Fusion Engineering and Design最新文献_第2页

Development and optimization of flow distribution test sections for CFETR WCCB blanket CFETR WCCB毯流分布试验段的研制与优化

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-01-20 DOI: 10.1016/j.fusengdes.2026.115636

Yifan Zhang , Kecheng Jiang , Lei Chen , Xuebin Ma , Songlin Liu

To address the risk of flow non-uniformity in the Water-Cooled Ceramic Breeder (WCCB) blanket of the China Fusion Engineering Test Reactor (CFETR), three acrylic-based test sections were developed for flow visualization experiments: (1) 1:5 scaled outboard segment model featuring hydraulically equivalent pipes regulated by pinch valves, (2) first wall (FW) model with 39 U-shaped cooling channels, and (3) breeding zone (BZ) model comprising four groups of 29 cooling tubes each. A key contribution of this work is the development of the scaling strategy for outboard segment test section based on equal Euler number (Eu) and cooling water velocity matching, resolving scaling conflicts between the high-pressure/high-temperature prototype and the ambient-condition test section. Computational Fluid Dynamics (CFD) optimization showed that the maximum deviation in blanket module between the 1:5 scaled outboard segment, and the full-scale prototype is 6.1%. For FW test section, geometric optimizations—including inlet pipe downsizing and manifold wall thinning—reduced the maximum deviation in channel flow distribution to 0.51%, while the cooling water streamlines in the manifold closely matched those of the prototype. Mass flow rates in the cooling channels are measured using both Doppler-based ultrasonic flowmeters and Particle Image Velocimetry (PIV), enabling cross-validation and detailed characterization of the internal flow field. This test section design provides high-fidelity experimental support for the hydraulic optimization of the CFETR WCCB blanket.

为了解决中国核聚变工程试验堆（CFETR）水冷陶瓷增殖堆（WCCB）包层中流动不均匀的风险，设计了3个基于亚烯的试验段进行流动可视化实验：(1)采用夹管调节水力等效管道的1:5比例外段模型，(2)带有39个u型冷却通道的第一壁（FW）模型，以及(3)包含4组29个冷却管的繁殖区（BZ）模型。本工作的一个关键贡献是基于等欧拉数（Eu）和冷却水速度匹配的舷外段试验段结垢策略的发展，解决了高压/高温样机与环境条件试验段之间的结垢冲突。计算流体动力学（CFD）优化结果表明，包层模块中1:5比例外段与全尺寸原型之间的最大偏差为6.1%。在FW试验段，通过减小进气管尺寸和管汇壁厚度等几何优化，使通道流量分布最大偏差减小到0.51%，而管汇内冷却水流线与原型机的流线基本吻合。使用基于多普勒的超声波流量计和粒子图像测速仪（PIV）测量冷却通道中的质量流量，从而实现内部流场的交叉验证和详细表征。该试验段设计为CFETR WCCB毯层水力优化提供了高保真的实验支撑。

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引用次数: 0

Tritium depth distribution measurement by using chemical etching and surface washing technique for structural material of the ICF target chamber 利用化学蚀刻和表面清洗技术测量ICF靶室结构材料的氚深度分布

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-01-19 DOI: 10.1016/j.fusengdes.2026.115634

Jingquan Xia , Zhilin Chen , Yang Yang , Zhu An

The tritium depth distribution in the structural material (i.e., the 5083 aluminum alloy (Al5083)) of the inertial confinement fusion (ICF) target chamber is a key basis for evaluating radiation protection and environmental hazards. Given the characteristic of shallow tritium ion implantation depth in the Al5083, this study aimed to establish a high-resolution measurement method. A method for measuring the tritium depth distribution in Al5083 was established by coupling the ZnCl₂ surface washing (SW) method and the layer-by-layer chemical etching (LLCE) method. Firstly, the effects of etchant type, acid-to-water ratio, temperature, and etching period on measurement resolution in the LLCE method were systematically investigated, and the depth resolution was controlled within 30–50 nm, meeting the requirement for high-resolution measurement of shallowly implanted tritium. Secondly, the reliability of two correction methods for liquid scintillation counting (LSC) measurement of tritium-containing zinc solution was verified using the internal standard method. It was confirmed that the SW method can accurately separate and quantitatively determine the total amount of surface-adsorbed tritium in the Al5083, providing a key method to distinguish between surface-adsorbed tritium and bulk-retained tritium. Experiments on tritium-loaded Al5083 sample by implantation with an average incident energy of 7.5 keV and a fluence of 4.5 × 10¹² ions/cm² showed that the surface-adsorbed tritium accounts for 1.8% of the total tritium amount with a high concentration (∼10⁸ Bq/cm³), and 80% of the tritium in the bulk is distributed within 200 nm of the surface. The standardized measurement method established in this study provides reliable technical support for evaluating the retention and migration of tritium in the structural material of the ICF device.

惯性约束聚变（ICF）靶室结构材料（即5083铝合金（Al5083））中的氚深度分布是评价辐射防护和环境危害的重要依据。鉴于Al5083中氚离子注入深度较浅的特点，本研究旨在建立一种高分辨率的测量方法。采用ZnCl2表面洗涤（SW）法和逐层化学蚀刻（LLCE）法，建立了一种测量Al5083中氚深度分布的方法。首先，系统研究了LLCE法中蚀刻剂类型、酸水比、温度、蚀刻周期对测量分辨率的影响，将深度分辨率控制在30 ~ 50 nm，满足浅注入氚的高分辨率测量要求。其次，用内标法验证了两种含氚锌溶液液体闪烁计数（LSC）测量校正方法的可靠性。结果表明，该方法能够准确地分离和定量测定Al5083中表面吸附氚的总量，为区分表面吸附氚和体积保留氚提供了关键方法。在平均入射能量为7.5 keV、注入量为4.5 × 10¹²离子/cm²的负载氚Al5083样品上进行的实验表明，表面吸附的氚占总氚量的1.8%，浓度较高（~ 108 Bq/cm3），体体中80%的氚分布在距表面200 nm的范围内。本研究建立的标准化测量方法为评估氚在ICF器件结构材料中的滞留和迁移提供了可靠的技术支持。

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引用次数: 0

Investigation of the ultra-wideband polarizer for high power millimeter wave system 大功率毫米波系统超宽带偏振器的研究

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-01-15 DOI: 10.1016/j.fusengdes.2026.115630

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

As a crucial component of the electron cyclotron resonance heating (ECRH) system, the polarizer primarily serves to change the polarization characteristics of millimeter wave. In this study, an ultra-wideband polarization strategy based on two polarizers for the ECRH system is presented. By employing two identical sinusoidally grooved polarizers at a designated incident angle of 60°, it is possible to attain arbitrary polarization can be attained across an ultra-wideband frequency ranging from 99 GHz to 189 GHz. A ultra-wideband polarizer was devised and evaluated, and computational results indicate that the arbitrary polarization efficiency of the proposed method reaches at least 99.94%. According to this analysis, nearly every desired polarization state can be realized using the presented polarization strategy.

偏振器作为电子回旋共振加热（ECRH）系统的关键部件，主要用于改变毫米波的偏振特性。本文提出了一种基于双极化器的ECRH系统超宽带极化策略。通过在指定的60°入射角上使用两个相同的正弦波槽偏振器，可以在99 GHz至189 GHz的超宽带频率范围内获得任意偏振。设计并评估了一种超宽带偏振器，计算结果表明，该方法的任意极化效率达到99.94%以上。根据这一分析，使用所提出的极化策略几乎可以实现所有期望的极化状态。

引用次数: 0

Development of 3D simulation demonstration platform for tritium safety confinement of China fusion engineering test reactor 中国核聚变工程试验堆氚安全约束三维仿真演示平台的研制

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-01-15 DOI: 10.1016/j.fusengdes.2026.115629

Haixia Wang , Xuewei Fu , Zihui Yang , Qianchao Huo , Jie Yu

The China Fusion Engineering Test Reactor (CFETR) is a next-generation fusion reactor project independently designed and actively pursued by China. As the key radioactive source term of the CFETR, tritium safety is an important issue of nuclear safety. The tritium safety confinement system is one of the major systems in the CFETR tritium plant, and the study of tritium transport behavior in confinement system is of significant research interest. Supported by the National Key R&D Program, this study employs Unreal Engine (UE) as the 3D interactive simulation engine to construct a 3D simulation demonstration platform for tritium safety confinement of the CFETR. The Tokamak Exhaust Processing (TEP) System is selected as a representative case for simulation. Test results indicate that the platform enables smooth human-computer interaction, effectively visualizes tritium transport behavior under typical conditions, and provides an immersive 3D scene virtual roaming experience. Through dynamic demonstration of tritium transport under multiple conditions, the design principle of the CFETR tritium safety confinement system is effectively visualized, offering valuable insights for the future design of tritium confinement system in tritium plants.

中国聚变工程试验堆（CFETR）是中国自主设计并积极推进的新一代聚变反应堆项目。氚作为CFETR的关键放射源项，其安全性是核安全的重要问题。氚安全约束系统是CFETR氚厂的主要系统之一，对约束系统中氚输运行为的研究具有重要的研究意义。本研究在国家重点研发计划的支持下，采用虚幻引擎（UE）作为三维交互仿真引擎，构建了CFETR氚安全约束的三维仿真演示平台。选取托卡马克排气处理（TEP）系统作为仿真的代表案例。测试结果表明，该平台实现了流畅的人机交互，有效地可视化了典型条件下氚的输运行为，提供了沉浸式3D场景虚拟漫游体验。通过多种条件下氚输运的动态演示，有效地可视化了CFETR氚安全约束系统的设计原理，为今后氚厂氚约束系统的设计提供了有价值的见解。

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引用次数: 0

Proximal probe thermal desorption mass spectrometry for mapping lateral hydrogen isotope retention in metals 近端探针热解吸质谱法测定金属中氢同位素的横向保留

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-01-15 DOI: 10.1016/j.fusengdes.2026.115628

Qin Lei , Qiannan Yu , Jiaguan Peng , Yiwen Sun , Mengqi Zhang , Hanfeng Song , Hao Yin , Xiaolu Xiong , Sijie Hao , Yuhao Li , Xiuli Zhu , Lu Sun , Long Cheng , Yue Yuan , Guang-Hong Lu

The study of hydrogen isotopes (HIs) retention in fusion materials is crucial for the safe operation of fusion devices. This research developed the proximal probe thermal desorption mass spectrometry (PTDS) technique, a unique technique utilizing a probe to heat the specific micro-regions on the sample, to characterize lateral deuterium (D) retention in materials using deuterated tungsten. The temperature during the test was studied using an infrared camera, with the maximum probe tip temperature reaching approximately 2300 K and the temperature-affected region having a diameter of about 500 µm. PTDS testing of deuterated tungsten films prepared by magnetron sputtering revealed a uniform lateral distribution of D retention on the sample surface. Using PTDS, the estimated deuterium-to-tungsten (D/W) atomic ratio was approximately 0.146. PTDS testing of D plasma-exposed sample provided the lateral distribution characteristics of D retention, which were compared with the distribution of plasma flux showing consistent trends. Besides, D/W ratio in D plasma-exposed sample is about 6.40 × 10^–5 as estimated based on thermal desorption spectroscopy (TDS) measurement, indicating that the detection capability of the device reached the order of ∼10^–5. Furthermore, this technique is of potential in precise localization of measurement spots and future research will focus on enhancing the lateral spatial resolution and in situ application of PTDS on HIs transport studies during plasma exposure.

氢同位素在核聚变材料中的保留研究对核聚变装置的安全运行至关重要。本研究开发了近端探针热解吸质谱（PTDS）技术，这是一种利用探针加热样品上特定微区域的独特技术，用于表征氘化钨材料中的侧向氘(D)保留。使用红外摄像机对测试过程中的温度进行了研究，测头最高温度约为2300 K，温度影响区直径约为500µm。对磁控溅射制备的氘化钨薄膜进行PTDS测试，发现样品表面有均匀的横向D保留分布。使用PTDS，估计氘与钨（D/W）原子比约为0.146。D等离子体暴露样品的PTDS检测提供了D潴留的横向分布特征，与等离子体通量分布相比较，显示出一致的趋势。此外，通过热解吸光谱（TDS）测量，D等离子体暴露样品的D/W比约为6.40 × 10-5，表明该器件的检测能力达到了~ 10-5的量级。此外，该技术在测量点的精确定位方面具有潜力，未来的研究将集中在提高横向空间分辨率和原位应用PTDS在等离子体暴露过程中的he输运研究上。

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引用次数: 0

Linear model responses in forced flow cooling 强迫流动冷却中的线性模型响应

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-01-14 DOI: 10.1016/j.fusengdes.2025.115610

Giacomo Cavuoti , Francesca Cau , José Lorenzo , Alfredo Portone

The aim of this paper is to present a fast method capable of computing thermo-hydraulic transients in solid components that are cooled (or heated) by incompressible forced flow with or without external heating sources. By coupling the heat conduction equation in the solid volume to the heat transfer to the forced flow we derive a linearized mapping between the vector of input (control) quantities u(t) such as mass flow and inlet temperature to the vector of nodal temperature T(t) in the solid domain. A comparison between the newly developed code, which is finite volume based and a standard finite element-based code such as ANSYS is presented. Despite the significant reduction in CPU time, the finite-volume code well approximates the solid temperature field computed by ANSYS for the two cases considered here, i.e. the fusion power operation and vacuum vessel baking operation.

本文的目的是提出一种快速的方法，能够计算固体部件在有或没有外部热源的不可压缩强迫流冷却（或加热）时的热水力瞬态。通过将固体体积内的热传导方程与强制流动的传热耦合，我们导出了输入（控制）量向量u(t)之间的线性映射，例如质量流量和入口温度向量到固体域中的节点温度向量t (t)。并将新开发的基于有限体积的有限元计算程序与ANSYS等标准有限元计算程序进行了比较。尽管CPU时间显著减少，但有限体积代码很好地近似于本文考虑的两种情况下ANSYS计算的固体温度场，即核聚变操作和真空容器烘烤操作。

引用次数: 0

Strategies and solutions for engineering challenges during the assembly of divertor and position control coils in ADITYA-U tokamak ADITYA-U托卡马克转向器和位置控制线圈组装过程中工程挑战的策略和解决方案

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-01-13 DOI: 10.1016/j.fusengdes.2026.115615

Rohit Kumar , Vaibhav Ranjan , Harshita Raj , Kumarpal Jadeja , Kaushal Patel , R.L. Tanna , J. Ghosh

The ADITYA tokamak, a medium-sized device with a limiter configuration is upgraded to ADITYA-U tokamak with divertor configuration for shaped plasma operation. Three pairs of divertor coils and two pairs of position control coils are introduced in ADITYA-U tokamak. The strategy was focused on optimising the available space for new magnetic field coils installation without relying on the active cooling arrangements. The primary challenge was to install the coil along with the bus bar without any joints while utilizing the same conductor. The demountable TF coils in ADITYA-U tokamak simplified the feasibility for the new coils. The physical and technical boundary conditions were met using copper-based continuous transposed conductor (CTC) for the in-situ coil winding. This simple design is low cost and offers winding flexibility while ensuring accurate coil dimensions. A detailed description of the assembly procedure and solution to different engineering challenges during the fabrication of the divertor and position control coils are presented in this paper.

ADITYA托卡马克是一种具有限制器配置的中型设备，升级为ADITYA- u托卡马克，具有用于形等离子体操作的分流器配置。ADITYA-U型托卡马克采用了三对导流线圈和两对位置控制线圈。该策略的重点是优化新磁场线圈安装的可用空间，而不依赖于主动冷却安排。主要的挑战是安装线圈沿母线没有任何接头，同时使用相同的导体。ADITYA-U托卡马克中可拆卸的TF线圈简化了新线圈的可行性。采用铜基连续转置导体（CTC）进行原位线圈绕组，满足物理和技术边界条件。这种简单的设计成本低，并提供绕组灵活性，同时确保准确的线圈尺寸。本文详细介绍了转向器和位置控制线圈在制造过程中的装配过程和解决方案。

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引用次数: 0

Design of a high spatiotemporal resolution hard X-ray camera system on the HL-3 tokamak HL-3托卡马克高时空分辨率硬x射线相机系统设计

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-01-12 DOI: 10.1016/j.fusengdes.2026.115624

J.Q. Wang , Y.P. Zhang , Z.B. Wang , Y.X. Han , Z.H. Wang , J. Chen , Y. Yu , J. Zhang , C.Y. Zhao , H.Y. Shen , H. Duan , Q.L. Yang , H.B. Xu , HL-3 Team

A high spatiotemporal resolution hard X-ray (HXR) camera system has been designed for HL-3 tokamak for detecting fast electron bremsstrahlung and runaway electron profile imaging. By utilizing a combination of yttrium oxyorthosilicate (YSO) scintillator and silicon photomultipliers (SiPM), the system achieves a time resolution of up to 1 ms. Through the rational arrangement of scintillators, the camera can simultaneously detect 100 channels of hard X-rays, resulting in a spatial resolution of 2 cm for the camera. The system is dedicated to study the runaway electrons in the hard X-ray energy range of 20 to 200 keV. By improving the time resolution to 1 ms, it can be used to study power deposition in lower hybrid current drive (LHCD) and electron cyclotron resonance heating (ECRH), the generation of runaway seed populations in plasmas, and behavior of runaway electrons during plasma disruptions. The experimental results can present the evolution over time and the spatial distribution. This paper presents the system design, performance and typical diagnostic results.

为HL-3托卡马克设计了一套高时空分辨率硬x射线（HXR）相机系统，用于快速电子轫致辐射探测和失控电子剖面成像。通过利用氧化硅酸钇（YSO）闪烁体和硅光电倍增管（SiPM）的组合，该系统实现了高达1ms的时间分辨率。通过对闪烁体的合理布置，摄像机可以同时探测100个通道的硬x射线，使摄像机的空间分辨率达到2 cm。该系统专门用于研究20 ~ 200kev硬x射线能量范围内的逃逸电子。通过将时间分辨率提高到1ms，它可以用于研究低混合电流驱动（LHCD）和电子回旋共振加热（ECRH）中的功率沉积，等离子体中失控种子种群的产生以及等离子体破坏过程中失控电子的行为。实验结果可以反映出随时间的变化和空间分布。本文介绍了系统的设计、性能和典型诊断结果。

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引用次数: 0

Efficient calculation of magnetic fields from ferromagnetic materials near strong electromagnets, and application to stellarator coil optimization 强电磁铁附近铁磁材料磁场的有效计算及其在仿星器线圈优化中的应用

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-01-10 DOI: 10.1016/j.fusengdes.2026.115627

Matt Landreman , Humberto Torreblanca , Antoine Cerfon

In fusion reactor design, steels under consideration for the blanket are ferromagnetic, so the steel’s effect on the plasma physics must be examined. For efficient calculation of these fields, we can exploit the fact that the ferromagnetic material gives a small perturbation relative to the fields from the electromagnetic coils and plasma. Moreover the magnetization is saturated due to the strong fields in typical fusion systems. These approximations significantly reduce the nonlinearity of the problem, so the magnetic materials can be described by an array of point dipoles of known magnitude, oriented in the direction of the coil and plasma field. The approach is verified by comparison to finite-element calculations with commercial software and shown to be accurate. As no linear or nonlinear solve is required, only evaluation of Biot–Savart-type integrals, the method here is significantly simpler to implement than other methods, and extremely fast. The method is compatible with arbitrary CAD geometry, and also allows rapid computation of the magnetic forces. We demonstrate adding the ferromagnetic effects to free-boundary magnetohydrodynamic equilibrium calculations, assessing the effect on plasma physics properties such as confinement and stability. Moreover, it is straightforward to differentiate through the model to get the derivative of the field with respect to the electromagnet parameters. We thereby demonstrate gradient-based coil optimization for a quasi-isodynamic stellarator in which the field contribution from a ferromagnetic blanket is included. Even a significant steel volume is found to have little impact on the plasma physics properties, with the main effects being a slight destabilization of ballooning modes and a radial shift of the edge islands due to decrease in rotational transform. Both of these issues are corrected by the minor reoptimization of the coil shapes to account for the field from the steel.

在核聚变反应堆设计中，考虑用于包层的钢是铁磁性的，因此必须检查钢对等离子体物理的影响。为了有效地计算这些场，我们可以利用铁磁材料相对于电磁线圈和等离子体产生的场有一个小的扰动这一事实。此外，在典型的核聚变系统中，由于强磁场的作用，磁化是饱和的。这些近似极大地降低了问题的非线性，因此磁性材料可以用已知量级的点偶极子阵列来描述，这些点偶极子在线圈和等离子体场的方向上取向。通过与商业软件的有限元计算对比，验证了该方法的准确性。由于不需要线性或非线性解，只需要求biot - savart型积分，因此该方法比其他方法实现起来简单得多，而且速度非常快。该方法兼容任意CAD几何形状，也允许快速计算磁力。我们演示了将铁磁效应添加到自由边界磁流体动力学平衡计算中，评估了对等离子体物理特性（如约束和稳定性）的影响。此外，通过模型求导得到电场对电磁铁参数的导数是很简单的。因此，我们展示了基于梯度的准等动力仿星器线圈优化，其中包括铁磁包层的场贡献。研究发现，即使钢的体积很大，对等离子体物理特性的影响也很小，主要影响是气球模式的轻微不稳定和由于旋转变换的减少而导致的边缘岛的径向位移。这两个问题都可以通过对线圈形状的微小重新优化来纠正，以考虑来自钢的磁场。

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引用次数: 0

A comprehensive database of TJ-II signals and diagnostics for statistically based models 基于统计模型的TJ-II信号和诊断的综合数据库

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design

Pub Date : 2026-01-09 DOI: 10.1016/j.fusengdes.2025.115613

A. González Ganzábal , G.A. Rattá , T. Estrada , J. Martínez-Fernández , N. Panadero , Á. Cappa , B. López-Miranda , A. Baciero , F. Martín , D. Tafalla , B.P. Van Milligen , F. Medina , Á. de la Peña , S. Dormido-Canto , TJ-II team

Starting in 1997, the stellarator TJ-II has produced valuable scientific data crucial in the study of plasma physics and confinement. In this work, we present a stand-alone, comprehensive database that focuses on the statistical value of the TJ-II data. For this purpose, and comprising 4800 discharges, all the signals and parameters required to characterise the device before a discharge, and the diagnostics that better describe the produced plasma have been included in a database. All these different signals have been curated according to the needs of each signal and synchronised into a unified time frame of interest of 1 ms. Thus, this paper and the presented database fulfil two objectives: an introduction to several TJ-II key signals and diagnostics and a common framework for future works that rely on a strong, statistically tested database, such as the creation of models based on machine learning or data simulations.

从1997年开始，仿星器TJ-II已经产生了对等离子体物理和约束研究至关重要的宝贵科学数据。在这项工作中，我们提出了一个独立的，全面的数据库，重点关注TJ-II数据的统计价值。为此目的，包括4800次放电，放电前表征设备所需的所有信号和参数，以及更好地描述产生的等离子体的诊断已包含在数据库中。所有这些不同的信号都根据每个信号的需要进行整理，并同步到1毫秒的统一时间框架中。因此，本文和所提出的数据库实现了两个目标：介绍几个TJ-II关键信号和诊断，以及为依赖于强大的、经过统计测试的数据库的未来工作提供一个通用框架，例如基于机器学习或数据模拟的模型创建。

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引用次数: 0