Fusion Engineering and Design最新文献_第5页

Corrigendum to “Improvements to standard diagnostic preparation and data-quality monitoring in the TCV tokamak” [Fusion Engineering and Design, Volume 223, February 2026, 115578] “改进TCV托卡马克的标准诊断准备和数据质量监测”的勘误表[融合工程与设计，卷223,2026年2月，115578]

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

Fusion Engineering and Design

Pub Date : 2026-01-06 DOI: 10.1016/j.fusengdes.2025.115599

P. Molina-Cabrera, F. Pastore, A. Frank, L. Simons, A. Tourneur, C. Yildiz, B. Vincent, K. Verhaegh, C. Marini, M. Wensing, A. Ianchenko, A. Balestri, S. Ernst, S. Coda, U. Sheikh, the TCV team

引用次数: 0

Topology Optimization of a 10 T, 52 cm bore stellarator magnet structure 10 T， 52 cm口径仿星器磁体结构拓扑优化

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

Fusion Engineering and Design

Pub Date : 2026-01-03 DOI: 10.1016/j.fusengdes.2025.115608

S. Del Nero , P. Fanelli , V. Prost , F.A. Volpe

The performance of high-field magnets is increasingly constrained not by the limits of High-Temperature Superconducting materials, but by the structural systems needed to withstand the intense Electro-Magnetic forces they produce. In response to this challenge, this work presents a design-driven methodology for optimizing the reinforcement structures of 52 cm bore wide HTS magnets under development at Renaissance Fusion, aimed at achieving magnetic fields up to 10 T on the plasma axis. A custom Topology Optimization tool, based on the Solid Isotropic Material Penalization method and implemented entirely in PyMAPDL, was employed to guide the mechanical design of the magnet reinforcements. Starting from a large design domain (

\sim

11.3 tons per sector), Topology Optimization with varying volume fractions produced lightweight structures, down to 3.93 tons, that meet strict mechanical constraints on magnet displacement (

<

1 mm), magnet strain (

<

0.5%) and global stress (

<

800 MPa). Then, a second optimization stage using extrusion constraints methodologies was employed to further optimize the structure while ensuring manufacturability. Recurring features from these runs informed the development of a parametric model, enabling further refinement and a final mass of 1.20 t. The final structure, segmented into sub-components for a feasible assembly procedure, retained the required mechanical performance while ensuring ease of manufacturing using conventional processes. This magnet design demonstrate the applicability and benefits of our multi-stage constrained topology optimization method for advancing the structural design of high-field and compact stellarators.

高磁场磁体的性能越来越受到高温超导材料的限制，而是受到承受它们产生的强烈电磁力所需的结构系统的限制。为了应对这一挑战，这项工作提出了一种设计驱动的方法，用于优化Renaissance Fusion正在开发的52厘米孔径宽的高温超导磁体的增强结构，旨在实现等离子体轴上高达10 T的磁场。采用完全在PyMAPDL中实现的基于固体各向同性材料惩罚方法的自定义拓扑优化工具，指导磁体增强件的力学设计。从大型设计域（每扇区约11.3吨）开始，具有不同体积分数的Topology Optimization生产出轻量化结构，轻至3.93吨，满足严格的磁体位移（<1 mm），磁体应变（<0.5%）和全局应力（<800 MPa）的机械约束。然后，采用挤压约束方法进行二次优化，在保证可制造性的前提下进一步优化结构。从这些运行中反复出现的特征为参数化模型的开发提供了信息，从而进一步细化，最终质量为1.20 t。最终的结构被分割成可行的装配程序的子组件，在保留所需的机械性能的同时确保使用传统工艺易于制造。该磁体的设计证明了多级约束拓扑优化方法在推进高场紧凑型仿星器结构设计中的适用性和优越性。

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引用次数: 0

Microstructural evolution and densification behaviors of W14Re2 alloy produced at different temperature by spark plasma sintering 放电等离子烧结不同温度下W14Re2合金的组织演变及致密化行为

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

Fusion Engineering and Design

Pub Date : 2026-01-03 DOI: 10.1016/j.fusengdes.2025.115611

Jinpeng Zhang , Lihua Guo , Guoqiang Wang , Jun Lin , Linyuan Lu , Jinwei Zhan

The effect of sintering temperature on the microstructural evolution and densification behaviors of W₁₄Re₂ (with a Re atomic ratio of 12.50 % and a mass ratio of 12.64 %) was explored for the first time utilizing spark plasma sintering (SPS) technology. The results reveal that Re is uniformly dispersed within the W matrix following high-energy ball milling. 1300 °C serves as a critical threshold for the microstructural transformation of W₁₄Re₂ alloy, during which the grain morphology evolves from nearly spherical to equiaxed. 1400 °C marks a pivotal temperature point for the densification transition of W₁₄Re₂, where the sample surface transforms from being porous and loose to highly dense. Overall, as the temperature rises, the grain size demonstrates a gradual increasing tendency. Specifically, the average W grain size attains approximately 1 μm at 1700 °C, which corresponds to a theoretical density of 97.47 %. Furthermore, the two phases exhibit an alternating peak-and-valley elemental concentration profile along the interface. The HRTEM reveals uniformly distributed diffraction spots with alternating intensities at the two-phase interface. These spots oscillate asymmetrically around the original lattice positions, suggesting a twin-like structural feature. This phenomenon can be attributed to Re doping-induced lattice distortion in the W matrix at elevated temperatures, coupled with interfacial interactions that facilitate solid solution formation between the phases. This study offers a preliminary investigation into the sintering properties of the W₁₄Re₂ alloy and is anticipated to establish a groundwork for facilitating further optimized preparation of W-Re alloys.

利用火花等离子烧结（SPS）技术，首次研究了烧结温度对W14Re2 （Re原子比12.50%，质量比12.64%）显微组织演变和致密化行为的影响。结果表明：高能球磨后，稀土均匀分散在W基体内。1300℃是W14Re2合金显微组织转变的临界阈值，晶粒形貌由近球形转变为等轴态。1400℃是W14Re2致密化转变的关键温度点，样品表面由多孔疏松转变为高密度。总体来看，随着温度的升高，晶粒尺寸呈逐渐增大的趋势。在1700℃时，W的平均晶粒尺寸约为1 μm，理论密度为97.47%。此外，两相的元素浓度沿界面呈峰谷交替分布。HRTEM在两相界面处显示出均匀分布的强度交变的衍射斑点。这些斑点围绕原始晶格位置不对称地振荡，表明具有类似双胞胎的结构特征。这种现象可以归因于高温下稀土掺杂引起的W基体晶格畸变，以及促进相之间形成固溶体的界面相互作用。本研究对W14Re2合金的烧结性能进行了初步研究，为进一步优化制备W-Re合金奠定了基础。

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引用次数: 0

Optical boundary reconstruction with visible/infrared integrated imaging systems on the HL-3 tokamak HL-3托卡马克上可见光/红外综合成像系统的光学边界重建

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

Fusion Engineering and Design

Pub Date : 2025-12-31 DOI: 10.1016/j.fusengdes.2025.115609

M.Y. He , J.M. Gao , X.Q. Ji , T.F. Sun , A. Wang , B.T. Cui , H.L. Du , J.X. Li , L. Liu , G.Z. Hao

The plasma boundary has been reconstructed using integrated multispectral optical imaging systems on the HL-3 tokamak, with particular emphasis on the divertor region. In addition to the mid-plane visible imaging system, which is commonly used to reconstruct the main plasma boundary, a new lower divertor visible and infrared imaging system has been developed to reconstruct the locations of the X-point and the strike points. It increases the accuracy of reconstructed plasma boundary, achieving precision of approximately 10 mm. Simulation results demonstrate that the averaged reconstructed error of the optical boundary is within a few millimeters. Finally, the reconstructed optical plasma boundary shows strong potential for applications in plasma diagnostics and equilibrium analysis.

利用HL-3托卡马克上的集成多光谱光学成像系统对等离子体边界进行了重建，重点研究了转向器区域。除了通常用于重建等离子体主边界的中平面可见成像系统外，还开发了一种新的下分流器可见和红外成像系统，用于重建x点和打击点的位置。它提高了重建等离子体边界的精度，达到了约10 mm的精度。仿真结果表明，光学边界的平均重构误差在几毫米以内。最后，重建的光学等离子体边界在等离子体诊断和平衡分析方面显示出强大的应用潜力。

引用次数: 0

Fast reciprocating probe system with synergistic operation of a small linear motor and a counterweight cabinet on HL-3 HL-3上小型直线电机和配重柜协同操作的快速往复探头系统

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

Fusion Engineering and Design

Pub Date : 2025-12-30 DOI: 10.1016/j.fusengdes.2025.115607

Kaiyang Yi , Zhihui Huang , Weice Wang , Jun Cheng , Na Wu , Yu He , Wei Zhao , Lin Nie , Longwen Yan , Guoliang Xiao , Zhongbing Shi , Xiaoquan Ji , Wulyu Zhong

This paper introduces the mid-plane fast reciprocating probe (FRP) system in the HL-3 tokamak. Unlike traditional pneumatic cylinder or servo motor drives, this system achieves fast movement through the operation of a linear motor and a counterweight cabinet. The counterweight cabinet is chosen to balance the atmospheric pressure for the first time, without requiring a large linear motor with high output torque. As a result, the system takes up less space and has high speed, high acceleration, long stroke length, and adjustable movement distance. The front of this system can accommodate various compound probes with a maximum pin number of 19. At present, this system has been put into operation in the HL-3 tokamak, and preliminary experimental results confirm the novel design.

介绍了HL-3托卡马克中平面快速往复探头（FRP）系统。与传统的气缸或伺服电机驱动不同，该系统通过直线电机和配重柜的操作实现快速运动。首次选用配重柜平衡大气压力，不需要大输出转矩的直线电机。因此，该系统占地面积小，速度快，加速度高，行程长，运动距离可调。该系统的前端可以容纳各种复合探头，最大引脚数为19。目前，该系统已在HL-3托卡马克上投入运行，初步实验结果证实了该设计的可行性。

引用次数: 0

Experimental study on particle crushing and pressure drop characteristics of Li4SiO4 breeder pebble beds Li4SiO4增殖层颗粒破碎及压降特性试验研究

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

Fusion Engineering and Design

Pub Date : 2025-12-30 DOI: 10.1016/j.fusengdes.2025.115604

Zheng Fang , Hao Cheng , Bing Zhou , Baoping Gong , Zhenzhong Li , Qiang Lian , Shanshan Bu , Deqi Chen

During long-term operation of tritium breeding blankets in fusion reactors, breeder particles are subjected to both irradiation and thermal stress, which can lead to particle fracture, thereby affecting the structural integrity of the pebble bed and the tritium breeding performance. This study investigates the fracture behavior of Li₄SiO₄ particles used in Helium-Cooled Ceramic Breeder (HCCB) blankets. In this work, Uniaxial cyclic compression tests were performed on breeder pebble beds to evaluate their mechanical response under different stress and temperature conditions. The particle breakage rate and fragment size distribution were obtained through sieving. Results indicated that increasing compressive stress and temperature led to higher breakage rates and a greater mass fraction of small fragments. Building on these fragmentation characteristics, multiple crushed packed beds with varying breakage rates (3–15%) and size distributions were configured to investigate particle breakage effects on purge-gas pressure drops, revealing that the helium pressure drop increases with the breakage rate. Crucially, the Ergun equation reliably predicted pressure drops for breakage rates ≤15%, with a maximum deviation of 10.6% under extreme fragmentation.

在聚变反应堆氚增殖包层长期运行过程中，增殖粒子受到辐照和热应力的双重作用，会导致粒子断裂，从而影响球床的结构完整性和氚增殖性能。本文研究了用于氦冷陶瓷增殖毯（HCCB）的Li₄SiO₄颗粒的断裂行为。在本工作中，进行了单轴循环压缩试验，以评估其在不同应力和温度条件下的力学响应。通过筛分得到颗粒破碎率和碎片大小分布。结果表明，压应力和温度的升高导致了更高的破碎率和更大的小碎片质量分数。在此破碎特性的基础上，配置不同破碎率（3-15%）和粒度分布的多个破碎充填层，研究颗粒破碎对吹扫气压降的影响，发现氦气压降随破碎率的增加而增加。至关重要的是，Ergun方程可靠地预测了破碎率≤15%时的压降，在极端破碎情况下最大偏差为10.6%。

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引用次数: 0

Design and simulation of a beam extraction and acceleration system for a small high-intensity neutron generator 小型高强度中子发生器束流提取与加速系统的设计与仿真

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

Fusion Engineering and Design

Pub Date : 2025-12-30 DOI: 10.1016/j.fusengdes.2025.115606

Jingtian Xu , Wen Wang , Qi Yang , Minghuang Wang , Shiyou Yang , FDS Consortium

A small high-intensity neutron generator imposes constraints on the beam extraction and acceleration system, which can deliver a deuterium/tritium (D/T) mixed ion beam with an energy of more than 200 keV and a current of more than 126 mA to the target within a limited space of 500 mm in length and 60 mm in radius. The beam at the target should have a spot radius of less than 40 mm and a peak current density of less than 50 A/m². In this work, beam transport simulations were conducted using the IBSIMU code. A preliminary design was obtained by iteratively optimizing the electrode geometry, which enables the transportation of a 200 keV, 126 mA D-T beam with a spot radius of 37 mm and a peak current density of 49.2 A/m² at the target. Based on this design, the effects of key geometric parameters, including the extraction gap, extraction aperture radius, acceleration gap, and acceleration aperture radius, on the beam spot radius and peak current density, were systematically analyzed. The results indicate that the variations in the extraction and acceleration gaps significantly affect the beam focusing condition, thus exerting a strong influence on the beam spot size and beam distribution. Under-focused transport conditions are more favorable for meeting the design requirements of the neutron generator. Variations in the extraction aperture radius and acceleration aperture radius do not modify the beam focusing condition and only marginally affect the beam spot and density, thereby allowing fine adjustments to be made according to practical requirements.

一个小型的高强度中子发生器对束流提取和加速系统施加了限制，该系统可以在长度为500mm、半径为60mm的有限空间内向目标输送能量超过200kev、电流超过126ma的氘/氚（D/T）混合离子束。激光束的光斑半径应小于40mm，峰值电流密度应小于50a /m²。在这项工作中，使用IBSIMU代码进行了波束输运模拟。通过对电极几何形状的迭代优化，得到了一个初步的设计方案，该设计方案可使200 keV、126 mA、光斑半径为37 mm、峰值电流密度为49.2 A/m2的D-T束流在目标处传输。在此基础上，系统分析了提取间隙、提取孔径半径、加速间隙和加速孔径半径等关键几何参数对光束光斑半径和峰值电流密度的影响。结果表明，提取间隙和加速间隙的变化会显著影响光束聚焦条件，从而对光束光斑大小和光束分布产生强烈影响。欠聚焦输运条件更有利于满足中子发生器的设计要求。提取孔径半径和加速孔径半径的变化不会改变光束聚焦条件，只会对光束光斑和密度产生轻微影响，可以根据实际需要进行微调。

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引用次数: 0

Demonstrating powder metallurgically produced long tungsten fiber-reinforced tungsten composite to serve as plasma-facing material 演示了粉末冶金法制备的长钨纤维增强钨复合材料作为等离子体表面材料

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

Fusion Engineering and Design

Pub Date : 2025-12-27 DOI: 10.1016/j.fusengdes.2025.115605

Yiran Mao , Jan Willem Coenen , Johann Riesch , Thomas Schwarz-Selinger , Elena Tejado , Arkadi Kreter , Alexis Terra , Marius Wirtz , Marcin Rasinski , Juan Du , Xiaoyue Tan , Yaohui Liu , Rudolf Neu , Christoph Broeckmann , Christian Linsmeier

For future fusion devices, tungsten is the main candidate materials for the application as plasma facing materials (PFMs). However, considering the challenging operational condition with high thermal loading/thermal stress combining plasma exposure and neutron irradiation/embrittlement, one of the major concern for tungsten as PFMs is its intrinsic brittleness. To avoid cracking and components failure, toughening tungsten is widely investigated, among which tungsten fiber reinforced tungsten composites (W_f/W) are developed using an extrinsic toughening mechanism. Recently, a new type of aligned long fiber W_f/W (L-W_f/W) with dedicated weak interface have been prepared by powder metallurgy process, combing the advantages of superb damage resilience with a much easier production compared to conventional chemical vapor deposition process. In this work, the newly developed material is characterized, including, mechanical tests, high heat flux tests, exposure to plasma for erosion and fuel retention tests. The l-W_f/W composite could improve significantly the damage resilience compared to pure W without altering much of other properties.

在未来的聚变装置中，钨是用作等离子体表面材料（pfm）的主要候选材料。然而，考虑到高热负荷/热应力结合等离子体暴露和中子辐照/脆化的具有挑战性的操作条件，钨作为pfm的主要问题之一是其固有的脆性。为了避免钨的断裂和部件失效，人们对钨的增韧进行了广泛的研究，其中利用外部增韧机制开发了钨纤维增强钨复合材料（Wf/W）。近年来，利用粉末冶金技术制备了一种专用弱界面定向长纤维Wf/W (L-Wf/W)，该材料具有优异的损伤回弹性和比传统化学气相沉积工艺更容易生产的优点。在这项工作中，对新开发的材料进行了表征，包括机械测试、高热流密度测试、暴露于等离子体进行侵蚀和燃料保留测试。与纯W相比，l-Wf/W复合材料在不改变其他性能的情况下显著提高了损伤回弹性。

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引用次数: 0

Design and analysis of PCHE-type recuperator for helium cooling system in CN HCCB TBS CN HCCB TBS氦冷却系统pche型回热器的设计与分析

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

Fusion Engineering and Design

Pub Date : 2025-12-27 DOI: 10.1016/j.fusengdes.2025.115603

Zhengning Zhao , Xinghua Wu , Jie Liu , Xingfu Ye , Hong Yang , Xiaoyu Wang

The Helium Cooling System (HCS) is an important ancillary system of the Chinese Helium-Cooled Ceramic Breeder Test Blanket System (CN HCCB-TBS) that provides cooling to remove heat from the fusion reactor blanket during plasma operation. The HCS is an “8″-shaped loop, in which a circulator provides the pressure head for the helium, while two heat exchangers and a heater are arranged to convert heat during operation. The recuperator is positioned at the center of the loop to transfer heat between the cold and hot helium streams, thereby enabling energy recovery and reducing loop energy consumption. Consequently, the design and selection of the recuperator significantly influence the operational stability and energy balance of the HCS. Printed Circuit Heat Exchangers (PCHEs) exhibit superior performance in terms of high-temperature and high-pressure capability, thermal efficiency, compactness, and operational reliability, making them widely applicable in petrochemical and hydrogen energy systems. This article presents the design and analysis of a PCHE-type recuperator based on specified requirements and project experience, providing valuable support for the design and manufacturing of future helium cooling loops and related applications.

氦冷却系统（HCS）是中国氦冷却陶瓷增殖试验包层系统（CN HCCB-TBS）的重要辅助系统，在等离子体运行过程中为聚变反应堆包层提供冷却以去除热量。HCS是一个“8″”形状的回路，其中一个循环器为氦气提供压力头，而两个热交换器和加热器则在运行过程中转换热量。回热器位于回路中心，在冷氦流和热氦流之间传递热量，从而实现能量回收，降低回路能耗。因此，回热器的设计和选择对HCS的运行稳定性和能量平衡有重要影响。印刷电路热交换器（PCHEs）在高温高压性能、热效率、紧凑性和运行可靠性方面表现出优异的性能，广泛应用于石化和氢能系统。本文根据规定的要求和项目经验，介绍了pche型回热器的设计和分析，为未来氦气冷却回路的设计和制造及相关应用提供了有价值的支持。

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引用次数: 0

Development and application of A-M combined TIG welding techniques for the ITER Blanket Shield Block 国际热核聚变实验堆包层屏蔽块A-M组合TIG焊接技术的开发与应用

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

Fusion Engineering and Design

Pub Date : 2025-12-23 DOI: 10.1016/j.fusengdes.2025.115600

Sa-Woong Kim , Jun-Sung Chang , Ji-Young Jeong , Duck-Hoi Kim

Active water cooling is designed to remove the nuclear heat generation in the Shield Block (SB). In some modules, the surface heat flux is also considered due to lack of First Wall (FW) coverage. According to the manufacturability assessment, the cooling channels in the SB are made by drilling process because it is preferable to manufacture the SBs from one single stainless steel forged block. The water headers are machined on the side of the SB, and closed by cover plates which have a thickness from 8 mm to 10 mm.

In this study, it is present a novel hybrid welding technique that combines the advantages of manual welding and robotic welding to address the unique challenges posed by conventional manual TIG welding. Manual TIG welding offers the flexibility and applicability required for variable weld geometries, while robotic welding provides the benefits of precision, repeatability, and increased productivity.

The development of the A-M combined welding process involves optimizing parameters such as welding speed, heat input and arc stability to achieve a seamless integration of manual and robotic welding techniques. Additionally, considerations for joint accessibility, weld quality and overall process efficiency are addressed to ensure the successful application of the hybrid approach in a complex welding environment.

The proposed approach not only meets the stringent requirements of ITER components but also provides a versatile solution that can be adapted to similar applications in advanced manufacturing scenarios.

主动水冷却设计用于消除屏蔽块（SB）中的核热产生。在一些模块中，由于缺乏第一壁（FW）覆盖，还考虑了表面热通量。通过可制造性评价，考虑到单根不锈钢锻件加工SBs的效果较好，采用钻孔工艺制作了SB的冷却通道。水集管被加工在SB的侧面，并由厚度从8 mm到10 mm的盖板封闭。本研究提出了一种新型的混合焊接技术，结合了手工焊接和机器人焊接的优点，以解决传统手工TIG焊接所面临的独特挑战。手工TIG焊接提供了可变焊缝几何形状所需的灵活性和适用性，而机器人焊接提供了精度、可重复性和提高生产率的好处。a - m组合焊接工艺的开发涉及到焊接速度、热输入和电弧稳定性等参数的优化，以实现人工和机器人焊接技术的无缝集成。此外，还考虑了接头可及性、焊接质量和整体工艺效率，以确保混合方法在复杂焊接环境中的成功应用。所提出的方法不仅满足ITER组件的严格要求，而且提供了一种通用的解决方案，可以适应先进制造场景中的类似应用。

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引用次数: 0