWP, the three layers are joined by the Hot Isostatic Pressing (HIP) diffusion bonding process.</div><div>Past studies defined the optimum parameters for the CuCrZr material, considering the loads present on the ITER machine such as high thermo-mechanical stresses and fast neutron damage. Attention is given to material testing for mechanical properties at room and elevated temperature and microstructure to ensure compliant material of the EU FWP.</div><div>The comparison between real HIP sequence and HIP simulation on the resulting material properties demonstrates suitability of the approach.</div><div>The CuCrZr material produced has been used for the qualification of the HIP processes of the EU FWP, which increases the confidence on a successful FWP series production. This paper summarizes the EU FWP CuCrZr material’s mechanical and microstructural test results, obtained by the ISQ laboratory, showing compliance with ITER material requirements and a high consistency and coherence on the material properties along the production and among different material suppliers. Also, it provides an overview of the material quantities procured over the past years and the future needs for the EU FWP production.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115417"},"PeriodicalIF":2.0,"publicationDate":"2025-09-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145096675","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":"Assessment of the structural integrity of in-vessel ELM control coils located on the high field side of the TCABR tokamak","authors":"A.S. Bouzan ,&nbsp;R. Ramos Jr ,&nbsp;F.M. Salvador ,&nbsp;J.I. Elizondo ,&nbsp;G.P. Canal","doi":"10.1016/j.fusengdes.2025.115434","DOIUrl":"10.1016/j.fusengdes.2025.115434","url":null,"abstract":"<div><div>The use of Resonant Magnetic Perturbations (RMP) is a well-established technique to control Edge Localized Modes (ELM) in tokamak plasmas. Uncontrolled ELM instabilities can dissipate high energy fluxes that are not withstood by the most advanced materials. In-vessel RMP coils on the low field side (LFS) are usually employed to suppress/mitigate ELMs, but research indicates that applying RMP fields on the high field side (HFS) may improve ELM control. To investigate the effects of RMP fields on both sides, the Tokamak à Chauffage Alfvén Brésilien (TCABR) is being upgraded. Among the improvements, a set of 108 RMP coils will be installed inside the vacuum vessel: 54 coils on the LFS and 54 coils on the HFS. These coils will have to operate with both direct (up to 2<!--> <!-->kA) or alternating (up to 1<!--> <!-->kA) currents, high voltages (up to 4<!--> <!-->kV), and frequencies up to 10<!--> <!-->kHz. Consequently, high stress levels due to temperature gradients and electromagnetic loads act in the coils casing. This work presents structural analyses of the in-vessel coils that will be installed on the HFS, for operations in direct current. In these analyses, finite element simulations using the software ANSYS were carried out to evaluate the feasibility of installing this set of coils. The maximum stresses in the CP coil components were obtained and compared with the allowable stresses for each component, showing that the proposed set of CP coils can be safely installed and operated in TCABR.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115434"},"PeriodicalIF":2.0,"publicationDate":"2025-09-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145096672","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":"Status of design and manufacturing qualification activities of the first wall of the Divertor Tokamak test facility","authors":"M. Furno Palumbo ,&nbsp;S. Roccella ,&nbsp;G. De Sano ,&nbsp;R. De Luca ,&nbsp;M. Iafrati ,&nbsp;A. Tatì ,&nbsp;B. Riccardi ,&nbsp;D. Paoletti ,&nbsp;G.M. Polli","doi":"10.1016/j.fusengdes.2025.115435","DOIUrl":"10.1016/j.fusengdes.2025.115435","url":null,"abstract":"<div><div>This paper gives an overview of the current design of the First Wall (FW) of the Divertor Tokamak Test facility (DTT) under construction at Enea Research Centre of Frascati (Rome), as well as the qualification activities related to the manufacturing process of the FW small scale mock-ups.</div><div>The main goal of the overview is to illustrate the latest release of the FW component’s design, in accordance with many constraints stemming from the Physics and DTT system interface, at both Inboard (IFW) and Outboard (OFW) side of the DTT device.</div><div>Concerning the qualification activities related to the manufacturing of FW preliminary small-scale mock-ups, different technologies were compared. Regarding the OFW plasma facing units (PFUs), the machining and welding processes – TIG, Laser and Electron Beam (EB) – are investigated as conventional manufacturing solutions. The additive manufacturing technology of selective laser melting is considered a valuable procedure that makes a as the best compromise between the manufacturability, performance and costs. Regarding the IFW, the small-scale mock-ups to be manufactured and qualified concern the limiter module. It will be adopted, other than the standard one, to cope with plasma limited phases, i.e. when the plasma interacts with the inner wall. The limiter layout is presented with the aim of discussing its manufacturability and performances.</div><div>The qualification activities related to the Copper-Chromium-Zirconium (CuCrZr)-Inconel weldings, by means of EB, were also performed and are discussed in this paper, in order to manufacture the transitions – up to the steel lids – located at the ends of the limiter modules – nearby the divertor region.</div><div>For the manufacturing solutions, destructive and non-destructive tests have been carried out on the mock-ups to assess the feasibility of the technological processes, and the results are presented in this contribution.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115435"},"PeriodicalIF":2.0,"publicationDate":"2025-09-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145096674","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}