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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 Q1 NUCLEAR SCIENCE & TECHNOLOGY 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

The ITER Electron Cyclotron Heating and Current Drive (ECH) plays a pivotal role in heating and controlling fusion plasmas, with the Steering Mirrors being a crucial component of this actuator. A representative model of the ECH is compulsory in the development and validation of the Plasma Control System (PCS). This manuscript aims to propose a Control-Oriented model of the Steering Mirrors based on the design tested at the Swiss Plasma Centre. In this design a steering mirror rotates on some frictionless flexure pivots due to the action of a set of externally pressurized bellows acting against pre-compressed springs. This system is referred to as the Steering Mirror Assembly (SMA). The adherence of the model is tested by comparing the simulations with the experimental results, while considering ITER’s most recent requirements. Performances, generally increased in terms of accuracy, are in line with the prototype’s results.

热核实验堆电子回旋加速器加热和电流驱动器(ECH)在加热和控制聚变等离子体方面发挥着关键作用,而转向镜则是该驱动器的重要组成部分。在开发和验证等离子体控制系统(PCS)的过程中,必须要有一个具有代表性的 ECH 模型。本手稿旨在以瑞士等离子体中心测试的设计为基础,提出一个面向控制的转向镜模型。在这种设计中,转向镜在一组外部加压波纹管与预压弹簧的作用下,在一些无摩擦挠性枢轴上旋转。该系统被称为转向镜组件(SMA)。考虑到热核实验堆的最新要求,通过将模拟结果与实验结果进行比较,对模型的一致性进行了测试。在精度方面普遍提高的性能与原型结果一致。
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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 Q1 NUCLEAR SCIENCE & TECHNOLOGY 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

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 Nb3Sn 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 Nb3Sn 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 Nb3Sn layer coil.

中国科学院等离子体物理研究所(ASIPP)正在建设超导导体试验装置,以评估工程技术的可靠性和聚变反应堆运行环境下的安全运行。由于该试验装置的铌3硒层线圈采用了风amp的制造工艺,作为匝间绝缘材料的高强度玻璃纤维在经过665℃高温热处理后会发生碳化,从而降低绕组的机械性能和电气性能。为改善玻璃纤维热处理后的性能,开发了高强度玻璃纤维表面脱碳改性工艺。通过线圈绕组径向压力测试和 VPI 样品性能测试,验证了所开发的玻璃纤维带处理工艺能够满足层状 Nb3Sn 超导磁体的制造工艺要求。该处理技术已成功应用于实验磁体的制造,为大型 Nb3Sn 层线圈的绝缘制造提供了技术支持。
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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 Q1 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-10-24 DOI: 10.1007/s10894-024-00470-3
Joseph Farmer, Ethan Smith, William Bennett, Ryan McClarren

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.

辐射传热是高能量密度物理学和惯性聚变的基本过程。准确预测马沙克波在各种材料特性和驱动条件下的行为对这些系统的设计和分析至关重要。传统的数值求解器和分析近似往往在精度和计算效率方面面临挑战。在这项工作中,我们提出了一种使用傅立叶神经算子 (FNO) 建立马沙克波模型的新方法。我们开发了两个基于 FNO 的模型:(1) 一个基础模型,该模型根据 Hammer & Rosen (2003) 广泛使用的分析模型,学习驱动条件与材料属性之间的映射,以获得近似解;(2) 一个模型,该模型通过学习映射,获得更精确的数值解,从而纠正分析近似解的不准确性。我们的研究结果证明了 FNOs 强大的泛化能力,与基础分析模型相比,预测精度有了显著提高。
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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 Q1 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-10-16 DOI: 10.1007/s10894-024-00467-y
A. Salar Elahi, M. Ghoranneviss
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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 Q1 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-10-12 DOI: 10.1007/s10894-024-00466-z
A. Salar Elahi, M. Ghoranneviss
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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 Q1 NUCLEAR SCIENCE & TECHNOLOGY 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

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.

开场线电流是直流螺旋注入等离子体启动的固有特性,对用标准重构分析推断等离子体平衡构成挑战。局部螺旋注入(LHI)是直流螺旋注入的一种类型,它使用小型模块化电流源,沿着螺旋场线驱动无力电流,以产生托卡马克等离子体。LHI 期间的 MHD 建模和磁场测量结果表明,注入的电流流在核心环形等离子体的外侧边缘保持相干的螺旋结构,该等离子体在环形平均意义上类似于托卡马克。为了提取核心等离子体的平衡特性,用标准的 Grad-Shafranov 平衡代码拟合了校正注入电流流贡献的外部磁诊断。描述了从诊断信号中估计和减去磁流贡献的迭代方法,并将其应用于模型平衡数据库,以减少磁流带来的系统误差。通常经过 2 到 4 次迭代就能达到收敛,推导出的平衡参数与规定的轴对称核心值相匹配,在估计的实验不确定性范围内。当来自流的净环形卷积电流与堆芯等离子体电流之比小于 0.2 时,堆芯参数就能得到精确恢复,而这在大多数实验中通常都能满足要求。
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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 Q1 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-10-12 DOI: 10.1007/s10894-024-00468-x
A. Rahimirad, M. Emami, M. Ghoranneviss, A. Salar Elahi
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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 Q1 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-10-12 DOI: 10.1007/s10894-024-00469-w
Ahmad Salar Elahi
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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 Q1 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-10-09 DOI: 10.1007/s10894-024-00462-3
S. Moniri, M. Ghoranneviss, M. R. Hantehzadeh, A. Salar Elahi
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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 Q1 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-10-09 DOI: 10.1007/s10894-024-00461-4
Naima Amrani, Cafer Mert Yeşilkanat, Serkan Akkoyun

This study focuses on leveraging powerful machine learning approaches to determine neutron- alpha reaction cross-sections within the 14–15 MeV energy range. The investigation utilizes an experimental dataset comprising measurements of 133 nuclei concerning (n, α) reaction cross- sections. These data are divided into training and validation subsets, following established protocols, with 80% allocated for model training and 20% for testing. Key nucleus characteristics, including neutron number (N), mass number (A), and symmetry representation [(N-Z)²/A], were used as input variables for the machine learning models. SVR and XGBoost methods showed superior performance among the other machine learning methods used in the present study. In addition, a machine learning based online calculation tool was developed to estimate the reaction cross section.

这项研究的重点是利用强大的机器学习方法来确定 14-15 MeV 能量范围内的中子-α 反应截面。研究利用了一个实验数据集,其中包括对 133 个原子核的(n,α)反应截面的测量结果。这些数据按照既定规程分为训练子集和验证子集,其中 80% 用于模型训练,20% 用于测试。关键核特征,包括中子数(N)、质量数(A)和对称性表示[(N-Z)²/A],被用作机器学习模型的输入变量。在本研究使用的其他机器学习方法中,SVR 和 XGBoost 方法表现出更优越的性能。此外,还开发了一种基于机器学习的在线计算工具来估算反应截面。
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Journal of Fusion Energy
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