Fusion Engineering and Design最新文献

{"title":"Progress and results of the first high voltage vacuum insulation tests in MITICA","authors":"T. Patton ,&nbsp;G. Chitarin ,&nbsp;N. Pilan ,&nbsp;M. Agostini ,&nbsp;D. Aprile ,&nbsp;M. Boldrin ,&nbsp;V. Candeloro ,&nbsp;M. Dan ,&nbsp;S. Denizeau ,&nbsp;N. Marconato ,&nbsp;A. Rigoni ,&nbsp;G. Manduchi ,&nbsp;F. Santoro ,&nbsp;E. Spada ,&nbsp;C. Taliercio ,&nbsp;L. Trevisan ,&nbsp;M. Valente ,&nbsp;L. Zanotto ,&nbsp;P. Barbato ,&nbsp;M. Fincato ,&nbsp;M. Kashiwagi","doi":"10.1016/j.fusengdes.2025.115349","DOIUrl":"10.1016/j.fusengdes.2025.115349","url":null,"abstract":"<div><div>The Heating Neutral Beam injector (HNB) for ITER includes a Beam Source (BS) surrounded by a single vacuum gap, operating up to 1 MV total voltage. MITICA (Megavolt ITER Injector &amp; Concept Advancement) is a full-scale prototype of the ITER Heating Neutral Beams (HNBs), devoted to test and optimize the design, under construction in Padova at the Neutral Beam Test Facility (NBTF) hosted by the Consorzio RFX.</div><div>Recent experiments on HV bushing for MITICA and reduced-scale models at QST lab in Naka, Ibaraki, Japan, indicate that the breakdown probability of the HNB insulation might be critical.</div><div>As a risk-mitigation measure for the HNB operation, a specific high-voltage test campaign has been undertaken in the MITICA test bed at NBTF. Full-size \"mock-up electrodes\", reproducing the outer geometry of the MITICA/HNB accelerator are used, allowing swift implementation and test of different electrostatic configurations in realistic conditions.</div><div>The main objectives are: (1) to verify the performance of the vacuum electrode insulation in the present design and: (2) to assess the minimal set of necessary modifications, possibly including the introduction of an intermediate electrostatic shield. All tests are foreseen during the time window before the installation of the real beam source in the MITICA vacuum vessel.</div><div>The paper describes the test strategy and the ad-hoc development of diagnostics, including current sensors in vacuum, integrated video camera system and data acquisition network, devoted to identify the most critical regions where an insulation breakdown could occur inside the large vacuum vessel.</div><div>Then, the results of the first test campaigns are presented and discussed, in terms of maximum withstand voltage of the insulation, in relation to electrode geometry, applied voltage rise time and vacuum conditioning procedure.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115349"},"PeriodicalIF":1.9,"publicationDate":"2025-07-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144686902","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":"Design, commissioning, and first operation of the high-temperature superconducting tokamak Honghuang70","authors":"Z. Yang,&nbsp;Y.J. Cao,&nbsp;B. Chen,&nbsp;G.B. Chen,&nbsp;W.J. Chen,&nbsp;G. Dong,&nbsp;Y.Q. Du,&nbsp;H.Y. Guo,&nbsp;Y.X. Guo,&nbsp;Y. Hua,&nbsp;Y. Huang,&nbsp;Y.Y. Li,&nbsp;Z.Y. Li,&nbsp;J.H. Liu,&nbsp;J.Q. Ma,&nbsp;Z.C. Pan,&nbsp;H. Qiao,&nbsp;Y.Z. Wang,&nbsp;Q.Q. Wei,&nbsp;H.G. Yang,&nbsp;Y.J. Zhu","doi":"10.1016/j.fusengdes.2025.115341","DOIUrl":"10.1016/j.fusengdes.2025.115341","url":null,"abstract":"<div><div>Honghuang70 (HH70) is the world’s first fully high-temperature superconducting (HTS) tokamak. It is a medium-sized tokamak with modest aspect ratio, featuring a major radius of <em>R₀</em> = 0.7 m and a minor radius <em>a</em> = 0.25 - 0.3 m. At the designed coil operation temperature of 20 K, the maximum designed magnetic field on the magnet coils is <em>B_max</em> = 2.5 T, and the toroidal magnetic field at the plasma center <em>B₀</em> = 0.6 T. All of HH70’s coils including the central solenoid (CS), the poloidal field (PF) coils and the toroidal field (TF) coils are constructed with the rare-earth barium copper oxide (ReBCO) HTS tape as the main current-carrying component. The construction and assembly of HH70 were completed in 2024. The coil commissioning results show that the behavior of the HTS coils agrees with engineering simulation results. The integrated commissioning has verified the capability of the supporting subsystems. This paper reviews the design, assembly, commissioning and initial operation of the HH70 tokamak, including its HTS coils and main supporting systems. The successful operation of HH70 demonstrates the feasibility of full-HTS tokamaks and provides valuable engineering experience.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115341"},"PeriodicalIF":1.9,"publicationDate":"2025-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144679714","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":"Upgrade of the Diagnostic Neutral Beam Injector for the RFX-mod2 experiment","authors":"Marco Barbisan ,&nbsp;Marco Boldrin ,&nbsp;Luca Cinnirella ,&nbsp;Bruno Laterza ,&nbsp;Alberto Maistrello ,&nbsp;Lionello Marrelli ,&nbsp;Federico Molon ,&nbsp;Simone Peruzzo ,&nbsp;Cesare Taliercio ,&nbsp;Marco Valisa ,&nbsp;Enrico Zampiva","doi":"10.1016/j.fusengdes.2025.115320","DOIUrl":"10.1016/j.fusengdes.2025.115320","url":null,"abstract":"<div><div>Diagnostic Neutral Beam Injectors (DNBI), through the combined use of Charge Exchange Recombination Spectroscopy (CHERS) and Motional Stark effect diagnostics (MSE), are a well-known tool to access important information about magnetically confined plasmas, such as radial profiles of ion temperature, ion flow, impurity content and intensity and direction of the magnetic field. For this purpose, a DNBI was installed and operated in the RFX-mod experiment, which was designed to confine plasma mainly through the Reversed Field Pinch configuration. The DNBI, designed and built by the Budker Institute of Nuclear Physics (BINP), was based on a source of positive hydrogen ions, accelerated to 50 keV and for a maximum ion current of 5 A. The beam could be modulated and the maximum overall duration was 50 ms.</div><div>With the upgrade of RFX-mod to the present RFX-mod2 machine, the DNBI is being renovated to solve several power units faults and improve the overall reliability of the system. The 50 kV power supply is being improved, as well as the power supplies in the high voltage deck and its insulation transformer. Magnetic field survival tests were performed on the toroidal-core-based DC–DC converters that should power the electronic boards in a reliable way. The control system, originally based on CAMAC technology, was redesigned to be fully replaced. This contribution reviews the technical criticalities emerged in the DNBI check-up and the new solutions adopted to make the DNBI operative and more reliable.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115320"},"PeriodicalIF":1.9,"publicationDate":"2025-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144679713","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":"On the potential and limitations of Bayesian ensemble algorithms for the decomposition of time series generated by tokamak diagnostics","authors":"Michela Gelfusa ,&nbsp;Teddy Craciunescu ,&nbsp;Riccardo Rossi ,&nbsp;Andrea Murari ,&nbsp;JET Contributors ,&nbsp;the EUROfusion Tokamak Exploitation Team","doi":"10.1016/j.fusengdes.2025.115318","DOIUrl":"10.1016/j.fusengdes.2025.115318","url":null,"abstract":"<div><div>The vast majority of signals generated by tokamak diagnostics are in the form of time series. Consequently dealing with time-indexed data is a major task, to be tackled daily by both experimentalists and analysts. Decomposing a time series in terms of seasonal components, trends, change-points and noise is therefore a crucial activity, per se and as a preliminary step to further investigations. In the present work, the Bayesian ensemble approach to model decomposition of time series, originally developed for remote sensing of the earth, is applied to various global measurements routinely available in tokamak devices. Among the competitive advantages of the methodology, particularly relevant are its holistic view of the data and the independence from the details of the statistical algorithms and models. The potential of the technique, implemented by the BEAST code, has been assessed with both synthetic signals and experimental data. The approach proves to be very reliable in modelling trends and determining the time locations of abrupt changes even of strongly oscillatory components, such as ELMs and sawteeth. Deployment to assess small drifts confirms the lack of stationarity in tokamak high performance discharges. The difficulties of modelling the details of the sawteeth and irregular ELMs indicate the need to improve the method to deal with seasonal components of complex harmonic content and/or varying frequency. However, the available routines are already very effective in determining the times changes in the ELM regimes.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115318"},"PeriodicalIF":1.9,"publicationDate":"2025-07-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144679770","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":"New progress on a compact deuterium-deuterium neutron generator based on RF ion source","authors":"Zhenqing Zhu ,&nbsp;Yuzhong Qian ,&nbsp;Mengmeng Li ,&nbsp;Xin Tao ,&nbsp;Zhi Dou ,&nbsp;Bing Hong ,&nbsp;Renli Zhu ,&nbsp;Wei Xu ,&nbsp;Lizhen Liang ,&nbsp;Chundong Hu","doi":"10.1016/j.fusengdes.2025.115353","DOIUrl":"10.1016/j.fusengdes.2025.115353","url":null,"abstract":"<div><div>This article presents a systematic optimization of a compact deuterium-deuterium neutron generator based on a RF ion source, significantly increasing the neutron yield by 6 times to 6.46 × 10⁹ n/s. The designed device employs a concave high-voltage vacuum feedthrough, increasing the overall breakdown strength of the device to 150 kV. Additionally, to improve the ion current extracted, an innovative ‘diffusion-type’ plasma chamber has been adopted, achieving an increase of over 20 % in beam extraction. Furthermore, it has been verified that under high thermal load conditions, the performance of the scandium target is superior to that of the titanium target, primarily due to the higher desorption temperature of deuterium from scandium compared to titanium. Finally, a stable neutron yield of over 5 × 10⁹ n/s was achieved, with an effective operating time exceeding 98 %. This result provides a solid technical foundation for further improving neutron imaging quality.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115353"},"PeriodicalIF":1.9,"publicationDate":"2025-07-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144679771","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":"Exploring the stability of blanket pebble bed with plasma events","authors":"Qigang Wu ,&nbsp;Mingzhun Lei ,&nbsp;Pinghui Zhao ,&nbsp;Zhao Liu ,&nbsp;Weibin Xi","doi":"10.1016/j.fusengdes.2025.115354","DOIUrl":"10.1016/j.fusengdes.2025.115354","url":null,"abstract":"<div><div>Plasma control instability is one of the inherent challenges in fusion reactors. Pebble beds, composed of assembled particles, are employed in blanket models to achieve neutron multiplication and tritium breeding using different materials. However, electromagnetic (EM) forces induced by plasma events can disturb the pebble bed, potentially altering its internal structure and the initial packing characteristics. These structural changes can significantly affect the physical properties and stability of the pebble beds. Despite its importance, studies investigating the structural behavior of pebble beds under the influence of EM force disturbances remain limited. This paper investigates the structural evolution of the Be pebble beds under the EM force perturbations in the fusion reactors. Using a coupled approach of Finite Element Analysis (FEA) and Discrete Element Method (DEM), the multiscale characteristics of the pebble bed are analyzed at mesoscopic and microscopic levels. Key factors, including the local packing factor, particle slip, force transmission, force chains, fabric anisotropy, wall forces, and energy dissipation, are systematically evaluated. The results indicate that EM force generated during plasma instability events significantly influence the pebble bed structure. EM force perturbations notably affect particle slip, fabric anisotropy, wall forces, and local packing factors, while the changes for the force chains are minimal. The force transmission within the pebble bed primarily aligns with the direction of the applied EM force. Additionally, the perturbation energy is mainly dissipated as frictional and strain energy. These findings provide valuable insights into the structural evolution of pebble beds under EM disturbances, offering guidance for improving the design and structural stability of pebble beds in fusion reactors.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115354"},"PeriodicalIF":1.9,"publicationDate":"2025-07-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144679772","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":"Haptic master arm development for tele-manipulation in tokamak like challenging environments","authors":"Naveen Rastogi ,&nbsp;Suryakant Gupta ,&nbsp;Krishan Kumar Gotewal","doi":"10.1016/j.fusengdes.2025.115355","DOIUrl":"10.1016/j.fusengdes.2025.115355","url":null,"abstract":"<div><div>This paper presents the development and implementation of a haptic master arm designed for tele-manipulation tasks within the highly restrictive environment of a tokamak. The haptic arm is engineered to enable precise remote handling by mimicking natural arm movements, addressing the unique challenges posed by the tokamak's complex geometry and hazardous conditions. Key aspects of the mechanical design, control architecture, and system integration are detailed, with emphasis on the requirements for the teleoperation in the challenging environments. A comprehensive kinematic model is derived to calculate the arm motion and to ensure accurate end-effector positioning. Additionally, a prototype gravity compensation mechanism is developed and validated to improve operator comfort and reduce fatigue during extended operation. Experimental results demonstrate the arm's accuracy, intuitive control, and potential for remote maintenance applications in fusion research environments. The findings from this work help improve haptic feedback and remote control systems, making them more effective for use in challenging or narrow environments</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115355"},"PeriodicalIF":1.9,"publicationDate":"2025-07-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144679773","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":"Interactions between alloying elements Ti/Al/Y and oxygen impurities in vanadium alloy: A first-principles study","authors":"Jingyuan Wang ,&nbsp;Mingliang Wei ,&nbsp;Pengbo Zhang ,&nbsp;Yichao Wang","doi":"10.1016/j.fusengdes.2025.115352","DOIUrl":"10.1016/j.fusengdes.2025.115352","url":null,"abstract":"<div><div>Low-activation vanadium alloy is a promising candidate structural material for fusion reactors. In this paper, we investigated the interactions of substitutional Ti/Al/Y atoms with oxygen (O) impurities and the stabilities of small-sized oxide clusters in vanadium alloy by first-principles calculations. The results showed that the presence of Ti/Y reduces the solution energy of O while Al increases it, O atom still prefers to occupy octahedral interstitial sites. The interactions of Ti−O and Y−O pairs are attractive with 0.34 and 0.50 eV respectively, while Al repels O (–0.64 eV). The stronger Y−O attraction means that Y additions hinder the aggregation of O and Ti into larger Ti−O complexes. Moreover, we determined the stability of Ti<em>_m</em>O<em>_n</em> and Y<em>_m</em>O<em>_n</em> clusters with the size (<em>m, n</em>=1∼4), the Y<em>_m</em>O<em>_n</em> clusters are more stable than Ti<em>_m</em>O<em>_n</em> clusters for the same size. Single Ti (Y) atom can attract three (over four) O atoms. The stability of these clusters mainly depends on the configuration and the <em>m/n</em> ratio. These findings provide a deeper understanding of solute−O interactions in vanadium alloys.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115352"},"PeriodicalIF":1.9,"publicationDate":"2025-07-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144665913","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":"Advancements in central control for IFMIF-DONES: Integrating CODAC, MPS, and SCS into a unified control framework","authors":"M. Cappelli ,&nbsp;F. Ambi ,&nbsp;E. Botta ,&nbsp;J. Cruz ,&nbsp;J. Diaz ,&nbsp;Z. Chen ,&nbsp;D. Dwojewski ,&nbsp;M. Giacchini ,&nbsp;V. Gutierrez ,&nbsp;R. Lorenzo ,&nbsp;M. Montis ,&nbsp;J. Sousa ,&nbsp;A. Ibarra","doi":"10.1016/j.fusengdes.2025.115345","DOIUrl":"10.1016/j.fusengdes.2025.115345","url":null,"abstract":"<div><div>The International Fusion Materials Irradiation Facility-DEMO<img>Oriented NEutron Source (IFMIF-DONES) represents a cutting-edge accelerator-based neutron source designed to produce high-energy neutrons for the irradiation of materials intended for use in DEMO, the future fusion reactor. Given the complexity of such a facility, a robust central control system is indispensable to ensure safe supervision and management of all operations. This paper provides an overview of recent advancements in the design of the Central Instrumentation and Control Systems (CICS) for IFMIF-DONES, focusing on the transition to the definition design phase. Employing a distributed approach, the architecture utilizes fast devices and dedicated networks for real-time communication among control units. This paper outlines the current status of the design for each CICS system and discusses existing and future plans for their integration into a unified control framework. The ongoing effort to integrate all CICS systems into a cohesive framework faces various challenges, such as data acquisition synchronization and interlock management. The integration of subsystems within CICS may be powerfully enhanced using artificial intelligence tools by enabling data-driven decision-making, proactive maintenance, adaptive control, and intelligent optimization.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115345"},"PeriodicalIF":1.9,"publicationDate":"2025-07-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144663187","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":"Joining and characterization of SPTAs/V/CLAM steel joints using SPDB technique with different current directions","authors":"Xiaoyue Tan ,&nbsp;Chenjun Xu ,&nbsp;Weihong Liu ,&nbsp;Yuming Chen ,&nbsp;Qingbo Tu ,&nbsp;Andrey Litnovsky ,&nbsp;Laima Luo ,&nbsp;Yucheng Wu","doi":"10.1016/j.fusengdes.2025.115350","DOIUrl":"10.1016/j.fusengdes.2025.115350","url":null,"abstract":"<div><div>Joining the dissimilar materials faces great challenge due to their different physical and chemical performances. In this study, the SPTAs/V/CLAM steel joints were produced by the spark plasma diffusion bonding (SPDB) technique. Investigation of the roles of current direction on the atomic diffusion behavior at interfaces by a scanning electron microscopy and an equipped energy dispersive spectrometer. It is found that the thickness of the diffusion layer at the SPTAs/V interface is independent on the current direction. However, there shows a thicker diffusion layer (σ and vanadium carbide phases) at the V/CLAM steel interface when the current flows through from CLAM steel side to SPTAs side. It is owing to the direction of the electron wind force coincides with the diffusion direction of dominated atom (V). The produced SPTAs/V/CLAM steel joints show good shear strength (201±24 MPa) and thermal cycling performance (35 cycles). In addition, a skillful method was proposed to quantify the directional effect of current on the interdiffusion between Fe and V, accounting for 36.7 %. This study provides a practical and theoretical support on joining dissimilar materials by designing current direction using SPDB technique.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"220 ","pages":"Article 115350"},"PeriodicalIF":1.9,"publicationDate":"2025-07-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144654006","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}