Fusion Engineering and Design最新文献

{"title":"Multiphysical modelling of superconducting coil discharge through varistors","authors":"T. Galvin ,&nbsp;A. Lampasi ,&nbsp;R. Bonifetto ,&nbsp;M. De Bastiani","doi":"10.1016/j.fusengdes.2025.115048","DOIUrl":"10.1016/j.fusengdes.2025.115048","url":null,"abstract":"<div><div>High-energy silicon-carbide (SiC) varistors will be used as quench protection and energy extraction for the toroidal field (TF) coils of the Divertor Tokamak Test (DTT) facility, as well as the Frascati Coil Cold Test Facility (FCCTF). As varistors have a nonlinear voltage/current response, which is also temperature dependent, multiphysical modelling is required to determine the maximum coil hot-spot temperature during a quench. This paper presents both electrical and thermal-hydraulic modelling of a coil discharge through the varistors, compared to an equivalent linear resistor array. For a single Toroidal Field Coil (TFC), tested in the FCCTF, the varistors discharge the current approximately 10 s faster than linear resistors, resulting in a reduction of the maximum coil hot-spot temperature of 10 K. In DTT with 18 TF coils and 3 discharge assemblies, varistors reduce the discharge time and maximum coil hot-spot temperature by approximately 20 s and 25 K, respectively.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115048"},"PeriodicalIF":1.9,"publicationDate":"2025-04-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143808792","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":"Mechanism of nanocracks formation in tungsten and tungsten-nickel-iron alloy under helium ion irradiation","authors":"Haiyu Xue ,&nbsp;Te Zhu ,&nbsp;Xiangming Xie ,&nbsp;Qigui Yang ,&nbsp;Peng Zhang ,&nbsp;Baoyi Wang ,&nbsp;Pinjing Cheng ,&nbsp;Xingzhong Cao ,&nbsp;Haibiao Wu","doi":"10.1016/j.fusengdes.2025.115037","DOIUrl":"10.1016/j.fusengdes.2025.115037","url":null,"abstract":"<div><div>Plasma-facing materials used in fusion energy facilities, such as pure tungsten (W) and tungsten-nickel-iron (W-Ni-Fe) alloys, must withstand helium irradiation, which can lead to nanocrack that eventually develop into surface blistering and large-size crack. The mechanisms behind this phenomenon remain elusive, highlighting the need for a detailed investigation. This study employed positron annihilation spectroscopy (PAS) and transmission electron microscopy (TEM) to analyze the development of nanocracks. The results elucidate that helium irradiation initially engenders vacancy-type defects within the material matrix. As the irradiation dose escalates, implanted helium atoms are captured by these vacancies, leading to the formation of helium-vacancy complexes that subsequently expand into larger aggregates and eventually evolve into helium bubbles. The coalescence of these bubbles results in the generation of high-pressure helium entities, which precipitate nanocrack formation once the internal pressure surpasses the structural limits of the material, ultimately culminating in surface blistering.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115037"},"PeriodicalIF":1.9,"publicationDate":"2025-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143799761","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":"Final implementation of the new upper divertor with coils in ASDEX Upgrade","authors":"I. Zammuto ,&nbsp;A. Herrmann ,&nbsp;M. Weißgerber ,&nbsp;W. Zeidner ,&nbsp;N. Arden ,&nbsp;N. Berger ,&nbsp;V. Brack ,&nbsp;T. Lunt ,&nbsp;B. Petzold ,&nbsp;V. Rohde ,&nbsp;G. Schall ,&nbsp;M. Teschke ,&nbsp;T. Vierle ,&nbsp;S. Vorbrugg ,&nbsp;Paolo Badino ,&nbsp;Marco Dani","doi":"10.1016/j.fusengdes.2025.115028","DOIUrl":"10.1016/j.fusengdes.2025.115028","url":null,"abstract":"<div><div>Theoretical investigations into detachment mechanisms have emphasized the potential of addressing the power exhaust challenge through alternative divertor configurations, such as the Snowflake and X-Divertor concepts. These configurations are realized by integrating two coils positioned along the outer strike line of the upper divertor. This concept is set to be tested soon at ASDEX Upgrade (AUG), a mid-sized tokamak located in Garching. Since August 2022, AUG has been undergoing a maintenance phase to facilitate various tasks, including the installation of novel components such as the upper divertor equipped with cryopump, inner and outer divertor modules, and notably, two concentric coils, each capable of carrying a current of 52 kAt.</div><div>The coil conductor design has been specifically tailored to meet these requirements. It features a hollow copper conductor with an internal water-cooling channel, surrounded by electrical insulation made of Tefzel—a fluorine-based polymer—and encased in a stainless-steel jacket. This design ensures compatibility with the stringent ultra-high vacuum (UHV) conditions of the vacuum vessel while also providing protection against electrical faults. Extensive electrical and thermal testing of the conductor has been carried out in recent years to validate its performance.</div><div>A distinctive feature of these coils is their construction from a single, continuous length of conductor, eliminating internal electrical joints to reduce the risk of failures. However, this design approach required a significant effort to wind the coils within the highly constrained space of the AUG vacuum vessel. A sophisticated bending procedure, supported by in-house-developed tools, was devised to address the spatial limitations and meet the required precision.</div><div>Following an extensive testing phase using a custom-built mock-up, the two coils were successfully bent and installed within the AUG vacuum vessel, integrating seamlessly into the new upper divertor structure. This paper provides a detailed overview of the project's main components, its current status, and the critical assembly phases involved.</div><div>Index Terms— ASDEX Upgrade, Divertor, In-vessel coils Snowflake divertor; advanced divertor configuration.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 115028"},"PeriodicalIF":1.9,"publicationDate":"2025-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143808213","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":"Insight into the structural integrity assessment of the European DEMO fusion reactor divertor (Part II: Application examples)","authors":"M. Muscat ,&nbsp;P. Mollicone ,&nbsp;N. Mantel ,&nbsp;J.H. You ,&nbsp;C. Carrelli ,&nbsp;A. Aleksa ,&nbsp;J. Hess","doi":"10.1016/j.fusengdes.2025.115046","DOIUrl":"10.1016/j.fusengdes.2025.115046","url":null,"abstract":"<div><div>The DEMO fusion reactor Divertor design group within the EUROfusion consortium use RCC-MRx as the main analysis code for the Divertor's structural integrity assessment. Analysis has been carried out within the same group using an in-house developed Finite Element Analysis post processing script which follows the Design by Elastic Analysis rules of RCC MRx. A number of stress classification lines (SCLs) were placed in the Divertor component regions which are susceptible to Type P and Type S damage. This paper focuses on two of these stress classification lines. One is located in the region of a stress singularity while the other is in a region of high stress where the temperature is above the creep threshold along part of the SCL. Design by Analysis was performed using a spreadsheet application. The purpose was to highlight difficulties encountered in using the RCC-MRx elastic design methodology applied to the DEMO divertor. Issues mainly arose because of stress singularities in the geometry, because of the inherent non-axisymmetric geometry and loading of the divertor and because of limited material data for Eurofer97 steel which is the main material used for the DEMO Divertor. This paper is Part II of a companion paper and compliments it by considering the two SCLs as application examples and case studies. In the companion paper (Part I), general discussions on the difficulties and issues encountered are presented including some theoretical background on the phenomenon of elastic follow up and on Neuber's hyperbola rule that addresses plasticity and stress relaxation. An additional outcome of this work emphasises the need to further develop the in-house Finite Element Analysis post processing script and to incorporate within it best practice in implementing the RCC-MRx Design by Elastic Analysis rules for the Divertor components. The post processing tool development would improve the assessment reliability and productivity in order to suggest timely Divertor design modifications.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 115046"},"PeriodicalIF":1.9,"publicationDate":"2025-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143808214","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 updates of a fusion superconducting conductor test facility magnet, SUCCEX","authors":"Hyun Wook Kim ,&nbsp;Hyunjung Lee ,&nbsp;Soo-Hyeon Park ,&nbsp;Yong Chu ,&nbsp;Mu-yong Kim ,&nbsp;Seokho Nam ,&nbsp;Young Min Park ,&nbsp;Young-Ju Lee ,&nbsp;Jinhwan Kim ,&nbsp;Byung Su Lim ,&nbsp;Keeman Kim","doi":"10.1016/j.fusengdes.2025.115040","DOIUrl":"10.1016/j.fusengdes.2025.115040","url":null,"abstract":"<div><div>The superconductor test facility, named SUperConducting Conductor Experiment (SUCCEX), is being designed since 2014 and the Korean government has lunched the official project in 2021. The SUCCEX magnet is being developed to evaluate superconducting Cable-in-Conduit Conductor (CICC) samples for the future fusion magnets. This split-pair solenoid magnet system is designed to generate magnetic fields over 15 T in a 600 mm diameter bore, with capability to test SULTAN-like conductor samples. The magnet consists of two types of coils: a high-field inner coil (IC) using high-performance Nb₃Sn strands (Jc ∼1000 A/mm² at 4.2 K, 16 T) and a low-field outer coil (OC) using ITER-grade Nb₃Sn strands (Jc &gt;1000 A/mm² at 4.2 K, 12 T). Operating at 24.8 kA, the magnet achieves a background field of 15.4 T, enabling sample testing about 16 T when combined with sample's self-field. This paper presents recent conceptual design updates of the SUCCEX magnet, specifically focusing on the modification of the inner coil (IC) jacket thickness from 4 mm to 5 mm. The modification aims to enhance the structural integrity of the high-field conductor while maintaining the magnet's overall performance characteristics.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 115040"},"PeriodicalIF":1.9,"publicationDate":"2025-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143808218","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":"Preliminary design of the remote handling system for the ITER vacuum vessel pressure suppression system","authors":"Taku Yokoyama ,&nbsp;Chang-Hwan Choi ,&nbsp;Shanshuang Shi ,&nbsp;Gong Zheng ,&nbsp;David Hamilton ,&nbsp;Jinwook Kim ,&nbsp;Jim Palmer ,&nbsp;Garin Schoonhoven ,&nbsp;Paul Talbot ,&nbsp;Francesco Becchi","doi":"10.1016/j.fusengdes.2025.114994","DOIUrl":"10.1016/j.fusengdes.2025.114994","url":null,"abstract":"<div><div>The Vacuum Vessel Pressure Suppression System Remote Handling Equipment (VVPSS RHE) is being developed for remote maintenance of VVPSS components, including the Rupture Disc Assembly (RDA), Bleed Line Valve Assembly (BLVA), Support Trolley and relief lines within the Neutral Beam (NB) cell. It works in conjunction with the Neutral Beam Remote Handling System (NBRHS), including the Monorail Crane System (MCS) and Beam Line Transporter (BLT) manipulator. The main functions of the VVPSS RHE are to disconnect and reconnect bolted flanges, limit the spread of contamination and clean relief lines to reduce internal contamination and radiation levels in the NB cell. This paper describes the remote handling (RH) interfaces and the preliminary design of the VVPSS RHE, which demonstrate the feasibility of maintenance operations within the constrained NB cell environment and the capability of the NBRHS.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114994"},"PeriodicalIF":1.9,"publicationDate":"2025-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143808208","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":"Comparative analysis of the electromagnetic loads acting on the EU-DEMO divertor with alternative material options","authors":"Gennaro Di Mambro ,&nbsp;Antonio Maffucci ,&nbsp;Giuseppe Mazzone ,&nbsp;Jeong-Ha You ,&nbsp;Salvatore Ventre ,&nbsp;Fabio Villone","doi":"10.1016/j.fusengdes.2025.115024","DOIUrl":"10.1016/j.fusengdes.2025.115024","url":null,"abstract":"<div><div>This study is focused on the computation of the electromagnetic (EM) loads acting on the divertor of the EU- DEMO tokamak, related to the transients associated to plasma disruptions and to the ferromagnetic effects due to the use of materials with magnetic properties (EUROFER97). Specifically, plasma disruption events result in transient eddy and halo currents flowing into the divertor, which is then subjected to loads due to the interaction of the magnetic fields with these currents. This problem is here analyzed by using an Ansys- EMAG 3D magneto-quasi-static model simulating a toroidal sector of the tokamak that includes three divertors accurately detailed in their geometric features, and the main external components, such as blankets and vessel, described with a coarser definition. Equivalent current sources are used to impose the excitations associated to the considered conditions. The ferromagnetic effects are instead computed by using an Ansys- Maxwell magneto-static model, in which the EM loads are associated to the interaction between the magnetization of the ferromagnetic components and the known equilibrium magnetic field.</div><div>The paper carries out a comparative analysis on the EM loads associated with different design options in terms of material choices for some components: (i) vertical targets support made of AISI 316 SS, EUROFER97 or CuCrZr; (ii) pipe manifolds and supports of the cooling system made of AISI 316 SS or EUROFER97; (iii) PFC tubes and manifolds insulated or not with respect to the vertical targets support; (iv) main tubes and supports insulated or not with respect to the cassette. The impact of these choices on the estimated value of the forces and moments acting on the divertor is discussed.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 115024"},"PeriodicalIF":1.9,"publicationDate":"2025-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143808211","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 KSTAR Nb3Sn superconducting magnet property after long term operation since 2008","authors":"Hyun Jung Lee,&nbsp;Mu Yong Kim,&nbsp;Young Min Park,&nbsp;Giil Kwon,&nbsp;Hyun Wook Kim,&nbsp;Si-Woo Yoon","doi":"10.1016/j.fusengdes.2025.115020","DOIUrl":"10.1016/j.fusengdes.2025.115020","url":null,"abstract":"<div><div>KSTAR has been operated using Nb₃Sn superconducting magnets since 2008, which are capable of generating high magnetic fields and are ideal for high-performance plasma research. The KSTAR PF superconducting magnets have undergone repeated thermal cycling over many campaigns (16 cycles) and have been subjected to significant mechanical and thermal stress during over 30,000 plasma experiments conducted in pulse mode. To monitor any changes, a performance test is conducted on the PF1UL magnets before each campaign. These tests annually apply 4 kA and 15 kA currents, with heat generation steadily decreasing until 2024, where it has now stabilized. The KSTAR PF coils were designed to handle up to 25 kA. However, they typically operate in the range of ± 15 kA during the plasma experiments. In 2012, a 25 kA current test was conducted for the first time following the upgrade of the magnet power supply and the motor generator. Subsequently, a second 25 kA evaluation was performed in 2024 to investigate potential degradation of superconducting magnet. In this paper, we compare the thermal load on the PF1UL magnet at 25 kA charging current between 2012 and 2024 and analyze AC losses to confirm changes in its properties.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 115020"},"PeriodicalIF":1.9,"publicationDate":"2025-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143808278","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":"Integration studies of a positive neutral beam injector system into the design of a volumetric neutron source","authors":"T. Franke ,&nbsp;C. Bachmann ,&nbsp;V. Claps ,&nbsp;A. Doering ,&nbsp;T. Fellinger ,&nbsp;C. Gliss ,&nbsp;T. Haertl ,&nbsp;C. Hopf ,&nbsp;M. Kannamüller ,&nbsp;D. Leichtle ,&nbsp;R. Mozzillo ,&nbsp;J. Hun Park ,&nbsp;P. Pereslavtsev ,&nbsp;R. Riedl ,&nbsp;M. Siccinio ,&nbsp;A. Valentine","doi":"10.1016/j.fusengdes.2025.115035","DOIUrl":"10.1016/j.fusengdes.2025.115035","url":null,"abstract":"<div><div>A feasibility study regarding a volumetric neutron source (VNS) is presently conducted in the EUROfusion Consortium. The VNS uses Positive Neutral Beam Injection (P-NBI) for plasma heating, current drive and particularly to drive beam-target fusion, aiming for a high neutron production (<span><math><mo>≈</mo></math></span>0.5 MW/m² neutron wall load in the equatorial plane). P-NBI is a reliable auxiliary heating system, widely employed in plasma devices such as ASDEX Upgrade (AUG), W7-X and JT60-SA.</div><div>The paper describes the integration of the P-NBI system into the design of the VNS. This includes the neutral beam (NB) duct from the torus vacuum vessel to the NBI box with the gate valves, the space requirements of the NB injectors in the building as well as the connections for cooling water, cryo-supplies, electrical high voltage and radio frequency (RF) cable connections. Since the VNS is a nuclear machine with lifetime doses significantly exceeding those of ITER, the requirements for remote maintenance (RM) are very different from any existing NBI design. The RM concept and the RM sequences will be discussed.</div><div>Neutronics studies for the NB duct were performed and design iterations undertaken to assure that neutron heating and lifetime fluences remain below limits at the superconducting toroidal and poloidal field coils adjacent to the NB duct.</div><div>The work considers the return of experience from AUG, ITER and some other fusion experimental machines in operation, under construction or in conceptual design such as DEMO.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 115035"},"PeriodicalIF":1.9,"publicationDate":"2025-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143808215","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":"Characterization of water adsorption capacity at high pressure of the molecular sieve proposed to be used in TER RMSB","authors":"George Ana,&nbsp;George Bulubasa,&nbsp;Alina Niculescu,&nbsp;Maria Craciun,&nbsp;Ciprian Bucur,&nbsp;Iuliana Stefan","doi":"10.1016/j.fusengdes.2025.115039","DOIUrl":"10.1016/j.fusengdes.2025.115039","url":null,"abstract":"<div><div>This study investigates the effects of total pressure and superficial velocity of purge gas on the adsorption capacity of Na-Y zeolite, a candidate material for the Tritium Extraction and Recovery (TER) system in the Helium Cooled Pebble Bed (HCPB) breeding blanket. The TER system captures tritiated water vapor from helium purge gas at intended high pressure (8 MPa) to reduce pressure differentials with the cooling gas and enhance system resilience. Experimental data reveal that, while total pressure increases marginally enhance adsorption capacity, higher purge gas velocities reduce it. Adsorption isotherms were evaluated using Langmuir, Sips, and Freundlich models, with the Sips model providing the closest fit to experimental data. Mass transfer zone (MTZ) analysis indicates a stable MTZ shape along the test bed, supporting scalability of the findings for larger TER systems. Calculated utilization factors remain around 0.93–0.94 across tested pressures but decrease with increasing superficial velocity, further informing optimal operational parameters for effective adsorption and scalability in full-scale equipment.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 115039"},"PeriodicalIF":1.9,"publicationDate":"2025-04-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143808216","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}