Fusion Engineering and Design最新文献_第6页

Optimizing variable Geometry of SMBI nozzle for Thailand Tokamak 1 (TT-1) using CFD with Ansys (Fluent) 基于Ansys (Fluent) CFD的泰国托卡马克1 (TT-1) SMBI喷嘴可变几何结构优化

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

Fusion Engineering and Design

Pub Date : 2025-12-11 DOI: 10.1016/j.fusengdes.2025.115556

P. Klaywittaphat , J. Promping , B. Chatthong

This study presents a geometric optimization of the Supersonic Molecular Beam Injection (SMBI) nozzle intended for the Thailand Tokamak-1 (TT-1), aiming to enhance fueling efficiency through improved particle penetration. Numerical simulations were performed using ANSYS Fluent, where hydrogen was used as the working fluid expanding from high-pressure stagnation conditions into the vacuum chamber. Variations in throat diameter, outlet diameter, divergent length, and inlet pressure were systematically investigated using a 2D axisymmetric computational domain and the SST k–ω turbulence model. The results show that the penetration depth strongly depends on the throat diameter, with an optimum value at 1.5 mm. The outlet diameter also plays a significant role, where a nozzle with equal inlet and outlet diameters of 6 mm achieved the maximum simulated penetration of approximately 6 mm. The divergent length exhibits only secondary influence compared with the throat and outlet sizes. Gas velocity increases substantially with increasing inlet pressure; however, excessively high pressures reduce cost-effectiveness. An inlet pressure of 0.5 MPa combined with a 24-mm divergent length is recommended as a practical compromise between performance and operational efficiency. The optimized geometry offers a credible design basis for the TT-1 SMBI system, and future work will involve fabrication and experimental validation during TT-1 plasma operations.

本研究提出了用于泰国托卡马克-1 （TT-1）的超音速分子束喷射（SMBI）喷嘴的几何优化，旨在通过改善颗粒穿透来提高燃料效率。采用ANSYS Fluent软件进行数值模拟，将氢气作为工作流体从高压停滞状态膨胀到真空室。采用二维轴对称计算域和SST k -ω湍流模型，系统地研究了喉道直径、出口直径、发散长度和进口压力的变化。结果表明，穿透深度与喉部直径有很大关系，喉部直径为1.5 mm时穿透深度最佳。出口直径也起着重要的作用，其中进口和出口直径均为6 mm的喷嘴获得了约6 mm的最大模拟穿深。与喉部和出口尺寸相比，发散长度只表现出次要的影响。气流速度随入口压力的增加而显著增加；然而，过高的压力会降低成本效益。进气压力为0.5 MPa，分流长度为24mm，这是性能和操作效率之间的折衷方案。优化的几何结构为TT-1 SMBI系统提供了可靠的设计基础，未来的工作将涉及TT-1等离子体操作期间的制造和实验验证。

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引用次数: 0

Integrated design of a snake endoscopic manipulator system for in-vessel observation of fusion reactors 用于聚变反应堆容器内观测的蛇形内窥镜操作系统集成设计

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

Fusion Engineering and Design

Pub Date : 2025-12-10 DOI: 10.1016/j.fusengdes.2025.115582

Shijie Liu , Kun Lu , Yong Cheng , Youzhi Xu , Lei Zheng , Guodong Qin , Hongtao Pan

Addressing the challenge of real-time monitoring for fusion reactor vacuum vessel components during operational intervals, this paper proposes an integrated observation system design based on a snake endoscopic manipulator (SEM). The system adopts a compact integrated design, installed at a specific 20-degree inclination angle within the reactor’s lower port to optimize spatial layout. Its core components include: a SEM with storage tube and end-effector observation equipment, a tube plug flipping mechanism, and a bellows dynamic sealing device. The storage tube is welded to the observation window of the passive plate and penetrates the blind flange; the innovatively designed plug flipping mechanism seals the window during non-observation periods, with its drive unit located in the non-vacuum area outside the blind flange and motion controlled via drive rods sealed by metal bellows; the manipulator executes inspection tasks using a trajectory tracking algorithm. Integrated with digital twin technology for design and verification, this system efficiently accomplishes full-process tasks—including trajectory planning, target localization, online observation, and system reset—during reactor operational intervals, significantly enhancing inspection efficiency, reducing operational costs, and providing a highly reliable in-service observation solution to support fusion reactor commercialization.

针对核聚变反应堆真空容器部件运行间隔实时监测的挑战，提出了一种基于蛇形内窥镜操作器的集成观测系统设计。系统采用紧凑的集成化设计，安装在反应器下孔内特定的20度倾角，优化空间布局。其核心部件包括：带存储管和末端执行器观察设备的扫描电镜、管塞翻转机构、波纹管动态密封装置。存储管焊接在被动式板的观察窗上，并穿透盲法兰；创新设计的塞子翻转机构在非观测期间密封窗户，其驱动单元位于盲法兰外的非真空区域，通过金属波纹管密封的驱动杆控制运动；该机械手使用轨迹跟踪算法执行检测任务。该系统集成了用于设计和验证的数字孪生技术，在反应堆运行间隔期间有效地完成全过程任务，包括轨迹规划、目标定位、在线观测和系统复位，显著提高了检查效率，降低了运行成本，并提供了高度可靠的在役观测解决方案，以支持聚变反应堆商业化。

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引用次数: 0

Fueling control system integration and control simulation for ITER start of research operation ITER研究运行启动燃料控制系统集成与控制仿真

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

Fusion Engineering and Design

Pub Date : 2025-12-10 DOI: 10.1016/j.fusengdes.2025.115580

D. Weldon , R. Nouailletas , P. Moreau , L. Zabeo , P.C. de Vries , T. Ravensbergen , L. Pangione , O. Kudlacek , T. Keenan , A. Sanchez-Mora

ITER's Start of Research Operation (SRO) operations target the generation of plasmas reaching ∼7.5 MA for durations exceeding 100 seconds. Effective control of fueling, density, impurity dosing, edge-localized modes (ELMs), and H-mode transitions is critical. To enable model-based design, the Gas Injection System (GIS) and Pellet Injection System (PIS) have been developed as models such that a complete fueling control system can be designed to address the complex requirements and challenges unique to ITER. These challenges involve lag-time due to lengthy gas lines, fueling efficiency decay at high plasma temperatures and densities, synchronization of multiple actuators, and balancing ELM pacing with fueling needs. An Actuator Manager (AM) coordinates the GIS and PIS operations to optimize performance.

The GIS and PIS models utilize 1-D particle transport models for the gas flow and diffusion through the pipe as well as the pellet transport through the Flight Tubes (FTs), which have been implemented within the Plasma Control System Simulation Platform (PCSSP). Furthermore, the particle deposition into the plasma as well as the plasma-neutral interactions are modeled through the RApid Plasma DENsity Simulator (RAPDENS). The results presented here demonstrate the successful integration of the GIS, PIS, AM, and RAPDENS for modeling the smooth transitions between fueling modes, and effective handling of actuator failures. This paper presents the architectural design, simulation results, and future strategies for optimizing fueling control during ITER's Augmented First Plasma operations.

ITER的开始研究操作（SRO）操作目标是产生持续超过100秒的等离子体，持续时间达到~ 7.5 MA。有效控制燃料、密度、杂质剂量、边缘局域模式（elm）和h模式转换是至关重要的。为了实现基于模型的设计，气体喷射系统（GIS）和颗粒喷射系统（PIS）已经被开发为模型，这样一个完整的燃料控制系统就可以设计出来，以解决ITER独特的复杂要求和挑战。这些挑战包括由于长输气管线造成的滞后、在高等离子体温度和密度下的燃料效率下降、多个致动器的同步，以及平衡ELM起搏器与燃料需求。执行器管理器（AM）协调GIS和PIS操作以优化性能。GIS和PIS模型利用一维粒子输运模型来模拟气体在管道中的流动和扩散，以及颗粒在飞行管（FTs）中的输运，这些模型已经在等离子体控制系统仿真平台（PCSSP）中实现。此外，通过快速等离子体密度模拟器（RAPDENS）模拟了粒子在等离子体中的沉积以及等离子体-中性相互作用。这里展示的结果表明，GIS、PIS、AM和RAPDENS的成功集成可以模拟加油模式之间的平稳过渡，并有效处理执行器故障。本文介绍了ITER增强型第一等离子体运行过程中的结构设计、仿真结果和优化燃料控制的未来策略。

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引用次数: 0

Deuterium-absorption promoted by He+ irradiation in bulk palladium He+辐照促进大块钯的氘吸收

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

Fusion Engineering and Design

Pub Date : 2025-12-10 DOI: 10.1016/j.fusengdes.2025.115585

Fengyun Li, Yanhong Chang, Meijuan Hu, Jingyuan Liu, Wa Li, Qifa Pan, Min Wang, Tao Tang, Huaqin Kou, Yanxia Yan, Ge Sang

Hydrogenation acceleration is crucial for bulk palladium to achieve rapid hydrogen isotope storage and delivery, particularly in structurally stability-dependent applications like palladium-hydrogen sensors. A series of He⁺ irradiations (1.0 × 10¹⁶ atoms/cm² ∼ 1.0 × 10¹⁷ atoms/cm²) was performed on flake-shaped palladium to explore irradiation effects on hydrogen isotope absorption of palladium. It is found that the kinetics of deuterium absorption in palladium is remarkably accelerated after He⁺ irradiation. Critically, absorption rate exhibits a positive correlation with irradiation fluence, yielding an 80 % enhancement in the deuterium-palladium reaction for samples irradiated at 1.0 × 10¹⁷ atoms/cm² compared to unirradiated counterparts. Furthermore, the mechanisms underlying accelerated deuterium-palladium reactions in irradiated palladium are elucidated in detail from surface state, crystal structure, internal defects and so on. This study confirms ion irradiation as an effective method to enhance hydrogen absorption in palladium and provides valuable insights for modifying absorption performance in other hydride- forming metals with limited lattice expansion during hydriding.

加氢加速对于散装钯实现快速氢同位素储存和输送至关重要，特别是在结构稳定性依赖的应用中，如钯氢传感器。对片状钯进行了一系列He+辐照（1.0 × 1016原子/cm2 ~ 1.0 × 1017原子/cm²），探讨辐照对钯氢同位素吸收的影响。研究发现，He+辐照后钯中氘的吸收动力学明显加快。关键的是，吸收率与辐照通量呈正相关，在1.0 × 1017原子/cm²辐照下，样品的氘-钯反应比未辐照的样品增强80%。此外，从表面状态、晶体结构、内部缺陷等方面详细阐述了辐照钯中氘钯加速反应的机理。该研究证实了离子辐照是一种增强钯中氢吸收的有效方法，并为改变其他在氢化过程中晶格膨胀有限的氢化形成金属的吸收性能提供了有价值的见解。

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引用次数: 0

Effect of hydrogen on corrosion behavior of CLF-1 steel under deaerated high-temperature water 氢对CLF-1钢在脱氧高温水中腐蚀行为的影响

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

Fusion Engineering and Design

Pub Date : 2025-12-10 DOI: 10.1016/j.fusengdes.2025.115584

Rongrong Luo , Linyu Sun , Yongming Han , Teng Zhang , Pengyuan Li , Yonghao Lu , Hualin Deng , Wanyun Xu , Haihong Wei

Reduced activation ferritic martensitic steel is considered one of the most advantageous structural materials for fusion reactor blankets. In this study, hydrogen was introduced through cathodic electrochemical charging, and the influences of hydrogen on the corrosion performances of CLF-1 steel were investigated. In addition, the specimens were tested at 325 °C and 15.5 MPa, both before and after hydrogen charging. The corrosion properties were evaluated through uniform corrosion testing, slow strain rate tensile (SSRT) testing, and crack growth testing. The microstructure indicated that the oxide layers possess a bilayer structure in both conditions. In particular, after hydrogen charging, the oxide layers were thicker than those after non-charging, and the outer oxide layer features some cracks. SSRT test results revealed that after hydrogen charging, the tensile strength decreased and the brittle region slightly increased. Constant load crack growth tests demonstrate an increased crack growth rate in hydrogen-charging specimens. The presence of hydrogen can reinforce the stress corrosion cracking sensitivity of CLF-1 steel.

低活化铁素体马氏体钢被认为是核聚变堆包层最有利的结构材料之一。本研究通过阴极电化学充电引入氢气，研究氢气对CLF-1钢腐蚀性能的影响。在325℃和15.5 MPa下进行了充氢前后的试验。通过均匀腐蚀测试、慢应变速率拉伸（SSRT）测试和裂纹扩展测试来评估腐蚀性能。微观结构表明，两种条件下的氧化层均具有双层结构。特别是充氢后的氧化层比未充氢后的氧化层厚，且外层氧化层有一定的裂纹。SSRT试验结果表明，充氢后拉伸强度降低，脆性区域略有增加。恒载裂纹扩展试验表明，充氢试样裂纹扩展速率增加。氢的存在增强了CLF-1钢的应力腐蚀开裂敏感性。

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引用次数: 0

Managing machine safety challenges for over 1 MA H-mode plasma operation on the HL-3 tokamak 在HL-3托卡马克上管理超过1ma h模式等离子体操作的机器安全挑战

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

Fusion Engineering and Design

Pub Date : 2025-12-10 DOI: 10.1016/j.fusengdes.2025.115576

Xiaolong Liu, Qinghua Ren, Jie Xu, Hongbin Xu, Yong Lu, Jilai Hou, Wenyu Huang, Ruibao Jia, Jin Wang, Long Zhang, Xiaoquan Ji

The HL-3 tokamak has achieved plasma currents exceeding 1 MA in high-confinement H-mode operations, pushing the boundaries of fusion research and offering new scientific insights. However, this advancement poses significant engineering challenges related to machine safety due to increased thermal loads and electromagnetic forces. To address these challenges, an integrated real-time machine monitoring and safe operation system has been developed, featuring real-time monitoring, interlock protection, data analysis, and centralized control. This system oversees critical components such as coils, vacuum vessel, plasma-facing elements, and auxiliary systems like cooling and gas injection. A hydraulic preload system optimizes preload forces on the toroidal field coils, reducing mechanical stresses and enhancing structural integrity. To mitigate risks from uncontrolled plasma disruptions, a Shattered Pellet Injection (SPI) system has been implemented. This system injects pellets composed of hydrogen, deuterium, neon, or argon to rapidly dissipate plasma energy, significantly reducing mechanical stresses and potential damage. Operational results at plasma currents up to 1.6 MA demonstrate the effectiveness of these measures, with successful monitoring and control of displacements and accelerations in vital components. These advancements have effectively addressed safety challenges, allowing high-performance operation without compromising machine integrity. Future work will focus on safely increasing plasma currents beyond 1 MA and achieving higher toroidal magnetic fields, addressing new engineering challenges while maintaining safety as the paramount priority.

HL-3托卡马克在高约束h模操作中实现了超过1毫安的等离子体电流，推动了聚变研究的界限，并提供了新的科学见解。然而，由于热负荷和电磁力的增加，这一进步带来了与机器安全相关的重大工程挑战。为了应对这些挑战，开发了一套集实时监测、联锁保护、数据分析和集中控制为一体的机器实时监测和安全操作系统。该系统监督关键部件，如线圈，真空容器，等离子体面元件和辅助系统，如冷却和气体注入。液压预紧系统优化了环形磁场线圈上的预紧力，减少了机械应力，提高了结构的完整性。为了降低不受控制的等离子体中断的风险，已经实施了破碎颗粒注入（SPI）系统。该系统注入由氢、氘、氖或氩组成的颗粒，以迅速消散等离子体能量，显著降低机械应力和潜在损伤。在高达1.6 MA的等离子体电流下的运行结果证明了这些措施的有效性，并成功地监测和控制了重要部件的位移和加速度。这些进步有效地解决了安全挑战，在不损害机器完整性的情况下实现了高性能操作。未来的工作将集中在安全地增加等离子体电流超过1毫安，并实现更高的环向磁场，在保持安全为首要任务的同时解决新的工程挑战。

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引用次数: 0

An optimization approach for cryogenic distillation-based protium removal systems in magnetic fusion energy fuel cycles 磁聚变能燃料循环中基于低温蒸馏的脱丙系统的优化方法

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

Fusion Engineering and Design

Pub Date : 2025-12-09 DOI: 10.1016/j.fusengdes.2025.115534

Alex D. Somers, P. Arron Rowell, Collin R. Malone, Holly B. Flynn, George K. Larsen

Tritium inventory reduction for fusion power plants is central to the successful adoption of fusion energy. The advent of direct internal recycling in deuterium-tritium fusion fuel cycle design has led to significant reduction in startup tritium inventory estimates for fusion power plants but requires an isotope rebalancing and protium removal (IRPR) system to ensure acceptable isotopic fuel composition. Cryogenic distillation is a potential solution for near-term deployment in an IRPR system due to its demonstrated performance in similar operating regimes. Using protium removal in the fuel cycle as the primary performance metric, this paper presents an optimization methodology for a single-column continuous cryogenic distillation-based IRPR system for a 500 MW_fus magnetic fusion device. Distillation column optimization was performed using the CryOgenic Distillation For Isotopic Separation of Hydrogen (CODFISH) code developed at Savannah River National Laboratory. The distillation column design presented maximizes direct recycling of hydrogen isotopes from the fusion chamber exhaust to the fueling system while minimizing IRPR system steady-state tritium inventory. The optimized IRPR distillation column presented achieves direct recycling of 60 % of the hydrogen isotopes in the fusion chamber exhaust with an estimated steady-state system tritium inventory <30 g. The optimized IRPR distillation column operation was then used to estimate the design requirements for a detritation column to treat the IRPR system effluent stream.

减少核聚变发电厂的氚库存是成功采用核聚变能源的关键。氘-氚聚变燃料循环设计中直接内部循环的出现导致聚变发电厂启动氚库存估算显著降低，但需要同位素再平衡和除protium （IRPR）系统来确保可接受的同位素燃料组成。由于低温蒸馏在类似的操作系统中具有良好的性能，因此它是近期在IRPR系统中部署的潜在解决方案。以燃料循环中protium的去除为主要性能指标，提出了一种500 MWfus磁聚变装置单柱连续低温蒸馏IRPR系统的优化方法。精馏塔优化使用萨凡纳河国家实验室开发的氢同位素分离低温蒸馏（CODFISH）代码进行。精馏塔设计最大限度地从聚变室废气中直接回收氢同位素到燃料系统，同时最大限度地减少IRPR系统稳态氚库存。所提出的优化的IRPR精馏塔可以直接回收聚变室废气中60%的氢同位素，估计稳态系统氚库存为30 g。然后利用优化后的IRPR精馏塔操作来估计处理IRPR系统出水的精馏塔的设计要求。

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引用次数: 0

A robust predictive tool for the yield strength of irradiated RAFM steels for fusion engineering applications 用于核聚变工程应用的辐照RAFM钢屈服强度的可靠预测工具

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

Fusion Engineering and Design

Pub Date : 2025-12-09 DOI: 10.1016/j.fusengdes.2025.115572

YanBang Tang

Reduced-activation ferritic/martensitic (RAFM) steels are primary candidates for structural components in future fusion reactors, where their performance is critically dictated by radiation-induced hardening. Predicting this complex, multi-variable phenomenon is essential for material design and reactor safety. In this study, we developed a robust, automated machine learning (AutoML) framework to predict the yield strength of RAFM steels under various service conditions. A comprehensive database containing 1843 data points was established, incorporating 26 input features spanning chemical composition, irradiation dose, irradiation temperature, helium concentration, and mechanical testing temperature. After establishing a performance benchmark with over 40 conventional algorithms, the AutoML framework was deployed to systematically construct a multi-layer stacked ensemble model. This advanced approach demonstrated superior and more stable predictive fidelity across multiple unseen test sets, surpassing all individual models. Permutation-based feature importance analysis revealed that irradiation conditions, particularly dose and testing temperature, are the most dominant factors governing yield strength. Among the alloying elements, tungsten (W), molybdenum (Mo), and tantalum (Ta) were identified as the most critical contributors. This work not only provides a high-precision predictive tool for assessing the mechanical integrity of RAFM steels but also offers quantitative, data-driven insights into the hierarchy of factors controlling radiation hardening.

低活化铁素体/马氏体（RAFM）钢是未来核聚变反应堆结构部件的主要候选材料，其性能在很大程度上取决于辐射诱发硬化。预测这种复杂的、多变量的现象对于材料设计和反应堆安全至关重要。在这项研究中，我们开发了一个鲁棒的自动机器学习（AutoML）框架来预测RAFM钢在各种使用条件下的屈服强度。建立了包含1843个数据点的综合数据库，包含化学成分、辐照剂量、辐照温度、氦浓度、力学测试温度等26个输入特征。在建立了40多种传统算法的性能基准后，部署AutoML框架系统地构建了多层堆叠集成模型。这种先进的方法在多个未见过的测试集上证明了优越和更稳定的预测保真度，超越了所有单个模型。基于排列的特征重要性分析表明，辐照条件，特别是剂量和试验温度，是影响屈服强度的最主要因素。在合金元素中，钨(W)、钼（Mo）和钽（Ta）是最重要的贡献者。这项工作不仅为评估RAFM钢的机械完整性提供了高精度的预测工具，而且还为控制辐射硬化的因素层次提供了定量的、数据驱动的见解。

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引用次数: 0

Evaluating solid-state neutron detectors for measuring 14 MeV neutrons at high temperatures 评价高温下测量14mev中子的固态中子探测器

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

Fusion Engineering and Design

Pub Date : 2025-12-08 DOI: 10.1016/j.fusengdes.2025.115586

Q. Potiron , C. Destouches , M. Houry , O. Llido , A. Lyoussi , C. Reynard-Carette , L. Dubus , P. Malard , P. Legou , B. Cheymol

Silicon Carbide 4H Polytype (4H-SiC) and Diamond wide bandgap semiconductors are promising detector materials for fusion environments. Threshold energy nuclear reactions provide information on the energy of impinging fast neutrons and the combination of low intrinsic carrier concentration with high thermal conductivity makes these semiconductors suitable for high-temperature applications, especially for neutron monitoring in tritium production through ITER breeding blankets. While the carrier properties of SiC and Diamond offer interesting charge collection dynamics from room temperature up to 200 °C, the stability of their detection performance at high temperatures above 200 °C remains to be confirmed. To investigate this, we conducted a measurement campaign in a fast neutron field representative of fusion reactors at the GENESIS (Generator of Neutrons for Science and IrradiationS) research platform of LPSC (Laboratoire de Physique Subatomique et de Cosmologie) laboratory in Grenoble, France. Both 4H-SiC and Diamond sensors were irradiated with 14 MeV fast neutrons from a D-T neutron generator while encapsulated in a heating device, recording current signals from room temperature up to 500 °C. Using a direct measurement method of charge carrier collection dynamics as a function of applied bias voltage and temperature by pulse shape analysis provided information on velocity drift and collected charge. The results offer a first representative study of charge carrier mobility behavior with increasing temperature up to 500 °C. The stability of performance in terms of CCE (charge collection efficiency) has been demonstrated for SiC from room temperature up to 500 °C, while Diamond experiences a CCE drop of 60% between 200 °C and 300 °C.

碳化硅4H多型（4H- sic）和金刚石宽禁带半导体是很有前途的聚变环境探测器材料。阈能核反应提供了关于撞击快中子能量的信息，低固有载流子浓度和高导热率的结合使这些半导体适合于高温应用，特别是用于通过ITER增殖毯生产氚的中子监测。虽然SiC和金刚石的载流子性质在室温至200°C的范围内提供了有趣的电荷收集动力学，但它们在200°C以上的高温下检测性能的稳定性仍有待证实。为了研究这一点，我们在法国格勒诺布尔LPSC（物理、亚原子和宇宙实验室）实验室的GENESIS（用于科学和辐射的中子发生器）研究平台上的聚变反应堆代表的快中子场进行了测量活动。将4H-SiC和Diamond传感器封装在加热装置中，用来自D-T中子发生器的14 MeV快中子照射，记录室温至500°C的电流信号。通过脉冲形状分析，直接测量电荷载流子收集动态随外加偏置电压和温度的变化，提供了速度漂移和电荷收集的信息。结果提供了第一个有代表性的研究电荷载流子迁移行为随着温度升高到500°C。SiC的CCE（电荷收集效率）性能在室温至500°C范围内保持稳定，而金刚石的CCE在200°C至300°C范围内下降60%。

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引用次数: 0

Design and feasibility verification of a novel metal lip seal for large-diameter detachable vacuum interfaces in fusion reactors 一种新型大直径可拆卸真空界面金属唇密封的设计与可行性验证

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

Fusion Engineering and Design

Pub Date : 2025-12-08 DOI: 10.1016/j.fusengdes.2025.115571

Qingzhou Yu , Genmu Shi , Shilin Chen , Zhaoxi Chen , Qingxi Yang , Hao Xu

This paper presents a novel metal seal designed for large-diameter detachable vacuum interfaces in future fusion reactors, addressing stringent requirements of high irradiation, reliability, and repeated assembly. The design features a dual-lip mating structure incorporating an angular adjustment mechanism, which enhances tolerance to the flatness of the flange surface while ensuring sealing repeatability. An optimization model based on response surface methodology (RSM) is constructed to systematically evaluate the influence significance and sensitivity of key structural parameters on the gap between lips and pretightening force, and to determine the optimal parameter set. Simulation results demonstrate that the optimized seal achieves excellent lip contact and exhibits favorable elastic response characteristics. Further simulations considering weld-trim-induced lip shortening suggest that the seal structure supports approximately 10 repeated sealing cycles, meeting the requirements for reliable sealing performance under repeated disassembly scenarios in future fusion reactors. To validate manufacturability and structural robustness, a 6 m sector prototype is fabricated via multi-roller cold bending and ring forming, and its geometric accuracy and magnetic characteristics are evaluated. Experimental results show precise lip dimensions within design tolerances and low relative magnetic permeability. Furthermore, sealing performance tests under ideal alignment and induced misalignment (up to 5 mm) demonstrate that the lip seal maintains effective contact and excellent vacuum tightness, with maximum local leakage rate below 5 × 10^-11 Pa·m³/s and average leakage rate per unit length below 1 × 10^-10 Pa·m³/(s·m) for helium. This study confirms the reliability, manufacturability, and practical applicability of the proposed lip seal, providing technical guidance for the design and implementation of large-scale vacuum seals in fusion reactors.

本文提出了一种新型的金属密封，用于未来聚变反应堆的大直径可拆卸真空界面，以满足高辐照、可靠性和重复组装的严格要求。该设计采用了带有角度调节机构的双唇配合结构，提高了对法兰表面平整度的容忍度，同时保证了密封的重复性。建立了基于响应面法（RSM）的优化模型，系统评价了关键结构参数对唇间隙和预紧力的影响重要性和敏感性，确定了最优参数集。仿真结果表明，优化后的密封具有良好的唇部接触性能和良好的弹性响应特性。进一步的模拟表明，考虑到焊接装饰引起的唇缩短，密封结构支持大约10次重复密封循环，满足未来聚变反应堆在反复拆卸情况下可靠密封性能的要求。为了验证其可制造性和结构稳健性，通过多辊冷弯和环形成形工艺制作了一个6 m扇形原型，并对其几何精度和磁性特性进行了评估。实验结果表明，唇形尺寸在设计公差范围内精度高，相对磁导率低。此外，在理想对中和诱导错中（不超过5 mm）下的密封性能试验表明，唇形密封保持了有效的接触和良好的真空密封性，氦气的最大局部泄漏率低于5 × 10-11 Pa·m3/s，单位长度的平均泄漏率低于1 × 10-10 Pa·m3/（s·m）。本研究证实了所提出的唇密封的可靠性、可制造性和实用性，为聚变反应堆大型真空密封的设计和实施提供了技术指导。

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