Fusion Engineering and Design最新文献_第3页

Maximum likelihood bolometric tomography for DTT diagnostic design

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-25 DOI: 10.1016/j.fusengdes.2025.114947

E. Peluso , T. Craciunescu , G.M. Apruzzese , A. Belpane , S. Palomba , L. Senni , V. D'Agostino , M. Gelfusa , P. Gaudio , L. Boncagni

{"title":"Maximum likelihood bolometric tomography for DTT diagnostic design","authors":"E. Peluso , T. Craciunescu , G.M. Apruzzese , A. Belpane , S. Palomba , L. Senni , V. D'Agostino , M. Gelfusa , P. Gaudio , L. Boncagni","doi":"10.1016/j.fusengdes.2025.114947","DOIUrl":"10.1016/j.fusengdes.2025.114947","url":null,"abstract":"<div><div>On both the Joint European Torus (JET) and the ASDEX-Upgrade (AUG) tokamaks, an Expectation Maximization algorithm has been adapted to implement a Maximum Likelihood (ML) approach to derive tomograms from bolometers data. The main feature of such an approach is the ability to estimate the variance associated with the reconstructed tomograms and hence the uncertainties in the derived quantities. It has therefore been selected to support the design of the bolometric diagnostics for the Divertor Tokamak Test Facility (DTT). A reliable reconstruction of the emissivity profile is indeed relevant for the scientific exploitation of the device. As any tomographic inversion method is an ill-conditioned problem, two milestones should be achieved: ensuring the reconstruction of specific features and minimizing the risk of producing artefacts. The design strategy for the bolometric diagnostic on DTT involves testing various possible layouts to ensure that they meet the above requirements and are compatible with the engineering and machine constraints. This contribution focuses on showing how the conceptual bolometric layout can handle different phantoms mimicking typical emissivities observed on JET and AUG. A methodology has been developed to further optimize the layout within the constraints of the machine design. For the initial phase of DTT, a reduced layout is proposed, utilizing half of the conceptual lines of sight. The ability to reconstruct specific emissivity features while minimizing the risk of producing artefacts has been tested. The current ML implementation uses an anisotropic diffusion technique and is already significantly faster than the JET implementation for each reconstruction.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114947"},"PeriodicalIF":1.9,"publicationDate":"2025-03-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685153","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}

引用次数: 0

The application of a directional electron probe in the measurement of W7-X scrape-off layer current

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-24 DOI: 10.1016/j.fusengdes.2025.114904

L. Liao , S.C. Liu , Y. Liang , A. Knieps , P. Drews , C. Killer , D. Nicolai , O. Neubauer , X.J. Liu , the W7-X Team

{"title":"The application of a directional electron probe in the measurement of W7-X scrape-off layer current","authors":"L. Liao , S.C. Liu , Y. Liang , A. Knieps , P. Drews , C. Killer , D. Nicolai , O. Neubauer , X.J. Liu , the W7-X Team","doi":"10.1016/j.fusengdes.2025.114904","DOIUrl":"10.1016/j.fusengdes.2025.114904","url":null,"abstract":"<div><div>An innovative configuration of the directional electron probe (DEP) has been recently implemented in the W7-X stellarator to accurately measure the scrape-off layer (SOL) electron current profile. This configuration employs dual radial arrays of electrodes oriented in contrasting toroidal directions. The probe is tilted by 10° in the toroidal direction such that each pair of electrodes is located on a common magnetic field line. Each DEP channel is equipped with a perforation through the boron nitride cover, terminating in a graphite collector. The perforation is designed in a sector shape with a central angle of 15°. Perforations are inclined at an angle of 18° with respect to the vertical direction in order to align with the shape of the magnetic flux surfaces at the probe position, featuring a radial width of 0.5 mm. By applying a positive biasing voltage to the graphite collector, such as +180 V, electrons are attracted and ions are repelled. Within the DEP setup, this voltage setup effectively repulses low-energy ions, while the perforation's dimensions impede most high-energy ions attributed to their substantial gyroradius in contrast to the smaller perforation width. Consequently, the current collected predominantly comes from electrons, and the differential current measured between the opposing collectors denotes the presence of a directional current driven by electrons. In the magnetic standard configuration with magnetic islands forming the SOL, the DEP measured SOL current profiles from close to the Last Closed Flux Surface (LCFS) to the far SOL (70 mm away). Net current follows in directions in the different regions of the SOL has been observed, with current densities reaching amplitudes up to 50 <span><math><mrow><mrow><mspace></mspace><mtext>kA</mtext></mrow><mo>/</mo><msup><mrow><mi>m</mi></mrow><mn>2</mn></msup></mrow></math></span>.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114904"},"PeriodicalIF":1.9,"publicationDate":"2025-03-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685152","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}

引用次数: 0

Investigation of stress corrosion properties of 9Cr-ODS-Al steel in supercritical water

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-24 DOI: 10.1016/j.fusengdes.2025.114982

Rongrong Luo , Haiying Fu , Teng Zhang , Yongming Han , Yonghao Lu , Shilei Han , Hongfeng Zhu , Tengfei Yan , Pengyuan Li

{"title":"Investigation of stress corrosion properties of 9Cr-ODS-Al steel in supercritical water","authors":"Rongrong Luo , Haiying Fu , Teng Zhang , Yongming Han , Yonghao Lu , Shilei Han , Hongfeng Zhu , Tengfei Yan , Pengyuan Li","doi":"10.1016/j.fusengdes.2025.114982","DOIUrl":"10.1016/j.fusengdes.2025.114982","url":null,"abstract":"<div><div>Consideration is being given to the Supercritical Water-Cooled Reactor (SCWR) as a prospective reactor configuration due to its superior thermal efficiency and the simplification of its structure, which obviates the need for steam generators and separators. This has led to the proposition of a supercritical water-based cooling concept within the scope of fusion reactor designs. When selecting alternative structural materials for the fusion breeding blanket, it is imperative to evaluate their resilience against corrosion and their vulnerability to stress corrosion cracking (SCC). In this context, the performance of 9Cr-ODS-Al steel, an oxide dispersion strengthened alloy, was examined under supercritical water (SCW) conditions at temperatures of 400 °C, 550 °C, and a pressure of 25 MPa over a period extending to 1152 h. The analytical findings from SEM and EDS confirmed the formation of a dual-layered oxide on the 9Cr-ODS-Al, consisting of an external layer and an internal compound oxide of Fe, Cr and Al. Slow Strain Rate Testing (SSRT) showed no signs of SCC on the examined fracture surfaces of the alloy, while a decrease in both ultimate tensile strength (UTS) and yield strength (YS) was observed at 550 °C/25MPa. Additionally, the fracture surfaces demonstrated characteristics of toughness, and the growth rate of stress corrosion cracks in the steel escalated with the stress intensity factor.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114982"},"PeriodicalIF":1.9,"publicationDate":"2025-03-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685150","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}

引用次数: 0

High RF voltage resonator test facility for new ASDEX Upgrade ICRF antenna vacuum feedthrough

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-24 DOI: 10.1016/j.fusengdes.2025.114984

O. Girka , W. Helou , H. Faugel , H. Fünfgelder , V. Bobkov

{"title":"High RF voltage resonator test facility for new ASDEX Upgrade ICRF antenna vacuum feedthrough","authors":"O. Girka , W. Helou , H. Faugel , H. Fünfgelder , V. Bobkov","doi":"10.1016/j.fusengdes.2025.114984","DOIUrl":"10.1016/j.fusengdes.2025.114984","url":null,"abstract":"<div><div>New vacuum feedthrough has been recently designed for the ASDEX Upgrade ICRF system. Vacuum feedthroughs in general can limit the voltage standoff of high power RF systems. ICRF vacuum feedthroughs are no exception, they require careful design, as well as qualifications and testing prior to installation to the antenna. The paper shows the design of a new full wavelength resonator test facility for the new ASDEX Upgrade ICRF antenna vacuum feedthroughs. The new test facility is an extension to ISHTAR (Ion-cyclotron System Hardware Test Arrangement) and is designed to have two configurations: the first one with two new 9-inch windows with improved surrounding structures (corona rings or arc traps); the second one with a 6-inch window with old-existing surrounding structures and one new 9-inch window. A set of high power tests (∼400 kW, ≤10 s) are planned using ASDEX Upgrade ICRF generator 5 in order to achieve the same voltage stand-off as it is during the ICRF system operation on ASDEX Upgrade. Different ceramics are characterized and considered for ASDEX Upgrade RF windows.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114984"},"PeriodicalIF":1.9,"publicationDate":"2025-03-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685154","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}

引用次数: 0

Maintenance plan of the ITER Radial Neutron Camera: Verification and validation by virtual reality simulation

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-23 DOI: 10.1016/j.fusengdes.2025.114980

Enrico Occhiuto , Domenico Marzullo , Danilo Nicola Dongiovanni , Ugo Bonavolontà , Francesco Malaroda , Daniele Marocco , Basilio Esposito

{"title":"Maintenance plan of the ITER Radial Neutron Camera: Verification and validation by virtual reality simulation","authors":"Enrico Occhiuto , Domenico Marzullo , Danilo Nicola Dongiovanni , Ugo Bonavolontà , Francesco Malaroda , Daniele Marocco , Basilio Esposito","doi":"10.1016/j.fusengdes.2025.114980","DOIUrl":"10.1016/j.fusengdes.2025.114980","url":null,"abstract":"<div><div>The Radial Neutron Camera (RNC) is an ITER diagnostic designed to measure the un-collided 14 MeV and 2.5 MeV neutrons from deuterium-tritium (DT) and deuterium-deuterium (DD) fusion reactions, through an array of detectors covering a poloidal plasma section along collimated Lines Of Sight (LOS).</div><div>The Ex-Port RNC is located in the Port Cell (PC) Interspace zone, the first area outside the Vacuum Vessel, and includes several detector units, mounted inside detector boxes. On the base of reliability considerations, the Radial Neutron Camera Maintenance Plan (RNC-MP) has foreseen a hands-on maintenance task to replace detectors unit equipment in case of failure. Despite not precluding workers access, the radiation field at shutdown in the PC Interspace zone requires optimization of hands-on operations to enable the minimization of occupational radiation exposure under the ALARA (As Low As Reasonably Achievable) principle.</div><div>The relevant complexity and dimensions of the Ex-Port RNC requires a maintenance evaluation method different from a physical mock-up. The Virtual Reality technology may help to create a digital mock-up for evaluating the detectors replacement operations. The paper aims to demonstrate the potentialities of such technologies, in a field where safety and worker ergonomics are primary priorities. Thanks to the virtual scenario built, the RNC-MP updated steps are evaluated, improved and finally validated. The VR simulation is as well validated via a simple physical mock-up of the detector box.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114980"},"PeriodicalIF":1.9,"publicationDate":"2025-03-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685151","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}

引用次数: 0

Development of an in-vessel special calibration light source for ITER divertor infrared thermography

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-23 DOI: 10.1016/j.fusengdes.2025.114963

Tomohiko Ushiki , Tatsuo Sugie , Hiroyuki Tachibana , Kosuke Shimizu , Butch Buenavidez , Naoto Kasano , Yuzi Katayanagi , Yoshihiko Nunoya

{"title":"Development of an in-vessel special calibration light source for ITER divertor infrared thermography","authors":"Tomohiko Ushiki , Tatsuo Sugie , Hiroyuki Tachibana , Kosuke Shimizu , Butch Buenavidez , Naoto Kasano , Yuzi Katayanagi , Yoshihiko Nunoya","doi":"10.1016/j.fusengdes.2025.114963","DOIUrl":"10.1016/j.fusengdes.2025.114963","url":null,"abstract":"<div><div>This study designed an in-vessel special calibration light source (heater) for calibrating the total transmittance change of the ITER divertor infrared thermography system. The top plate of this calibration heater was designed having a multi-pyramid structure that uses triangular pyramids to ensure robustness and high reproducibility for calibrations over ITER's 20-year operational period. The triangular pyramid structure enhances robustness by minimizing the impact of changes in surface emissivity, such as changes caused by contamination, on the effective emissivity. A prototype of this calibration heater was fabricated, and its performance was evaluated. The prototype heater demonstrated stable light source performance, achieving a low variation rate of luminance on the heater top plate surface of approximately 3.2 % within the measurement wavelength range of 1.5–4.5 μm by controlling the temperature of the thermocouple embedded in the top plate during several heating cycles. Furthermore, the light source proved to be robust, as the effective emissivity changed by only 4.5 %, even when the local surface emissivity of the top plate varied by ±40 % due to surface contamination.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114963"},"PeriodicalIF":1.9,"publicationDate":"2025-03-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685166","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}

引用次数: 0

Preparation of Fe-Al coating on 316LSS by low-temperature and high-activation pack aluminizing

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-23 DOI: 10.1016/j.fusengdes.2025.114978

Shijian Lin , Yongjin Wu , Changzheng Li , Zhiyi Cai , Lihong Nie , Qisen Ren , Bin Luo , Hao Yang , Hongtao Huang

{"title":"Preparation of Fe-Al coating on 316LSS by low-temperature and high-activation pack aluminizing","authors":"Shijian Lin , Yongjin Wu , Changzheng Li , Zhiyi Cai , Lihong Nie , Qisen Ren , Bin Luo , Hao Yang , Hongtao Huang","doi":"10.1016/j.fusengdes.2025.114978","DOIUrl":"10.1016/j.fusengdes.2025.114978","url":null,"abstract":"<div><div>The Fe-Al/Al<sub>2</sub>O<sub>3</sub> composite coating is the preferred tritium permeation barrier system in the current research. The Fe-Al transition layer possesses distinct properties, including excellent thermal adaptability and self-healing capabilities. Pack aluminizing is a widely utilized technique for preparing Fe-Al coatings. In this study, the pack aluminizing process was employed on the surface of 316 L stainless steel substrate, and the effects of aluminizing agent ratio, substrate roughness, substrate geometry, aluminizing temperature and aluminizing time on the growth of the aluminized layer were investigated. The experimental results indicated that the aluminized layer comprises Fe<sub>2</sub>Al<sub>5</sub> and FeAl<sub>3</sub> phases. Increasing the aluminizing temperature and duration resulted in a thicker Fe-Al coating. However, these factors did not significantly affect the phase composition. The geometry of the substrate does not significantly affect the growth thickness and phase composition of the aluminized layer. Based on these findings, the kinetics of the aluminized layer formation process were analyzed. The relationship between aluminizing temperature and coating thickness followed the Arrhenius equation. The activation energy of pack aluminizing on the surface of 316 L stainless steel was determined to be 68.70 kJ/mol under the aluminizing agent ratio of 40 wt.% aluminum, 56 wt.% alumina and 4 wt.% aluminum chloride. The value was found to be lower than the previously reported activation energies. Furthermore, a thicker coating can be achieved at the same aluminizing temperature and duration by increasing the aluminum source and activator content.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114978"},"PeriodicalIF":1.9,"publicationDate":"2025-03-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685163","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}

引用次数: 0

Simulation of helicon wave current drive on the Experimental Advanced Superconducting Tokamak under high poloidal beta scenarios

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-22 DOI: 10.1016/j.fusengdes.2025.114968

Daozheng Zi , Zehou Cheng , Shuheng Sun , Miaohui Li , Xinxia Li

{"title":"Simulation of helicon wave current drive on the Experimental Advanced Superconducting Tokamak under high poloidal beta scenarios","authors":"Daozheng Zi , Zehou Cheng , Shuheng Sun , Miaohui Li , Xinxia Li","doi":"10.1016/j.fusengdes.2025.114968","DOIUrl":"10.1016/j.fusengdes.2025.114968","url":null,"abstract":"<div><div>The high poloidal beta (<span><math><msub><mrow><mi>β</mi></mrow><mrow><mi>p</mi></mrow></msub></math></span>) scenario serves as a promising operational mode for tokamak fusion reactors. In this paper, the helicon wave current drive under high <span><math><msub><mrow><mi>β</mi></mrow><mrow><mi>p</mi></mrow></msub></math></span> scenarios on the EAST device is studied numerically. Theoretical analysis based on the fast wave dispersion relation indicates that a higher wave frequency enhances wave power absorption in the device. GENRAY/CQL3D simulations indicate that an effective on-axis plasma current drive can generally be achieved. Scans of plasma parameters reveal that lower plasma density and higher plasma temperature contribute to higher current drive efficiency. Moreover, a scheme of combined current drive using lower hybrid waves and helicon waves in the device is analyzed, resulting in significant complementarity in the current drive profile and a positive synergistic effect on the net current drive. This work is expected to provide a new perspective for the next stage of EAST operations.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114968"},"PeriodicalIF":1.9,"publicationDate":"2025-03-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685165","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}

引用次数: 0

Model experiments to the conductivity of turn insulation of large fusion magnets during unmitigated quench

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-22 DOI: 10.1016/j.fusengdes.2025.114975

Linlin Fang , Yury Ilin , Xiongyi Huang , Qingxiang Ran , Zhiheng Dai , Cao Wang , Guoliang Li , Jinxing Zheng , Kun Lu , Yuntao Song

{"title":"Model experiments to the conductivity of turn insulation of large fusion magnets during unmitigated quench","authors":"Linlin Fang , Yury Ilin , Xiongyi Huang , Qingxiang Ran , Zhiheng Dai , Cao Wang , Guoliang Li , Jinxing Zheng , Kun Lu , Yuntao Song","doi":"10.1016/j.fusengdes.2025.114975","DOIUrl":"10.1016/j.fusengdes.2025.114975","url":null,"abstract":"<div><div>The ITER superconducting magnet system stores a significant amount of energy. During an unmitigated quench, the undissipated energy can cause localized conductors to melt and break, leading to the formation of arcs. These arcs not only directly damage the conductor but may also cause indirect damage to adjacent components, such as the vacuum vessel and cryostat, potentially leading to the release of radioactivity. As the arcs form and develop in the magnet, the turn insulation gradually carbonizes. If the resistivity of the carbonized insulation is sufficiently low, it can affect the current distribution and arc propagation. To understand the conductivity of the turn insulation in a superconducting magnet during an unmitigated quench, this paper references the ITER magnet design and manufactures simplified samples. The experimental setup was established, and the samples were heated under a direct current. The voltage and temperature signals of the samples were analyzed during testing to gain a preliminary understanding of the turn insulation's conductivity from room temperature to 1000 °C over a heating period of several hundred seconds.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114975"},"PeriodicalIF":1.9,"publicationDate":"2025-03-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685918","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}

引用次数: 0

Enabling model-based scenario control in EAST by fast surrogate modeling within COTSIM

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-03-22 DOI: 10.1016/j.fusengdes.2025.114969

Z. Wang , E. Schuster , T. Rafiq , Y. Huang , Z. Luo , Q. Yuan , J. Barr

{"title":"Enabling model-based scenario control in EAST by fast surrogate modeling within COTSIM","authors":"Z. Wang , E. Schuster , T. Rafiq , Y. Huang , Z. Luo , Q. Yuan , J. Barr","doi":"10.1016/j.fusengdes.2025.114969","DOIUrl":"10.1016/j.fusengdes.2025.114969","url":null,"abstract":"<div><div>The Control-Oriented Transport Simulator (COTSIM) is a fast, modular code designed to predict the evolution of both equilibrium and internal profiles in the EAST tokamak. Built on MATLAB/Simulink®, COTSIM is tailored for iterative control design, making it suitable for applications such as pulse design, feedforward scenario optimization, feedback-control testing prior to implementation, and real-time estimation and optimization. Recent advancements have enhanced its prediction accuracy for EAST while maintaining computational efficiency through the integration of neural-network-based surrogate models for the Multi-Mode Anomalous Transport Module (MMM), GENRAY/CQL3D (Lower Hybrid Wave [LHW]), and NUBEAM (Neutral Beam Injection [NBI]). Additionally, the transport solver has been coupled with both fixed-boundary and free-boundary equilibrium solvers. This study demonstrates the development and testing of model-based optimal feedback controllers in COTSIM simulations. These controllers regulate key plasma properties crucial for advanced tokamak scenarios, including the safety factor (<span><math><mi>q</mi></math></span>) at various spatial locations, plasma internal energy (<span><math><mi>W</mi></math></span>), normalized beta (<span><math><msub><mrow><mi>β</mi></mrow><mrow><mi>N</mi></mrow></msub></math></span>), and internal inductance (<span><math><msub><mrow><mi>l</mi></mrow><mrow><mi>i</mi></mrow></msub></math></span>). Control actuators include plasma current, plasma density, low-frequency (2.45 GHz) and high-frequency (4.60 GHz) LHW powers, and individual NBI powers. To validate these control algorithms, experimental testing has been conducted on EAST. Results from simulations and experiments demonstrate the ability to regulate scenario-defining plasma properties, suggesting COTSIM’s utility as a tool for advanced tokamak control development.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114969"},"PeriodicalIF":1.9,"publicationDate":"2025-03-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685164","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}

引用次数: 0