Fusion Engineering and Design最新文献_第2页

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

Preliminary proof-of-concept of real-time divertor heat flux control from infrared cameras with nitrogen injection in the DIII-D tokamak DIII-D托卡马克中注入氮气的红外摄像机实时转向器热通量控制的初步概念验证

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.2025.115598

Troy Pederson , Himank Anand , Charlie Lasnier , Lennard Ceelen , Jun Ren , Keith Erickson , Ben Penaflor , John Ferron

In future tokamak reactors like ITER and the Fusion Pilot Plant (FPP), real-time feedback control of heat flux to the plasma-facing components (PFC) will be critical for steady-state operation. This work presents the first experimental demonstration of real-time divertor heat flux estimation with infrared thermography and feedback control with impurity seeding on the DIII-D tokamak. The flexible infrastructure of the Plasma Control System (PCS) on DIII-D makes this new capability possible. The PCS software runs on a gateway computer system, and five real-time compute nodes. An array of low latency streaming digitizers from d-TACQ Solutions connects to these real-time computers to collect and process data, and send commands to actuators during plasma discharges. This system handles the signal IO from the tokamak and allows the PCS to utilize the diagnostic data necessary to perform control in real-time. Feedback control on heat flux was accomplished by feeding infrared camera data from the “Infrared TV” (IRTV) camera to a custom-developed User Datagram Protocol (UDP) server. This server transmits infrared data to a newly developed PCS algorithm that estimates the heat flux to PFC. A proportional integral derivative (PID) controller minimizes the error between a heat flux reference and the real-time estimate by injecting nitrogen gas into the divertor.

在未来的托卡马克反应堆中，如ITER和聚变中试工厂（FPP），对等离子体面组件（PFC）的热通量的实时反馈控制将对稳态运行至关重要。本文首次在DIII-D托卡马克上用红外热像仪实时估计转向器热流密度和用杂质播种进行反馈控制。DIII-D上等离子体控制系统（PCS）的灵活基础设施使这种新功能成为可能。PCS软件运行在网关计算机系统和5个实时计算节点上。来自d-TACQ Solutions的一系列低延迟流数字化仪连接到这些实时计算机，以收集和处理数据，并在等离子体放电时向执行器发送命令。该系统处理来自托卡马克的信号IO，并允许PCS利用必要的诊断数据来实时执行控制。热通量的反馈控制是通过将红外电视（IRTV）摄像机的红外摄像机数据馈送到定制开发的用户数据报协议（UDP）服务器来完成的。该服务器将红外数据传输给新开发的PCS算法，该算法将热流密度估计到pfc。比例积分导数（PID）控制器通过向导流器注入氮气来最小化热流密度参考值与实时估计值之间的误差。

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引用次数: 0

Thermal stability of tungsten fiber-reinforced tungsten composites fabricated by powder metallurgy 粉末冶金制备钨纤维增强钨复合材料的热稳定性

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.2025.115612

Svitlana Rudchenko , Yiran Mao , Wolfgang Pantleon

Tungsten-based materials are considered as armor of plasma-facing components for future fusion reactors. To mitigate the brittleness of tungsten, tungsten fiber-reinforced tungsten composites (W_f/W) have been developed. Two types of W_f/W composites, with either continuous, aligned, potassium-doped tungsten wires in a dense tungsten matrix or randomly oriented, short fibers in a porous tungsten matrix are investigated. Both were fabricated using a powder metallurgical route facilitating field assisted sintering technology (FAST). Specimens are annealed at 1450 °C for different amounts of time up to two weeks to assess the thermal stability of the composites. Scanning electron microscopy and electron backscatter diffraction reveal major changes in the microstructure. After 4 hours of annealing initiation of recrystallization in the fibers concurrent to grain growth in the matrix is observed in both composites. Recrystallization commences at the outskirts of the fibers causing formation of a rim of small, recrystallized grains. Longer annealing increases the rim of recrystallized grains inwards into the fiber. After 3 days of annealing, all fibers are completely recrystallized, and the matrix is coarsened significantly by grain growth. While the short fibers can still be identified in the porous matrix after one week of annealing, matrix and continuous fibers cannot be distinguished any longer in the dense matrix. Short fibers with large, recrystallized grains can still be recognized after 2 weeks of annealing, while the porous matrix disintegrates by particle coarsening.

钨基材料被认为是未来核聚变反应堆等离子体组件的“护甲”。为了减轻钨的脆性，研制了钨纤维增强钨复合材料。研究了两种类型的Wf/W复合材料，一种是在致密钨基中连续排列的掺钾钨丝，另一种是在多孔钨基中随机取向的短纤维。这两种材料都采用粉末冶金路线制备，促进了场辅助烧结技术（FAST）。试样在1450°C下退火不同的时间，最长可达两周，以评估复合材料的热稳定性。扫描电子显微镜和电子背散射衍射显示了微观结构的主要变化。退火4小时后，在两种复合材料中都观察到纤维中开始再结晶，同时在基体中晶粒长大。再结晶开始于纤维的外围，形成小的再结晶晶粒的边缘。长时间退火增加了再结晶晶粒向纤维内部的边缘。退火3天后，所有纤维完全再结晶，基体因晶粒长大而明显变粗。退火一周后，多孔基体中仍能识别出短纤维，而致密基体中已无法区分出基体和连续纤维。退火2周后仍能识别出晶粒较大的再结晶短纤维，而多孔基体则因颗粒粗化而解体。

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引用次数: 0

Timing control system design of stellarator based on virtual instrument 基于虚拟仪器的仿星器定时控制系统设计

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

Fusion Engineering and Design

Pub Date : 2026-01-08 DOI: 10.1016/j.fusengdes.2026.115625

Jiajing Hua, Puqiong Yang, Xianghui Yin, Yushan Zhou, Yulin Wang

CN-H1 is a three-cycle quasi-spiral symmetric star simulator. The timing control system needs to manage the starting, running and closing sequence of the coil power supply, heating system, diagnosis system and other subsystems in a unified way, and the clock error is required to be controlled within ±2 microseconds to ensure the coordinated operation of each subsystem. This paper designs and implements a distributed timing control system centered on virtual instruments in response to the strict requirements for high-precision and multi-channel timing control during the plasma discharge of stellarators. The system takes LabVIEW FPGA as the core execution module and realizes hardware-level parallel logic by using its graphical programming. Aiming at the complex timing logic of the stellarator, a hybrid programming model of "state machine - event" was designed to decompose the complex discharge process into configurable time segments, so as to achieve the purpose of real-time switching and dynamic adjustment of waveform segments during the experiment. The test results show that the nanosecond-level absolute delay of the system signal is completely transparent to millisecond-level applications. Meanwhile, the waveform synchronization error of any two channels of the system is better than 55ns. The system can stably generate complex timing waveforms with millisecond-level cycles, and the timing accuracy and synchronization performance significantly exceed those of conventional solutions. This design has the advantages of multi-channel output, simple operation and strong real-time performance. It fully meets the timing control requirements during the discharge of CN-H1 and has important engineering application value.

CN-H1是一个三圆准螺旋对称星模拟器。定时控制系统需要对线圈电源、加热系统、诊断系统等子系统的启动、运行、合闸顺序进行统一管理，并要求时钟误差控制在±2微秒以内，以保证各子系统的协调运行。针对仿星器等离子体放电过程中对高精度、多通道定时控制的严格要求，本文设计并实现了以虚拟仪器为核心的分布式定时控制系统。该系统以LabVIEW FPGA为核心执行模块，利用其图形化编程实现硬件级并行逻辑。针对仿星器复杂的时序逻辑，设计了一种“状态机-事件”混合规划模型，将复杂的放电过程分解为可配置的时间段，从而达到实验过程中波形段实时切换和动态调整的目的。测试结果表明，系统信号的纳秒级绝对延迟对毫秒级应用是完全透明的。同时，系统任意两个通道的波形同步误差均优于55ns。该系统可以稳定地产生毫秒级周期的复杂时序波形，其时序精度和同步性能明显优于传统方案。本设计具有多通道输出、操作简单、实时性强等优点。完全满足CN-H1放电时的定时控制要求，具有重要的工程应用价值。

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引用次数: 0