Fusion Engineering and Design最新文献

{"title":"Experimental study on the critical current in highly flexible REBCO cables under copper tube compaction","authors":"Haihong Liu ,&nbsp;Huan Jin ,&nbsp;Guanyu Xiao ,&nbsp;Le wang ,&nbsp;Yongsheng Wu ,&nbsp;Fang Liu ,&nbsp;Chao Zhou ,&nbsp;Xiaochuan Liu ,&nbsp;Jinggang Qin","doi":"10.1016/j.fusengdes.2024.114707","DOIUrl":"10.1016/j.fusengdes.2024.114707","url":null,"abstract":"<div><div>The Institute of Plasma Physics Chinese Academy of Sciences (ASIPP) is developing the high-current REBCO cable-in-conduit conductor (CICC) for use in the Central Solenoid (CS) coil of the next generation nuclear fusion device. The aim is to develop a CICC comprising six REBCO sub-cables to satisfy the requirements of operation with a current of around 46 kA and a peak field of up to 20 T. Sub-cables, as crucial components within CICCs, play a pivotal role in ensuring the mechanical support strength and current-carrying stability of the entire CS coil system. Therefore, a process was developed in this paper for the first time to make a sub-cable that meets the requirements by inserting the Highly Flexible REBCO Cable (HFRC) cable into a copper tube and compacting it. Meanwhile, the feasibility and reliability of this process were evaluated and optimized using experimental methods at 77 K and self-field. The result indicated that sub-cables without copper tape protection experienced a 25.42% degradation in critical current (<em>I_C</em>). In contrast, when at least one protective layer of copper tape was used as a protective buffer between the HFRC cable and the inner wall of the copper tube, the <em>I_C</em> remained stable within a 1% error margin after compaction. These findings demonstrate the feasibility of this sub-cable preparation process. Meanwhile, this compaction method provides a solid process foundation for the development of full-size conductors in future magnet applications.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-11-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142571253","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":"Direct internal recycling fractions approaching unity","authors":"Chao Li ,&nbsp;J. Douglas Way ,&nbsp;Thomas F. Fuerst ,&nbsp;Colin A. Wolden","doi":"10.1016/j.fusengdes.2024.114705","DOIUrl":"10.1016/j.fusengdes.2024.114705","url":null,"abstract":"<div><div>Direct internal recycling (DIR) refers to the process of recovering pure hydrogen isotopes (D/T) from helium and other impurities in the fusion plasma exhaust and directing them back to the fuel injection system. Increasing the exhaust fraction purified through DIR significantly reduces the size and cost of the tritium plant and provides additional benefits including reduced requirements for both the tritium startup inventory and tritium breeding ratio. Metal foil pumps (MFPs) are the dominant technology for this separation, relying on the concept of superpermeation. We recently demonstrated that PdCu foils operated at low temperature provide both exceptional flux and resilience to helium absorption as the DIR fraction is increased. Herein we design and demonstrate continuous and semi-batch DIR processes using PdCu MFPs. Under continuous processing, stable performance was observed for DIR fractions up to 92 %. In addition, we demonstrate a semi-batch process capable of extending the DIR fraction to unity (&gt; 99.8 %). Under the experimental conditions described within a PdCu MFP area of ∼22 m² would be sufficient to process the fusion exhaust with 92 % DIR fraction at expected flowrates of 100 Pa·m³·<em>s</em>⁻¹ for a future fusion power plant.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-11-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142571252","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":"Parametric study of liquid metal flows in conducting circular ducts in a strong nonuniform magnetic field","authors":"S. Molokov ,&nbsp;G. Politis","doi":"10.1016/j.fusengdes.2024.114688","DOIUrl":"10.1016/j.fusengdes.2024.114688","url":null,"abstract":"<div><div>Parametric study of main flow characteristics in magnetohydrodynamic flow in the exit duct from a liquid metal blanket has been performed. The flow in such a duct occurs in a nonuniform, decreasing magnetic field. The duct wall is electrically conducting. The wall conductance ratio, <span><math><mi>c</mi></math></span>, and the gradient of the field, <span><math><mi>γ</mi></math></span>, have been varied in a wide range, <span><math><mrow><mn>0</mn><mo>.</mo><mn>01</mn><mo>≤</mo><mi>c</mi><mo>≤</mo><mn>0</mn><mo>.</mo><mn>5</mn></mrow></math></span> and <span><math><mrow><mn>0</mn><mo>.</mo><mn>3</mn><mo>≤</mo><mi>γ</mi><mo>≤</mo><mn>0</mn><mo>.</mo><mn>8</mn></mrow></math></span> covering most of the cases relevant to fusion. The studies have been performed with asymptotic methods for high values of the Hartmann number and interaction parameter, as well as with FLUENT. Pressure drop correlation has been developed, which is important for blanket design. The results show a significant increase in three-dimensional effects with decreasing wall conductance ratio. For small values of <span><math><mi>c</mi></math></span>, a stagnant zone is present in the nonuniform field region for all the values of the field gradient, which may create difficulties for tritium removal. If the exit duct is very long, the three-dimensional pressure drop is relatively low, but the effect of the nonuniform magnetic field on the velocity profiles is significant.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142571250","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":"Thermal hydraulic and material analysis of upgraded flat-type Graphite divertor mock-up for Pakistan Spherical Tokamak (PST)","authors":"Shahab Ud-Din Khan ,&nbsp;Ayesha Alam ,&nbsp;Muhammad Abdullah ,&nbsp;Ahmad Ali ,&nbsp;Ali Hussain ,&nbsp;Sehrish Shakir ,&nbsp;Shahzaib Zahid ,&nbsp;Riaz Khan","doi":"10.1016/j.fusengdes.2024.114704","DOIUrl":"10.1016/j.fusengdes.2024.114704","url":null,"abstract":"<div><div>The design of a divertor is critically dependent on managing power deposition, erosion effects, and plasma configuration. An upgraded double-null divertor configuration has been developed for the Pakistan Spherical Tokamak (PST), featuring graphite targets that are actively cooled and designed to withstand a peak heat flux of 0.3 MW/m² at a pressure of 0.1 MPa. This paper presents a comprehensive thermal-hydraulic and material analysis for the upgraded flat-type divertor mock-up system, covering aspects such as material surface heat load, peak temperature rise (∆T °C) on the mock-up, and surface temperature increase in the cooling channel. The analysis includes total deformation (mm) and equivalent strain for the inner vertical target (IVT), outer vertical target (OVT), and dome structure, along with material comparison. The recommended SST K-ω turbulence model is utilized in the pressure-based transient analysis, with an inlet velocity of 1.5 m s^-1 and an inlet temperature of 16.8 °C. A comparative study of the material and thermal-hydraulic analyses was performed using CFD and RELAP5. The findings reveal that graphite is more suitable than tungsten for the PST's upgraded divertor system, demonstrating its effectiveness as the preferred surface material to address heat enhancement challenges in the PST.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142571251","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":"Numerical structural analysis and flow-induced vibration study in support of the design of the EU-DEMO once-through steam generator mock-up for the STEAM experimental facility","authors":"I. Catanzaro ,&nbsp;G. Bongiovì ,&nbsp;S. Giambrone ,&nbsp;A. Gioè ,&nbsp;P. Arena ,&nbsp;A. Del Nevo ,&nbsp;M. Eboli ,&nbsp;S. Basile ,&nbsp;R. Burlon ,&nbsp;P. Chiovaro ,&nbsp;P.A. Di Maio ,&nbsp;M. Giardina ,&nbsp;A. Quartararo ,&nbsp;E. Tomarchio ,&nbsp;E. Vallone","doi":"10.1016/j.fusengdes.2024.114698","DOIUrl":"10.1016/j.fusengdes.2024.114698","url":null,"abstract":"<div><div>ENEA, as part of the EUROfusion consortium, is working at the realization of STEAM, an experimental facility integrated into the Water-cooled lithium lead-thermal-HYDRAulic (W-HYDRA) platform, envisaged for the qualification of the EU-DEMO steam generator during the different operational phases of a fusion reactor. It will aim at testing and qualifying the technological solutions to be adopted for the Primary Heat Transport System (PHTS) of the Water-Cooled Lead Lithium Breeding Blanket (WCLL BB). In particular, a mock-up of the Once-Through Steam Generator (OTSG) foreseen for the PHTS of the DEMO WCLL BB will be designed, installed and tested within STEAM. In this regard, a campaign of numerical structural analyses and a preliminary flow-induced vibration study have been carried out at the University of Palermo, in close collaboration with ENEA Brasimone. Firstly, a pipe stress analysis has been conducted focussing on the structural performances of the surge line devoted to connecting the STEAM facility to the pressurizer, looking at the stress and displacement arising under the nominal operating conditions so to propose proper design modifications. Secondly, in order to investigate the structural performances of the DEMO OTSG mock-up in the envisaged nominal operating scenario, a 3D steady-state thermo-mechanical FEM analysis has been carried out. The outcomes have allowed selecting the most critical regions in view of the adopted structural design code. Lastly, in order to preliminarily assess the potential onset of vibration-induced issues within the tubes of the DEMO OTSG mock-up, a preliminary analytical study has been carried out adopting formulae available in literature. The scope has been to establish if vibration-induced issues in the tubes can be reasonably excluded or if they could represent a tangible concern, to be further assessed. Models, assumptions and outcomes are provided and critically discussed.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-10-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142561282","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":"Preliminary results and analysis of a tangential TV Thomson scattering diagnostic system on EAST","authors":"Y.X. Zhu ,&nbsp;Q. Zang ,&nbsp;W. Chu ,&nbsp;M․Yu Kantor ,&nbsp;G.L. Lin ,&nbsp;M.F. Ren","doi":"10.1016/j.fusengdes.2024.114696","DOIUrl":"10.1016/j.fusengdes.2024.114696","url":null,"abstract":"<div><div>This paper presents the latest development of a tangential TVTS (Television Thomson scattering) system on the EAST Tokamak and the preliminary results obtained recently. For the goals of the thousand-second H-mode on EAST, it is obviously essential for the experimental operation and physical research to develop a high spatial resolution edge Thomson scattering diagnostic system. The new system uses a tangential optical path, mainly covering plasma ρ = 0.8 – 1.1 region. A high energy 532 nm laser was designed as the light source, which can realize the stable output of 10 Hz/3.5 <em>J</em> in the time of a thousand seconds through the new optical structure technology. In order to improve the scattering light splitting efficiency, the transmission grating is used as the main splitting device. We use a three-step image enhancement amplification technique so that the detection efficiency of the system can reach 3000 counts/photon. At present, the spatial resolution of the system is about 3 mm, and the measurement electron temperature (T_e) range is 50 eV - 2 keV, the electron temperature error is expected &lt;7 %.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-10-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142537947","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":"Parametric study of the breaking scenarios during the loss of vacuum accident for CFETR","authors":"Chenxi Hu ,&nbsp;Shanliang Zheng ,&nbsp;Yuanjie Li","doi":"10.1016/j.fusengdes.2024.114700","DOIUrl":"10.1016/j.fusengdes.2024.114700","url":null,"abstract":"<div><div>In the China Fusion Engineering Test Reactor (CFETR), the occurrence of a Loss of Vacuum Accident (LOVA) could result in high-velocity airflow entering the vacuum vessel, causing plasma disruption and potentially posing a significant safety hazard. In this study, the LOVA involving multiple small and minor breaches in the vacuum vessel (VV) of the CFETR is analyzed through modeling and simulation utilizing the ANSYS Fluent software. The study examines the influence of the initial pressure in VV, the total area, number, position, and distribution of breaking points on gas flow characteristics during the LOVA, based on the validation of the numerical model. The analysis includes the examination of the evolution and disappearance of the Mach disk resulting from supersonic fluid under the conditions of LOVA. With a constant total area, an increase in the number of distinct breaking points would result in a reduction of the critical mass flow rate of the jet. This decrease would decelerate the decline of the flow rate, consequently extending the necessary stability time. Moreover, the findings indicate that as the number of breaking points increases, the size of the Mach disk observed along the central flow axis diminishes, while the numerical value demonstrates a rising pattern.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-10-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142537951","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 development and preliminary experiment progress of in-vessel resonant magnetic perturbation coils system on HL-3 tokamak","authors":"A. Wang ,&nbsp;T.F. Sun ,&nbsp;W. Chen ,&nbsp;B.T. Cui ,&nbsp;J.M. Gao ,&nbsp;S.Y. Liang ,&nbsp;M.Y. He ,&nbsp;X.Q. Ji","doi":"10.1016/j.fusengdes.2024.114702","DOIUrl":"10.1016/j.fusengdes.2024.114702","url":null,"abstract":"<div><div>This paper details the design, construction, and analysis of resonant magnetic perturbation (RMP) with 16 in-vessel coils on the HL-3 to investigate the interactions between resonant magnetic perturbations and magnetohydrodynamic instabilities. The toroidal × poloidal = 8 × 2 arrangement allows for a more flexible magnetic field and spectrum shape. The RMP coil was designed as a four-turn double-layer winding. The coils are adopted with a water-cooled hollow copper conductor insulated with a MgO layer and then housed inside a welded stainless steel shell. The thermal and electromagnetic loads of the coil were evaluated by simulation, which meets the requirements. Four power supplies are integrated into the HL-3 system that can provide DC and AC with various waveforms. The maximum DC amplitude is 3 kA, while the AC frequency can reach up to 1 kHz. In the HL-3 H-mode plasmas, an experimental result of edge localized mode (ELM) mitigation with <em>n</em> = 1 RMPs which are oddly paired by 8 RMP coils is also given for the first time in this paper.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-10-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142537952","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":"Numerical investigation of the structural performances of the EU-DEMO Water-Cooled Lead Lithium breeding blanket equipped with helicoidal double-walled tubes","authors":"J.A. Noguerón ,&nbsp;P.A. Di Maio ,&nbsp;G. Bongiovì ,&nbsp;I. Catanzaro ,&nbsp;P. Chiovaro ,&nbsp;S. Giambrone ,&nbsp;A. Quartararo ,&nbsp;E. Vallone ,&nbsp;I. Fernández-Berceruelo ,&nbsp;P. Arena","doi":"10.1016/j.fusengdes.2024.114703","DOIUrl":"10.1016/j.fusengdes.2024.114703","url":null,"abstract":"<div><div>With the aim of improving the EU-DEMO breeding blanket (BB) system performances, variants to the reference design are presently under investigation in the EUROfusion activities. Among them, a novel layout for the double-walled tubes (DWTs) aimed at cooling the breeding zone is being studied for the Water-Cooled Lead Lithium (WCLL) BB concept. The new DWTs configuration consists of 6 couples of helical-shaped DWTs, with each tubes couple being positioned in a slot defined by the radial-poloidal stiffening plates (SPs). The adoption of the helicoidal tubes layout shall allow reducing the thermal hotspots in the BB structural material, being beneficial also in terms of thermal stress. Hence, a structural analysis of the equatorial region of the WCLL BB central outboard blanket segment has been performed and presented in this work.</div><div>The structural assessment has been conducted under various loading scenarios, including Normal Operation (NO), with nominal and design pressure values, and NO scenario considering buoyancy effects induced by the liquid breeder. All these scenarios assumed the same previously obtained thermal field to predict displacements and stress fields. Subsequently, a stress linearization procedure has been performed in some critical regions of the structure, which allows comparing the stress values obtained with the criteria prescribed by the reference design standard RCC-MRx. The outcomes derived from this evaluation, in terms of stresses and displacements, seem very promising. However, some contact regions have been identified in the tubes, necessitating careful consideration of geometric modifications in future analyses. Nevertheless, the obtained results clearly show that the proposed layout is worthy to be further assessed. A theoretical–numerical approach based on the Finite Element Method (FEM) was followed adopting the Ansys commercial code.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-10-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142537950","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":"Characterisation of pulse-mode operation of D-T portable neutron generator by diamond detector","authors":"Tomas Bily,&nbsp;Ondrej Novak,&nbsp;Ondrej Huml,&nbsp;Zhao-Ming Pan","doi":"10.1016/j.fusengdes.2024.114695","DOIUrl":"10.1016/j.fusengdes.2024.114695","url":null,"abstract":"<div><div>A single-crystal fast neutron diamond detector has been applied to study the pulse-mode operation of the MP320 portable neutron generator. The pulses were recorded by the Red Pitaya – STEMlab 125–14 with modified FPGA firmware. The study includes the main parameters that affect the neutron pulse output of the neutron generator, i.e. pulsing frequency, duty factor, and beam current. Neutron pulse shapes, i.e. time dependences of neutron emission of neutron generator operated in pulsing mode, have been measured for four frequencies in the range from 250 Hz to 20 kHz, for two values of duty factors (10 % and 50 %), and for three values of beam current (20, 45 and 70 μA). The measurement showed significant deterioration from idealised rectangular neutron emission, especially for high frequencies and for low values of beam current. The results confirm that the fast neutron diamond detectors can be advantageously used for characterisation of pulse operation of DT portable neutron generator in the whole range of its operational parameters.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-10-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142537948","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}