Fusion Engineering and Design最新文献_第6页

Kernel ridge regression estimation of high-frequency signals for nuclear fusion diagnostics 核聚变诊断高频信号的核脊回归估计

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-06-12 DOI: 10.1016/j.fusengdes.2025.115261

A. Pereira , S. Moreno , J. Rodríguez , M. Villalba

{"title":"Kernel ridge regression estimation of high-frequency signals for nuclear fusion diagnostics","authors":"A. Pereira , S. Moreno , J. Rodríguez , M. Villalba","doi":"10.1016/j.fusengdes.2025.115261","DOIUrl":"10.1016/j.fusengdes.2025.115261","url":null,"abstract":"<div><div>Estimating missing signals in plasma measurements is a significant challenge, particularly in fusion plasma devices where high-frequency temporal evolution signals provide valuable insight into the behavior of plasma. Indeed, occasional signal absence can impact to misfunction of other active diagnostics, leading to misinterpretation of the plasma state and inaccurate management of related control systems that affect the overall performance of the device. Therefore, the replacement of synthetic and accurate signals is a crucial aspect for system performance and reliability in fusion diagnostics, particularly when original signals are missing or erroneous. Precise prediction of high-frequency signals refers to time-series synthetic data that are modelled at an extremely fine scale. Due to the large number of samples, high frequency observations generally contain a large amount of data and most forecasting techniques based on dimensionality reduction or feature selection are not applicable as valuable information is lost before training periods. Besides, many real-time signals such as those in ITER, are non-stationary, meaning that their spectral content changes with time. In the current work a novel algorithm is presented based on kernel ridge regression (KRR) confidence machine. It provides a balance between computational efficiency and high accuracy across the entire frequency spectrum.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115261"},"PeriodicalIF":1.9,"publicationDate":"2025-06-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144271498","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

Self-consistent equilibrium and transport simulations for NSTX-U plasmas enhanced via machine learning surrogate models 通过机器学习代理模型增强NSTX-U等离子体的自洽平衡和输运模拟

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-06-12 DOI: 10.1016/j.fusengdes.2025.115201

Brian Leard , Tariq Rafiq , Ian Ward , Franco Galfrascoli , Eugenio Schuster , Alexei Pankin , Marina Gorelenkova

{"title":"Self-consistent equilibrium and transport simulations for NSTX-U plasmas enhanced via machine learning surrogate models","authors":"Brian Leard , Tariq Rafiq , Ian Ward , Franco Galfrascoli , Eugenio Schuster , Alexei Pankin , Marina Gorelenkova","doi":"10.1016/j.fusengdes.2025.115201","DOIUrl":"10.1016/j.fusengdes.2025.115201","url":null,"abstract":"<div><div>The Control-Oriented Transport SIMulator (COTSIM) is an advanced equilibrium and transport code designed for simulating tokamak discharges at computational speeds suitable for control applications. COTSIM’s modular framework enables users to select models that balance accuracy with speed according to specific needs, allowing the code to operate from fast to faster-than-real-time performance levels. This work presents recent enhancements to COTSIM’s predictive accuracy for NSTX-U scenarios, achieved by integrating neural-network-based surrogate models and self-consistent equilibrium calculations. To improve source deposition predictions, a surrogate model for NUBEAM has been incorporated. Additionally, a surrogate model for the Multi-Mode Module (MMM) now supports predictions of anomalous thermal, momentum, and particle diffusivities—key factors for modeling the evolution of temperature and rotation. Each surrogate model was specifically trained for the NSTX-U operational regime to enhance COTSIM’s accuracy while maintaining computational efficiency. Moreover, COTSIM now couples fixed-boundary equilibrium solvers with its transport solvers, enabling self-consistent predictions of plasma profiles and equilibrium evolution over the discharge. Simulation results demonstrate strong agreement between COTSIM and TRANSP predictions for NSTX-U discharges. These substantial advancements expand COTSIM’s utility in model-based control applications for NSTX-U. Potential applications include simultaneous optimization of equilibrium and transport scenarios, integration into digital twins, real-time profile estimation (e.g., temperature and rotation) from limited or noisy measurements, and advanced feedback-based scenario control.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115201"},"PeriodicalIF":1.9,"publicationDate":"2025-06-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144262726","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

Design of strain measuring system in ultra-high vacuum environment for JT-60SA JT-60SA超高真空环境下应变测量系统设计

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-06-12 DOI: 10.1016/j.fusengdes.2025.115245

Shigetoshi Nakamura, Manabu Takechi, Satoshi Yamamoto, Akihiko Isayama, Go Matsunaga

引用次数: 0

Design of the upgraded Glow Discharge Cleaning system for RFX-mod2 RFX-mod2升级版辉光放电清洗系统设计

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-06-11 DOI: 10.1016/j.fusengdes.2025.115228

M. Fadone , R. Cavazzana , S. Ciufo , L. Grando , S. Peruzzo , A. Rizzolo , M. Zuin

引用次数: 0

Compensating control delays in the CFETR Multi-Purpose Overload Robot for divertor maintenance by using transformer-enhanced Temporal Convolutional Network 基于变压器增强时间卷积网络的CFETR多用途过载机器人改道维修控制延迟补偿

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-06-11 DOI: 10.1016/j.fusengdes.2025.115183

Chenhui Wan , Zibo Qi , Hongbin Huang , Jie Liu , Youmin Hu , Hongtao Pan , Yong Cheng , Yang Cheng , Zhongxu Hu

{"title":"Compensating control delays in the CFETR Multi-Purpose Overload Robot for divertor maintenance by using transformer-enhanced Temporal Convolutional Network","authors":"Chenhui Wan , Zibo Qi , Hongbin Huang , Jie Liu , Youmin Hu , Hongtao Pan , Yong Cheng , Yang Cheng , Zhongxu Hu","doi":"10.1016/j.fusengdes.2025.115183","DOIUrl":"10.1016/j.fusengdes.2025.115183","url":null,"abstract":"<div><div>Communication delays in the CFETR (China Fusion Engineering Test Reactor) Multi-Purpose Overload Robot (CMOR), designed for divertor maintenance, significantly degrade control precision and operational reliability. This study proposed a Transformer-enhanced Temporal Convolutional Network (TransformerTCN) to address these delays. By integrating the local temporal feature extraction of Temporal Convolutional Networks (TCNs) with the long-range dependency modeling of Transformer’s self-attention mechanism, TransformerTCN accurately predicted future robot states and dynamically adjusted control commands. Validation in ROS-based simulations demonstrated that TransformerTCN outperformed traditional models, achieving a Mean Squared Error (MSE) of 0.002 and an <span><math><msup><mrow><mi>R</mi></mrow><mrow><mn>2</mn></mrow></msup></math></span> score of 0.994, showcasing its superior accuracy and robustness. These results highlight TransformerTCN as a powerful solution for delay compensation in robotic systems operating in challenging nuclear fusion environments.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115183"},"PeriodicalIF":1.9,"publicationDate":"2025-06-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144254043","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

A multi-degree-of-freedom water hydraulic manipulator in nuclear applications: Design and experiments 多自由度水液压机械臂在核能中的应用：设计与实验

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-06-10 DOI: 10.1016/j.fusengdes.2025.115204

Weidi Huang , Zhiwen Pan , Changhong Guo , Min Cheng , Ruiheng Jia , Zhiwei Chen , Junhui Zhang , Bing Xu

{"title":"A multi-degree-of-freedom water hydraulic manipulator in nuclear applications: Design and experiments","authors":"Weidi Huang , Zhiwen Pan , Changhong Guo , Min Cheng , Ruiheng Jia , Zhiwei Chen , Junhui Zhang , Bing Xu","doi":"10.1016/j.fusengdes.2025.115204","DOIUrl":"10.1016/j.fusengdes.2025.115204","url":null,"abstract":"<div><div>In nuclear applications, water hydraulic manipulators present notable advantages in terms of safety and environmental compatibility compared to oil hydraulic alternatives. However, traditional Valve-Controlled Hydraulic Cylinder Systems (VCHCS) suffer from severe leakage, and existing new designs add system complexity. These design flaws adversely affect the control accuracy of the manipulator. To address these issues, a novel multi-degree-of-freedom water hydraulic manipulator for nuclear applications is proposed in this study, including system design, controller design and experiments. In the system design, the servo valve in VCHCS is replaced by two ball-type proportional valves per joint, which avoids severe leakage due to their sealing properties. Additionally, a pressure-reducing valve and a relief valve shared by three joints achieve fewer valves, minimizing potential leakage points while reducing system complexity. Further, to improve the control accuracy of the new system, a nonlinear control strategy based on virtual decomposition control (VDC) is designed. The VDC strategy addresses the hydraulic-kinematic coupling and nonlinearities by decomposing the manipulator into closed-chain subsystems and integrating fluid dynamics into the rigid-body dynamics model. Experimental results demonstrate tracking accuracy improvements of 29.2% in the X direction and 70.2% in the Y direction, where X is defined as the forward direction and Y is defined as the upward direction of the end clamp. Finally, underwater task operation experiments show that the tracking errors are confined within 3 mm (X) and 4 mm (Y), demonstrating the practical application of the proposed system and control strategy.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115204"},"PeriodicalIF":1.9,"publicationDate":"2025-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144241852","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

Vacuum commissioning and operation result after the KSTAR PFC upgrade KSTAR PFC升级后的真空调试和运行结果

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-06-10 DOI: 10.1016/j.fusengdes.2025.115249

Kwangpyo Kim , Hyunmyung Lee , Hyung ho Lee , Koung Moon Kim , Hyunseok Kim , Jeongwon Lee , H. Schamis , E.P. Gilson , Jae-in Song , Nam-yong Joung , Soo-hyeon Park

引用次数: 0

Initial plasma achieved within engineering constraints in the PLATO tokamak 在PLATO托卡马克的工程限制内实现的初始等离子体

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-06-10 DOI: 10.1016/j.fusengdes.2025.115222

T. Nishizawa , Y. Nagashima , C. Moon , D. Nishimura , T.-K. Kobayashi , T. Ido , T. Suetsugu , T. Tokuzawa , K. Yamasaki , T. Yamada , S. Inagaki , T. Onchi , S. Kato , M. Murayama , T. Kobayashi , A. Shimizu , K. Kikuta , R. Hayashi , D. Di Matteo , A. Fujisawa

{"title":"Initial plasma achieved within engineering constraints in the PLATO tokamak","authors":"T. Nishizawa , Y. Nagashima , C. Moon , D. Nishimura , T.-K. Kobayashi , T. Ido , T. Suetsugu , T. Tokuzawa , K. Yamasaki , T. Yamada , S. Inagaki , T. Onchi , S. Kato , M. Murayama , T. Kobayashi , A. Shimizu , K. Kikuta , R. Hayashi , D. Di Matteo , A. Fujisawa","doi":"10.1016/j.fusengdes.2025.115222","DOIUrl":"10.1016/j.fusengdes.2025.115222","url":null,"abstract":"<div><div>In order to save flux consumption and lessen engineering requirements, the achievable toroidal loop voltage tends to be lowered in modern tokamaks. In such devices, careful optimization of the plasma startup scenario is often required to achieve a successful tokamak discharge. The PLATO tokamak, which is recently built at Kyushu University, also faces challenges in the plasma startup. PLATO employs an air-cored central solenoid that limits the loop voltage and creates stray magnetic fields. In addition, only simple capacitor banks with modest maximum charging voltages are available for the generation of the poloidal magnetic and toroidal electric fields in the initial operation. To realize the breakdown and plasma current ramp-up under those constraints, the configuration of coils and capacitor bank settings has been optimized to produce sufficient loop voltage while minimizing the stray field inside the vacuum chamber at the onset of the discharge. Through this optimization, a tokamak discharge with a plasma current of 30 kA and a pulse duration of 20 ms has been achieved.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115222"},"PeriodicalIF":1.9,"publicationDate":"2025-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144254042","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

Bubble dynamics in Magnetohydrodynamics conditions: Numerical simulation and flow characterization for high density ratio mixture 磁流体动力学条件下的气泡动力学：高密度比混合物的数值模拟和流动特性

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-06-10 DOI: 10.1016/j.fusengdes.2025.115215

Sonia Pignatiello, Simone Siriano, Alessandro Tassone

{"title":"Bubble dynamics in Magnetohydrodynamics conditions: Numerical simulation and flow characterization for high density ratio mixture","authors":"Sonia Pignatiello, Simone Siriano, Alessandro Tassone","doi":"10.1016/j.fusengdes.2025.115215","DOIUrl":"10.1016/j.fusengdes.2025.115215","url":null,"abstract":"<div><div>Many Breeding Blanket (BB) concepts envision the use of a liquid metal (LM) alloy containing lithium to fulfill the functions of tritium production through the tritium breeding reaction, which produces helium as a by-product. This, under appropriate conditions, can nucleate, aggregate into bubbles that can be transported within the main fluid flow. The study of the bubbles transport within the magnetohydrodynamic (MHD) LM flow is mandatory to assess the impact on the BB performance and safety, due to their potential accumulation in some part of the system.</div><div>In this study, the dynamics of bubbles in MHD conditions is examined using a custom OpenFOAM solver called mhdInterFoam (mIF). This code is capable of modeling a two-phase MHD flow of incompressible, immiscible, and isothermal fluids using the Volume of Fluid (VoF) method. The code has been validated against experimental data, producing results in good agreement with the reference for several bubble diameters (Eötvös number, Eo <span><math><mo>≈</mo></math></span> 1.5 - 8.5) and magnetic fields up to 1.5 T (Hartmann number, Ha <span><math><mo>≈</mo></math></span> 0 - 220).</div><div>Specifically, the magnetic field effects on the bubbles regime of motion are analyzed and the characteristics of the LM flow around the bubbles are presented. The study is performed considering the distribution of fundamental physical quantities, which are challenging to investigate through experimental studies alone.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115215"},"PeriodicalIF":1.9,"publicationDate":"2025-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144254041","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

Feasibility study of the high-power millimeter-wave collective Thomson scattering diagnostic system on HL-3 tokamak HL-3托卡马克上大功率毫米波集体汤姆逊散射诊断系统的可行性研究

IF 1.9 3区工程技术

Fusion Engineering and Design Pub Date : 2025-06-09 DOI: 10.1016/j.fusengdes.2025.115242

Feng Zhang, Mei Huang, Gangyu Chen, Wanxin Zheng, Cheng Chen, Guoyao Fan, He Wang

{"title":"Feasibility study of the high-power millimeter-wave collective Thomson scattering diagnostic system on HL-3 tokamak","authors":"Feng Zhang, Mei Huang, Gangyu Chen, Wanxin Zheng, Cheng Chen, Guoyao Fan, He Wang","doi":"10.1016/j.fusengdes.2025.115242","DOIUrl":"10.1016/j.fusengdes.2025.115242","url":null,"abstract":"<div><div>Collective Thomson scattering (CTS) is an important diagnostic technique which can be applied to measure the velocity distribution of fast ions within fusion plasmas with high temporal and spatial resolutions. <em>The feasibility of diagnosing fast ions in the HL-3 tokamak by high-power millimeter-wave CTS was studied</em>. Specifically, the study examined the effects of various factors, including the frequency of the probing wave, scattering geometry and plasma parameters, on the scattering spectrum. Among the various plasma parameters, this study specifically focused its analysis on the effects of electron density, electron temperature, bulk ion temperature, and fast ion density on the scattering spectrum and, consequently, on the inference of the fast ion distribution. Finally, a CTS diagnostic system for the HL-3 tokamak was designed. In this setup, the 140 GHz and 1 MW gyrotron served as the probe beam source, the diagnostic system could achieve temporal and spatial resolutions of approximately 200 µs and 100 mm, respectively.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115242"},"PeriodicalIF":1.9,"publicationDate":"2025-06-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144241851","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