Journal of Fusion Energy最新文献

Preliminary Control-Oriented Modeling of the ITER Steering Mirror Assembly and Local Control System in the Electron Cyclotron Heating & Current Drive Actuator 热核实验堆转向镜组件和电子回旋加速器加热与电流驱动致动器局部控制系统的初步控制导向建模

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-10-29 DOI: 10.1007/s10894-024-00465-0

G. Grapow, T. Ravensbergen, M. D’Onorio, F. Pesamosca, A. Vu, G. Carannante

引用次数: 0

Research on Insulation Technology for Nb3Sn Layer Coil of Superconducting Conductor Testing Facility 超导导体测试设备 Nb3Sn 层线圈绝缘技术研究

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-10-29 DOI: 10.1007/s10894-024-00471-2

Yuanyuan Ma, Bozhou Huang, Yongzheng Yao, Houxiang Han, Changneng Zhang, Lei Wu, Yi Shi

{"title":"Research on Insulation Technology for Nb3Sn Layer Coil of Superconducting Conductor Testing Facility","authors":"Yuanyuan Ma, Bozhou Huang, Yongzheng Yao, Houxiang Han, Changneng Zhang, Lei Wu, Yi Shi","doi":"10.1007/s10894-024-00471-2","DOIUrl":"10.1007/s10894-024-00471-2","url":null,"abstract":"<div><p>The Superconducting Conductor Testing Facility, which is developed to evaluate the reliability of engineering technology and safe operation in a fusion reactor operation environment, is under construction by the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP). Since the Nb<sub>3</sub>Sn layer coil of this test facility adopts the manufacturing process of the wind & react, the high-strength glass fiber used as the inter-turn insulation material will carbonize after high-temperature heat treatment at 665℃, thereby reducing the mechanical and electrical properties of the winding. The surface decarburization and modification process of high-strength glass fiber was developed to improve the properties of glass fiber after heat treatment. It is verified that the developed glass fiber tape treatment process can meet manufacturing process requirements of layered Nb<sub>3</sub>Sn superconducting magnets through the coil winding radial pressure test and VPI sample performance test. This processing technology has been successfully applied in the manufacturing of experimental magnets, providing technical support for the insulation manufacturing of a large Nb<sub>3</sub>Sn layer coil.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"43 2","pages":""},"PeriodicalIF":1.9,"publicationDate":"2024-10-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142524491","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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 Energy Density Radiative Transfer in the Diffusion Regime with Fourier Neural Operators 利用傅立叶神经算子实现扩散状态下的高能量密度辐射传输

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-10-24 DOI: 10.1007/s10894-024-00470-3

Joseph Farmer, Ethan Smith, William Bennett, Ryan McClarren

{"title":"High Energy Density Radiative Transfer in the Diffusion Regime with Fourier Neural Operators","authors":"Joseph Farmer, Ethan Smith, William Bennett, Ryan McClarren","doi":"10.1007/s10894-024-00470-3","DOIUrl":"10.1007/s10894-024-00470-3","url":null,"abstract":"<div><p>Radiative heat transfer is a fundamental process in high energy density physics and inertial fusion. Accurately predicting the behavior of Marshak waves across a wide range of material properties and drive conditions is crucial for design and analysis of these systems. Conventional numerical solvers and analytical approximations often face challenges in terms of accuracy and computational efficiency. In this work, we propose a novel approach to model Marshak waves using Fourier Neural Operators (FNO). We develop two FNO-based models: (1) a base model that learns the mapping between the drive condition and material properties to a solution approximation based on the widely used analytic model by Hammer & Rosen (2003), and (2) a model that corrects the inaccuracies of the analytic approximation by learning the mapping to a more accurate numerical solution. Our results demonstrate the strong generalization capabilities of the FNOs and show significant improvements in prediction accuracy compared to the base analytic model.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"43 2","pages":""},"PeriodicalIF":1.9,"publicationDate":"2024-10-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-024-00470-3.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142519003","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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

Retraction Note: Determination of the Plasma Internal Inductance and Evaluation of its Effects on Plasma Horizontal Displacement in IR-T1 Tokamak 撤回说明：IR-T1 托卡马克中等离子体内部电感的测定及其对等离子体水平位移影响的评估

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-10-16 DOI: 10.1007/s10894-024-00467-y

A. Salar Elahi, M. Ghoranneviss

引用次数: 0

Retraction Note: Differences Between the Toroidal and Poloidal Flux Loops in the Measurement of Plasma Position in Tokamaks 撤回说明：测量托卡马克等离子体位置时环形和极环形通量环的差异

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-10-12 DOI: 10.1007/s10894-024-00466-z

A. Salar Elahi, M. Ghoranneviss

引用次数: 0

Effects of Injected Current Streams on MHD Equilibrium Reconstruction of Local Helicity Injection Plasmas in a Spherical Tokamak 注入电流流对球形托卡马克中局部螺旋注入等离子体的 MHD 平衡重构的影响

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-10-12 DOI: 10.1007/s10894-024-00460-5

J. D. Weberski, M. W. Bongard, S. J. Diem, R. J. Fonck, J. A. Goetz, M. D. Nornberg, J. A. Reusch, C. E. Schaefer, A. C. Sontag

{"title":"Effects of Injected Current Streams on MHD Equilibrium Reconstruction of Local Helicity Injection Plasmas in a Spherical Tokamak","authors":"J. D. Weberski, M. W. Bongard, S. J. Diem, R. J. Fonck, J. A. Goetz, M. D. Nornberg, J. A. Reusch, C. E. Schaefer, A. C. Sontag","doi":"10.1007/s10894-024-00460-5","DOIUrl":"10.1007/s10894-024-00460-5","url":null,"abstract":"<div><p>Open field line currents are intrinsic to DC helicity injection plasma startup and pose a challenge for inferring the plasma equilibrium with standard reconstruction analysis. Local helicity injection (LHI) is a type of DC helicity injection which uses small, modular current sources to drive force-free current along helical field lines to produce tokamak plasmas. MHD modeling and magnetic measurements during LHI indicate the injected current streams remain coherent as helical structures on the outboard edge of a core toroidal plasma that is tokamak-like in a toroidally averaged sense. To extract core plasma equilibrium properties, external magnetic diagnostics corrected for contributions from the injected current streams are fitted by a standard Grad-Shafranov equilibrium code. An iterative approach for estimating and subtracting the stream contributions from the diagnostic signals is described and applied to a model equilibrium database to reduce systematic errors introduced by the streams. Convergence is usually attained with 2 to 4 iterations, with derived equilibrium parameters matching the prescribed axisymmetric core values to within estimated experimental uncertainties. Accurate recovery of core parameters occurs when the ratio of the net toroidal windup current from the streams to the core plasma current is less than 0.2, which is typically satisfied in most experiments.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"43 2","pages":""},"PeriodicalIF":1.9,"publicationDate":"2024-10-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-024-00460-5.pdf","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142411493","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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

Retraction Note: Demonstration of Shafranov Shift by the Simplest Grad–Shafranov Equation Solution in IR-T1 Tokamak 撤稿说明：用 IR-T1 托卡马克中最简单的格拉德-沙弗诺夫方程解法证明沙弗诺夫偏移

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-10-12 DOI: 10.1007/s10894-024-00468-x

A. Rahimirad, M. Emami, M. Ghoranneviss, A. Salar Elahi

引用次数: 0

Retraction Note: Multipole Moments Based Study on Determination of Toroidal Plasma Equilibrium Position and Shift 撤回说明：基于多极矩的环形等离子体平衡位置和位移测定研究

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-10-12 DOI: 10.1007/s10894-024-00469-w

Ahmad Salar Elahi

引用次数: 0

Retraction Note: Nano-Scale Precipitates of Reduced Activation Steels for the Application of Nuclear Fusion Reactors 撤稿说明：用于核聚变反应堆的还原活化钢的纳米级沉淀物

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-10-09 DOI: 10.1007/s10894-024-00462-3

S. Moniri, M. Ghoranneviss, M. R. Hantehzadeh, A. Salar Elahi

引用次数: 0

Neutron-Alpha Reaction Cross Section Determination by Machine Learning Approaches 通过机器学习方法确定中子-阿尔法反应截面

IF 1.9 4区工程技术

Journal of Fusion Energy Pub Date : 2024-10-09 DOI: 10.1007/s10894-024-00461-4

Naima Amrani, Cafer Mert Yeşilkanat, Serkan Akkoyun

引用次数: 0