Fusion Engineering and Design最新文献_第8页

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 : 2026-02-01 Epub 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 : 2026-02-01 Epub 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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引用次数: 0

Preliminary design of the self-cooled lithium-lead SCYLLA blanket for a spherical tokamak 球形托卡马克用自冷锂铅SCYLLA包层的初步设计

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

Fusion Engineering and Design

Pub Date : 2026-02-01 Epub Date: 2025-12-05 DOI: 10.1016/j.fusengdes.2025.115574

Luigi Candido , Paul Barron , Colin Baus , Italo Godoy-Morison , John McGrady , Minoru Jimma , Satoshi Ogawa , Richard Pearson , Ben Raeves , Taishi Sugiyama , Jun Takamine , Jack Taylor , Luke Taylor-King , Satoshi Ueguchi , Andrew Wilson , Satoshi Konishi

The future deployment of commercial fusion energy depends on several critical factors, among which the development of a feasible, safe, and integrated breeding blanket (BB) plays a prominent role. Since the company was founded in 2019, Kyoto Fusioneering (KF) has been developing its capability in advanced blanket design and technology development, focusing efforts on the advancement of its own innovative concept known as SCYLLA (Self-Cooled Yuryo Lithium-Lead Advanced), a self-cooled lithium-lead type blanket using silicon carbide composite (SiC

_{f}

/SiC) as a structural material. Efforts to develop the SCYLLA design have employed a holistic approach focused on component modelling, identification of system interfaces between components and systems, and safety evaluation. In this paper, progress towards an application of the SCYLLA breeding blanket configuration, using a spherical Tokamak reactor as a reference, is reported. The description of the current architecture is provided, focusing on the main modifications to evolve the design from a pre-conceptual configuration to a more robust layout. From the point of view of interfaces and experimental R&D, a lithium-lead loop has also been developed by KF as part of its UNITY-1 facility, based in Kumiyama (Kyoto, Japan). This system includes comprehensive design and modelling of the tritium extraction unit. The chosen modelling strategy and the obtained results are reported in the paper and critically discussed.

未来商业核聚变能源的部署取决于几个关键因素，其中开发一种可行、安全、集成的育种毯（BB）起着突出的作用。自2019年成立以来，京都Fusioneering （KF）一直在开发先进的电毯设计和技术开发能力，专注于推进自己的创新概念SCYLLA（自冷Yuryo锂铅先进型），这是一种使用碳化硅复合材料（SiCf/SiC）作为结构材料的自冷锂铅型电毯。开发SCYLLA设计的努力采用了一种整体方法，侧重于组件建模、组件和系统之间的系统接口识别以及安全评估。本文报道了以球形托卡马克反应堆为参考，在SCYLLA增殖包层结构应用方面的进展。本文提供了当前体系结构的描述，重点介绍了将设计从概念前配置演变为更健壮的布局的主要修改。从界面和实验研发的角度来看，KF也开发了锂-铅回路，作为其位于Kumiyama （Kyoto, Japan）的UNITY-1设施的一部分。该系统包括氚萃取装置的综合设计和建模。本文报告了所选择的建模策略和获得的结果，并对其进行了批判性讨论。

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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 : 2026-02-01 Epub 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

Irradiation resistance properties of WTaVCr alloy coatings WTaVCr合金涂层的耐辐照性能

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

Fusion Engineering and Design

Pub Date : 2026-02-01 Epub Date: 2025-12-05 DOI: 10.1016/j.fusengdes.2025.115467

Lingmin La , Lin Qin , Guanjie Liang , Lingling Wang

WTaVCr alloy coatings with different elemental contents and W substrates were selected for He ion irradiation experiments (irradiation energy 50 eV, irradiation dose of 1 × 10²⁵ m^-2, irradiation temperature 1273 K). After irradiation, the tungsten substrate showed a "fuzz" structure on the surface, while pinholes and convoluted structures appeared on the surface of WTaVCr. The irradiated WTaVCr alloy coatings exhibited a hardening phenomenon, The W₂₅Ta_23.5V_20.8Cr_30.6 alloy coating exhibits the lowest hardening rate, and the TEM observations of W₂₅Ta_23.5V_20.8Cr_30.6 show that the number density of He bubbles in the alloy was significantly lower than that of pure tungsten, which exhibits excellent resistance to irradiation.

选择不同元素含量的WTaVCr合金涂层和W衬底进行He离子辐照实验（辐照能量50 eV，辐照剂量1 × 1025 m-2，辐照温度1273 K）。辐照后，钨基板表面呈“绒毛状”结构，而WTaVCr表面出现针孔和卷曲结构。W25Ta23.5V20.8Cr30.6合金涂层的硬化率最低，且透射电镜观察表明，W25Ta23.5V20.8Cr30.6合金中He气泡的数量密度明显低于纯钨，表现出优异的耐辐照性能。

引用次数: 0

Demonstration of enhanced abnormal Plasma Current detection in KSTAR Fast Interlock System KSTAR快速联锁系统中增强异常等离子体电流检测的演示

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

Fusion Engineering and Design

Pub Date : 2026-02-01 Epub Date: 2025-12-07 DOI: 10.1016/j.fusengdes.2025.115579

Seung-Ju Lee , Myungkyu Kim , Jaesic Hong , Sang-won Yun , Taegu Lee , Sang-hee Hahn , Woong-Ryol Lee , Taehyun Tak

The KSTAR Fast Interlock System (FIS) has the primary role of protecting the devices installed in the vacuum vessel of tokamak such as Plasma Facing Components (PFCs) by immediately stopping the KSTAR heating devices, following the event handling actions of the Plasma Control System (PCS). Furthermore, the FIS assists the PCS event handling operations by redundantly detecting abnormal Plasma Current (IP) events. The initially implemented detection logic for the IP minimum fault event has been successfully evaluated and operated. In this paper, we implement another logic detecting the IP error fault event that the discrepancy between the target IP and the measured IP exceeds the criteria. As the architecture design, we assign more complicated tasks such as the waveform generation to the host server and the error fault-checking task requiring real-time operation to the target controller. Second, the Direct Memory Access (DMA) method for data communication is adopted; thus, the target controller can conduct the detection logic and the data communication in parallel without real-time performance degradation. Third, we design proper timing of the data communication for stable operation. On the host side, we employ ITER Real-Time Framework (RTF) technology for initiating the data communication with precise timing and controlling the precise execution cycle. Finally, we apply the bypass logic to prevent conflict with the same detecting operation of the PCS. We evaluate the functionality of the IP error fault detection logic in the KSTAR plasma experiments.

KSTAR快速联锁系统（FIS）的主要作用是保护安装在托卡马克真空容器中的设备，如等离子体面向组件（pfc），在等离子体控制系统（PCS）的事件处理操作之后立即停止KSTAR加热设备。此外，FIS通过冗余检测异常等离子体电流（IP）事件来协助PCS事件处理操作。初步实现的IP最小故障事件检测逻辑已成功评估并运行。在本文中，我们实现了另一种检测IP错误故障事件的逻辑，即目标IP与被测IP之间的差异超过了标准。在架构设计中，我们将波形生成等较为复杂的任务分配给主机服务器，将需要实时操作的错误故障检测任务分配给目标控制器。其次，采用直接存储器存取（DMA）方式进行数据通信；因此，目标控制器可以并行地进行检测逻辑和数据通信，而不会降低实时性。第三，我们设计了适当的数据通信时序，保证了系统的稳定运行。在主机端，我们采用ITER实时框架（RTF）技术启动数据通信，具有精确的定时和精确的执行周期控制。最后，我们采用旁路逻辑来防止与PCS的相同检测操作发生冲突。我们在KSTAR等离子体实验中评估了IP错误故障检测逻辑的功能。

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引用次数: 0

Preliminary assessment of surface inspection using visual imaging sensors for DEMO service weld seam 使用视觉成像传感器对DEMO服务焊缝进行表面检测的初步评估

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

Fusion Engineering and Design

Pub Date : 2026-02-01 Epub Date: 2025-12-01 DOI: 10.1016/j.fusengdes.2025.115553

A. Azka

Maintenance of DEMO breeding blanket includes the removal and replacement of plasma facing components. Due to the components having an active cooling loop, multiple coolant pipes need to be removed to allow access to the tokamak. The connection then needs to be reconnected using the replacement components. To fulfill the safety requirements, the welded connection needs to be inspected and approved for operation. Due to the space restriction of DEMO vacuum vessel, both the welding procedure and the subsequent inspection procedure must be conducted from inside the pipe bore.

One of the methods currently under development in DEMO remote maintenance work package is visual inspection method designed to inspect the surface of the pipe weld seam as an alternative inspection method.

This study presents the comparison between stereo RGB cameras and laser triangulation-based system for use in demo service joining. This includes the comparison between the visual inspection systems for their capability to detect the pipe weld seam, detect any pipe weld defect if present and quantify the size of the pipe defect. With the result from each visual inspection system, a comparative advantage and disadvantage analysis of each sensor is carried out and the result of the analysis is then used for further development and integration of the inspection system into the overall cut and weld concept.

DEMO繁殖毯的维护包括去除和更换等离子体表面组件。由于组件有一个主动冷却回路，需要拆除多个冷却剂管道以允许进入托卡马克。然后需要使用替换的组件重新连接。为了满足安全要求，需要对焊接连接进行检查并批准操作。由于DEMO真空容器的空间限制，焊接过程和随后的检验过程都必须在管腔内进行。DEMO远程维护工作包中目前正在开发的方法之一是目测检测法，旨在对管道焊缝表面进行检测，作为一种替代检测方法。本文介绍了立体RGB相机与基于激光三角测量的系统在演示服务连接中的比较。这包括视觉检测系统之间的比较，以检测管道焊缝的能力，检测任何管道焊接缺陷（如果存在），并量化管道缺陷的大小。根据每个视觉检测系统的结果，对每个传感器进行比较优势和劣势分析，然后将分析结果用于进一步开发和将检测系统集成到整体切割和焊接概念中。

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引用次数: 0

Commissioning and first results obtained by the C/O monitor system at the Wendelstein7‑X stellarator Wendelstein7‑X仿星器上的C/O监测系统调试和获得的第一批结果

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

Fusion Engineering and Design

Pub Date : 2026-02-01 Epub Date: 2025-12-01 DOI: 10.1016/j.fusengdes.2025.115542

Ireneusz Książek , Tomasz Fornal , Birger Buttenschön , Monika Kubkowska , Rainer Burhenn , Katarzyna Książek , Ralph Laube , the W7-X Team

A new diagnostic system designed for monitoring low-Z plasma impurities was constructed and successfully commissioned during the operational phase OP2 of the Wendelstein 7-X experiment [1]. The system is working based on recording the emission of the Lyman-α spectral lines emitted by hydrogen-like ions of carbon and oxygen (a second subsystem designed to measure the boron and nitrogen line is planned to be installed in the future). The first results obtained during the campaign OP2 showed that the system works following the design assumptions, and its properties comply with the numerical simulations. These findings suggest that this diagnostic system can be an important tool for scientific research of the stellarator plasmas.

在Wendelstein 7-X实验[1]的OP2运行阶段，构建了一套用于监测低z等离子体杂质的新诊断系统，并成功投入使用。该系统的工作原理是记录碳和氧的类氢离子发射的莱曼α谱线（第二个设计用于测量硼和氮谱线的子系统计划在未来安装）。在OP2活动期间获得的初步结果表明，该系统符合设计假设，其性能符合数值模拟。这些发现表明，该诊断系统可作为仿星等离子体科学研究的重要工具。

引用次数: 0

Exploring parameter dependencies in fusion experiments using interpretable machine learning: A case study on core electron temperature in EAST 利用可解释机器学习探索核聚变实验中的参数依赖关系：以EAST核电子温度为例

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

Fusion Engineering and Design

Pub Date : 2026-02-01 Epub Date: 2025-12-01 DOI: 10.1016/j.fusengdes.2025.115543

Ying Liu , Shengdi Liao , Xiaotao Liu , GuoSheng Xu , Genfan Ding , Xingli Wang , Qing Zang , Tianfu Zhou

This study proposes an interpretable machine-learning framework integrating XGBoost (eXtreme Gradient Boosting) and SHAP (SHapley Additive exPlanations) analysis to predict the core electron temperature (T_e) in the Experimental Advanced Superconducting Tokamak (EAST) and demonstrate parameter dependencies. The XGBoost-based framework comprises two components: a reconstruction model developed using the "all" parameter set achieved a mean absolute percentage error (MAPE) of 8.5 %, and a prediction model constructed with the "main" parameter set yielded a MAPE of 9.2 %. SHAP-based parameter dependency analysis identified radiation power (P_rad), loop voltage (V_loop), and normalized poloidal beta (β_n) as dominant factors in the reconstruction model, revealing a non-monotonic relationship for P_rad and a strong negative correlation for V_loop with T_e. In the prediction model, electron cyclotron resonance heating power (P_ECRH) and lower hybrid wave heating power (P_LHW) significantly enhanced T_e. Plasma shape parameters substantially influenced T_e predictions in both models. Analysis of Shot #78,841 captured the synergistic heating effect between P_ECRH and P_LHW, validating the framework’s interpretability. This work confirms the feasibility of combining machine learning with interpretable tools to explore parameter dependencies in fusion plasmas, offering novel insights into device-specific parameter correlations.

本研究提出了一个可解释的机器学习框架，集成了XGBoost （eXtreme Gradient Boosting）和SHAP （SHapley Additive exPlanations）分析，用于预测实验先进超导托卡马克（Experimental Advanced Superconducting Tokamak， EAST）中的核心电子温度（Te），并证明参数依赖性。基于xgboost的框架包括两个部分：使用“all”参数集开发的重建模型实现了8.5%的平均绝对百分比误差（MAPE），使用“main”参数集构建的预测模型产生了9.2%的MAPE。基于shap的参数依赖分析发现，辐射功率（Prad）、环路电压（Vloop）和归一化极向β (βn)是重构模型中的主导因素，Prad与Te呈非单调关系，Vloop与Te呈强负相关。在预测模型中，电子回旋共振加热功率（PECRH）和较低的混合波加热功率（PLHW）显著增强了Te。等离子体的形状参数在很大程度上影响了两个模型的Te预测。对78,841号镜头的分析捕捉到了PECRH和PLHW之间的协同加热效应，验证了框架的可解释性。这项工作证实了将机器学习与可解释工具相结合来探索聚变等离子体中参数依赖性的可行性，为特定设备参数相关性提供了新的见解。

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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 : 2026-02-01 Epub 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