Fusion Engineering and Design最新文献

{"title":"On the fabrication of ultrafine-grained potassium-doped tungsten: Mechanical milling and spark plasma sintering of K-doped W powder prepared by evaporation-condensation method","authors":"Meng She ,&nbsp;Jianming Nie ,&nbsp;Xiaoyan Shu ,&nbsp;Lin Feng ,&nbsp;Jun Tang ,&nbsp;Bo Huang","doi":"10.1016/j.fusengdes.2024.114678","DOIUrl":"10.1016/j.fusengdes.2024.114678","url":null,"abstract":"<div><div>Bubble strengthened materials have received lots of attention in recent years, and among them, potassium-doped tungsten (W-K) is extremely desirable for very high-temperature applications such as plasma-facing materials in fusion reactors. However, it is difficult to fabricate ultrafine-grained W-K bulk materials by traditional methods. In this study, a novel preparation method of ultra-fine-grained bubble-strengthened material is presented. Unlike traditional routes, W-K mixed powder was prepared by evaporating and condensing pure K on the surface of nanoscale W powder. Two W-K mixing methods using this evaporation-condensation route were developed. Mechanical milling process combined with regular SPS sintering were carried out on the W-K mixed powder, which successfully manufactured ultrafine-grained (0.9 μm) W-K bulk material with a high density (96.4%). This study can provide important reference for the fabrication of other bubble-strengthened materials.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142318530","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":"X-ray imaging crystal spectrometer (XICS) diagnostic on the HL-3 tokamak","authors":"X.L. Zhang ,&nbsp;Z.Y.H. He ,&nbsp;Z.F. Cheng ,&nbsp;W. Yan ,&nbsp;Y.B. Dong ,&nbsp;Y. Liu ,&nbsp;W. Deng ,&nbsp;B.Z. Fu ,&nbsp;Z.B. Shi ,&nbsp;Y.P. Zhang ,&nbsp;Y.J. Shi","doi":"10.1016/j.fusengdes.2024.114674","DOIUrl":"10.1016/j.fusengdes.2024.114674","url":null,"abstract":"<div><div>The construction of an X-ray imaging crystal spectrometer (XICS) diagnostic system on the HL-3 tokamak plays a crucial role in measuring core plasma parameter profiles, including ion temperature, electron temperature, rotational velocity, and impurity radiation profiles. This diagnostic system has been specifically designed to provide detailed and accurate data essential for understanding the behavior and characteristics of tokamak plasma. The resonance spectral line (<em>w</em> line of Ar XVII at 3.9494 Å) and its satellites of helium-like argon ions were chosen on the basis of the HL-3 parameter range. A spherically bent quartz crystal (1012) with a lattice constant of 2d = 4.562 Å, a curvature radius of Rc = 3.0 m, and a size of 10 cm (high) × 5 cm (wide) was mounted on an adjustable displacement platform in the XICS system. The position was adjusted in three dimensions (vertical, inclined, rotation) to effectively record the spectra of the helium-like argon ions. The XICS has a tangential angle of 49° for the toroidal direction in the magnetic axis. This layout accounts for 65.6 % of the toroidal rotation velocity component. The XICS system was set at an 11° poloidal angle in the mid-plane to cover a plasma range of 10 cm above to 50 cm below the mid-plane, which corresponds to the <em>q</em> = 1 surface of the HL-3 plasma (elongation κ &gt; 1.8). This XICS layout produced a spectrum with poloidal and toroidal rotational contributions, requiring decoupling through data processing. In general, because the contribution of the poloidal rotation velocity is much smaller than that of the toroidal rotation velocity, it can be ignored. The XICS system offers a spatial resolution of ∼1.5 cm and a temporal resolution of 5–10 ms on the basis of a high-performance PILATUS3 × 900 K detector. The spectral resolution is <span><math><mrow><mi>λ</mi><mo>/</mo><mstyle><mi>Δ</mi></mstyle><mi>λ</mi><mo>∼</mo><mn>4</mn><mspace></mspace><mo>×</mo><msup><mn>10</mn><mn>4</mn></msup></mrow></math></span>, which satisfies the experimental measurement requirements. Preliminary results of ion and electron temperature profiles were obtained for the HL-3 tokamak.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142318531","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"The energy output equilibrium scheme with intermediate energy storage for tokamak fusion power plant","authors":"Hua Li ,&nbsp;Zhanpeng Liang ,&nbsp;Kui Xiang ,&nbsp;Qianglin Xu ,&nbsp;Hang Su ,&nbsp;Zhiquan Song ,&nbsp;Ge Gao ,&nbsp;Peng Fu","doi":"10.1016/j.fusengdes.2024.114669","DOIUrl":"10.1016/j.fusengdes.2024.114669","url":null,"abstract":"<div><p>Different from the design of nuclear fission power plant, the design of fusion power plant needs to consider the problem of discontinuous fusion energy output from nuclear island. This paper proposed an energy output equilibrium scheme for fusion power plant. Based on analysis and comparison, thermal energy storage method was adopted, and two system operation schemes for fusion power plant were further proposed. Finally, system thermal storage calculation and analysis were conducted under WCCB blanket and HCCB blanket respectively, and conclusions were drawn on the applicable system operation scheme under different blankets. This study provides research foundation and engineering reference for the design and construction of future fusion power plants.</p></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142263066","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":"Measurement of the mechanical vibration and its impact on the magnetic diagnostics in the J-TEXT tokamak","authors":"Bo Hu,&nbsp;Song Zhou,&nbsp;Nengchao Wang,&nbsp;Yangbo Li,&nbsp;Feiyue Mao,&nbsp;Zhengkang Ren,&nbsp;Ying He,&nbsp;Chuanxu Zhao,&nbsp;Yonghua Ding,&nbsp;the J-TEXT team","doi":"10.1016/j.fusengdes.2024.114670","DOIUrl":"10.1016/j.fusengdes.2024.114670","url":null,"abstract":"<div><p>The mechanical vibration and its profound impacts on the magnetic diagnostic measurement have been observed on the J-TEXT tokamak. To explain the low frequency magnetic oscillation induced by the vibration, an analytical model has been developed. The comparisons between the experimental results and the analytical model indicate that the vibration of the vacuum vessel is along two keystones of J-TEXT. Through vibration measurements of J-TEXT components, we have identified that the origin of vibration is the rapid change of the pre-magnetization field. Additionally, it is found that the relative vibrations between magnetic diagnostics and toroidal magnetic fields contribute to the low frequency magnetic oscillation. The results obtained in this work are not only important for the prediction of vibration in fusion devices, but also helpful for experimenters to input corrections in obtained diagnostic results.</p></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142233902","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":"Overview of the TCV digital real-time plasma control system and its applications","authors":"Cristian Galperti ,&nbsp;Federico Felici ,&nbsp;Trang Vu ,&nbsp;Olivier Sauter ,&nbsp;F. Carpanese ,&nbsp;M. Kong ,&nbsp;G. Marceca ,&nbsp;A. Merle ,&nbsp;A. Pau ,&nbsp;A. Perek ,&nbsp;F. Pesamosca ,&nbsp;M. Baquero-Ruiz ,&nbsp;S. Coda ,&nbsp;J. Decker ,&nbsp;B. Duval ,&nbsp;M. Gospodarczyk ,&nbsp;A. Karpushov ,&nbsp;S. Marchioni ,&nbsp;A. Maier ,&nbsp;B. Marletaz ,&nbsp;F. Sartori","doi":"10.1016/j.fusengdes.2024.114640","DOIUrl":"10.1016/j.fusengdes.2024.114640","url":null,"abstract":"<div><p>Real-time plasma control systems are at the heart of operation of modern tokamaks. The control system of the TCV tokamak has recently seen a major upgrade in terms of its hardware and software components. Control algorithms are entirely programmed and tested in MATLAB/Simulink(R), executable code is automatically generated and interfaced to run-time parameters and signals through introspection using the MARTe2 software framework. The primary control system (used for coil currents, plasma current, position, shape and density control) has been upgraded by installing new analog signal inputs/output hardware, connected to two real-time computers that can operate in parallel. In addition, an EtherCAT-based real-time industrial network has been deployed to operate distributed low Input/Output count subsystems, greatly boosting the system flexibility and reach. The majority of TCV’s real-time codes have been ported to this new approach, such as the real-time equilibrium reconstruction (LIUQE), real-time Magneto-Hydro-Dynamics mode analysis algorithms, and a real-time plasma supervision, actuator management and plasma event monitor, including real-time plasma analysis using neural networks, and plasma disruption avoidance control schemes.</p></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S0920379624004915/pdfft?md5=5fad12079caa8fcac05d400d0beab1a4&pid=1-s2.0-S0920379624004915-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142229968","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":"Influence of dimensional deviation and thickness non-uniformity on the small-size specimen tensile results of CLF-1 steel","authors":"Shushan Cui ,&nbsp;Lifeng He ,&nbsp;Xinfu He ,&nbsp;Jiru Zhong ,&nbsp;Bin Long ,&nbsp;Dongli Zou","doi":"10.1016/j.fusengdes.2024.114673","DOIUrl":"10.1016/j.fusengdes.2024.114673","url":null,"abstract":"<div><p>Tensile testing of small-size specimens has been widely used to evaluate the influence of neutron irradiation on the mechanical properties for structural materials of fusion reactors. In recent years, researchers have been trying to standardize small-size specimen tensile test method. In the present paper, we have investigated the influence of dimensional deviation and thickness non-uniformity on the tensile results of small-size specimen by both experiments and finite element simulations, based on one of the candidate structural materials of fusion reactor, <em>i.e.</em> CLF-1 steel. It was found that under the conditions of small grain size, small metallurgical defect size and suitable specimen preparation, the tensile results of SS-J3 specimen could be close to the results of large-size specimen. Slightly higher yield and ultimate strengths for small specimens may be caused by the surface treatment of the wheel grinding. The repeatability of ultimate strength was better than that of yield strength, and the repeatability of elongation was worse than that of strength. For tensile tests on eight SS-J3 specimens, the maximum difference in total elongation was about 3 %. With ±0.1 mm deviation of thickness and parallel width, the maximum variation in total elongation was about 1.8 %. The ductility properties were sensitive to specimen's thickness non-uniformity, the measured uniform and total elongations would obviously decrease even with 0.01 mm thickness non-uniformity.</p></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142229969","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":"Analysis, design, and testing of mechanical switch for the backup protection of switching network unit in fusion device","authors":"Qianglin Xu ,&nbsp;Zhiquan Song ,&nbsp;Hua Li ,&nbsp;Meng Xu","doi":"10.1016/j.fusengdes.2024.114672","DOIUrl":"10.1016/j.fusengdes.2024.114672","url":null,"abstract":"<div><p>Switching network unit (SNU) is one of the important systems in the power supply system of fusion devices, which excites and establishes plasma current. A mechanical switch has been designed for SNU backup protection, which can short-circuit other components in case of SNU failure to prevent further deterioration of the situation. An optimized contact system is used in this switch to improve the maintainability of the contacts. A detailed structural design was carried out for the switch, and the final prototype test results verified that it meets the relevant design requirements. This backup protection scheme can provide a certain reference for the engineering design and reliable operation of SNU.</p></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142171818","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":"First operation and validation of simulations for the divertor cryo-vacuum pump in Wendelstein 7-X","authors":"V. Haak ,&nbsp;C.P. Dhard ,&nbsp;D. Boeyaert ,&nbsp;T. Bräuer ,&nbsp;V. Bykov ,&nbsp;C. Day ,&nbsp;S. Degenkolbe ,&nbsp;G. Ehrke ,&nbsp;J. Igitkhanov ,&nbsp;M. Khokhlov ,&nbsp;T. Kremeyer ,&nbsp;M. Nagel ,&nbsp;D. Naujoks ,&nbsp;M. Pietsch ,&nbsp;D. Pilopp ,&nbsp;G. Schlisio ,&nbsp;H. Strobel ,&nbsp;C. Tantos ,&nbsp;S. Varoutis ,&nbsp;H. Viebke ,&nbsp;O. Volzke","doi":"10.1016/j.fusengdes.2024.114671","DOIUrl":"10.1016/j.fusengdes.2024.114671","url":null,"abstract":"<div><p>Ten cryo-vacuum pumps (CVPs) were installed in the subdivertor region of each island divertor in the stellarator Wendelstein 7-X (W7-X) and operated for the first time during the recently completed plasma campaign OP2.1. A pumping speed of 70 ± 1<!--> <span><math><mfrac><mrow><msup><mrow><mtext>m</mtext></mrow><mrow><mn>3</mn></mrow></msup></mrow><mrow><mtext>s</mtext></mrow></mfrac></math></span> was measured during dedicated tests with known hydrogen gas injection. Based on a conductance model, the estimated pumping speed ranges from 86-93<!--> <span><math><mfrac><mrow><msup><mrow><mtext>m</mtext></mrow><mrow><mn>3</mn></mrow></msup></mrow><mrow><mtext>s</mtext></mrow></mfrac></math></span> for different sticking coefficients between 0.6 and 0.8. After completion of the initial tests the CVPs were operated successfully throughout the campaign, with regeneration performed once a week. Neutral gas pressures in the subdivertor in the range of 10⁻⁴ <!-->mbar are well within the molecular flow regime and limit the particle exhaust capabilities of the CVPs. Simulations of the neutral gas pressure in the three-dimensional complex geometry of the subdivertor were performed using the DIVGAS code based on the direct simulation Monte Carlo method and a model implemented in the steady-state thermal package in ANSYS, which are in agreement with the measured values during plasma operation.</p></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S0920379624005222/pdfft?md5=a5cfecbe4c18fa6bf0ac68d10c414bbc&pid=1-s2.0-S0920379624005222-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142169130","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Design and construction of GaInSn experimental facility for studies of mixed-convection MHD flows","authors":"Jiandong Zhou ,&nbsp;Yuhao Tang ,&nbsp;Yanwu Cao ,&nbsp;Ze Lyu ,&nbsp;Kecheng Jiang ,&nbsp;Juancheng Yang ,&nbsp;MingJiu Ni","doi":"10.1016/j.fusengdes.2024.114654","DOIUrl":"10.1016/j.fusengdes.2024.114654","url":null,"abstract":"<div><p>A multifunctional liquid metal loop named MaTHE-XJTU (Magneto-Thermo-Hydrodynamic Experiments-Xi'an Jiaotong University) that utilizes eutectic alloy GaInSn as a working fluid has been designed and constructed. The function of the MaTHE-XJTU facility is to study the magnetohydrodynamic (MHD) flow and mixed convection characteristics under the coupling effect. The main operating parameters of the loop are: the maximum magnetic field intensity is 3T, the effective magnetic field region is 300 mm × 800 mm × 1000 mm, the maximum flow rate of electromagnetic pump (EM pump) is 8 m³/h, the maximum pressure head of EM pump is 0.5 MPa. The paper describes the major components and basic operation procedures of the loop, the related flow diagnostics method, and near-future experiments. This loop could provide a high-parameter experimental platform (<em>Ha</em>∼10⁴, Gr∼<em>10</em>⁹, <em>Re</em>∼10⁴) for investigations that improve the present understanding of magnetohydrodynamic and heat transfer performance in liquid metal blankets.</p></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142163214","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Experimental investigation of tritium release behavior from neutron irradiated LiAlO2 with Zr for tritium production in a high-temperature gas-cooled reactor","authors":"Hiroki Isogawa ,&nbsp;Kazunari Katayama ,&nbsp;Seiyo Kobayashi ,&nbsp;Hideaki Matsuura ,&nbsp;Yuto Iinuma","doi":"10.1016/j.fusengdes.2024.114657","DOIUrl":"10.1016/j.fusengdes.2024.114657","url":null,"abstract":"<div><p>Tritium production using nuclear reactions of neutrons with lithium in a high temperature gas-cooled reactors has been studied as an external source of fuel tritium in the early stage of fusion reactor operation. In order to control tritium migration throughout the reactor, it is important to understand tritium release behaviors from Zr-containing LiAlO₂, which are used as tritium producing materials. In this study, tritium release behavior from neutron irradiated LiAlO₂ with and without Zr ware investigated by heating to 900 °C. In the case of heating only LiAlO₂, most tritium was released in the chemical form of HTO. On the other hand, in the case of heating Zr-containing LiAlO₂, the chemical form of tritium was mostly HT. This result indicates that even if tritium is released from LiAlO₂ as HTO, it is effectively absorbed by Zr at 900 °C.</p></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9,"publicationDate":"2024-09-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S0920379624005088/pdfft?md5=34dd2349a51fb34d20de1e2168bd8a10&pid=1-s2.0-S0920379624005088-main.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142163215","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}