Fusion Engineering and Design最新文献_第6页

Comparison of remote access technologies for research facilities using EPICS/CSS. Application to particle accelerator experiments 基于EPICS/CSS的科研设施远程访问技术比较。应用于粒子加速器实验

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.2025.115595

Javier Cruz-Miranda , Manuel Rodríguez-Álvarez , Miguel Damas , Iván Casero-Santos , Iván Podadera-Aliseda , José Franco-Campos , Antti Jokinen , André Sancho-Duarte , Javier Díaz

This study compares and proposes new alternatives for remotely connecting to visualize the experiments occurring in a particle accelerator located in Rokkasho, Japan. Three different platforms have been considered for remote access: the existing X2GO client, Guacamole with Control System Studio (CSS), and Phoebus web. While X2GO is a standard client for remote access to a server desktop, the other two platforms are proposed to improve the access, the response time, and the user experience for the researchers The servers for this study and the Operator Interfaces (OPIs) have been placed in our laboratory located in Granada, Spain, and the accelerator data, by means of Process Variables (PVs), were obtained via a VPN. Additionally, these platforms have been tested in two ways: with direct access to the PV data for each connection and using a local EPICS (Experimental Physics Industrial Control System) Gateway. The results prove that these new platforms, with a stable connection to the accelerator, could eventually enhance access to the experiments and balance the load of researchers connecting to the facility. This would allow the international team of researchers to participate in experiments as if they were physically in the control room.

本研究比较并提出了远程连接的新方案，以可视化在位于日本六所所的粒子加速器中发生的实验。考虑了三种不同的远程访问平台：现有的X2GO客户端、Guacamole with Control System Studio （CSS）和Phoebus web。虽然X2GO是远程访问服务器桌面的标准客户端，但我们提出了另外两个平台来改善访问，响应时间和研究人员的用户体验。本研究的服务器和操作员接口（opi）已放置在我们位于西班牙格拉纳达的实验室中，加速器数据通过过程变量（pv）通过VPN获得。此外，这些平台已经通过两种方式进行了测试：直接访问每个连接的光伏数据，以及使用本地EPICS（实验物理工业控制系统）网关。结果证明，这些与加速器稳定连接的新平台最终可以增加对实验的访问，并平衡连接到该设施的研究人员的负载。这将允许国际研究团队参与实验，就好像他们在控制室一样。

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引用次数: 0

Pre-conceptual design of ECE Imaging for real time NTM control 用于实时NTM控制的ECE成像的概念前设计

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

Fusion Engineering and Design

Pub Date : 2025-12-22 DOI: 10.1016/j.fusengdes.2025.115597

N. Rispoli , A. Pecorelli , L. Figini , C. Sozzi , D. Busi , F. Braghin , E. Alessi

The reduction or suppression of magneto-hydrodynamic instabilities, such as Neoclassical Tearing Modes (NTMs), can be performed through localized current driven by Electron Cyclotron Heating and Current Drive (ECH&CD). In this paper, we show that the proper aiming of a steerable antenna can be obtained using a suitable layout of an array of Electron Cyclotron Emission diagnostics (ECE imaging). The diagnostic principle leading to the adoption of ECE imaging is to exploit propagation reciprocity at electron cyclotron frequencies, which allows for the implementation of control strategies such as the In-Line (van den Brand et al., 2018) and the Quasi-In-Line (Sozzi et al., 2023) control schemes (I-L and Q-I-L schemes). However, these schemes require equipping a dedicated ECE diagnostic with at least a movable antenna.

This contribution is based on simulations obtained for a DEMO-like reactor to demonstrate the feasibility of NTM control schemes based on information provided by an ECE imaging diagnostic, which uses a set of fixed Lines-of-Sight (LoS). Towards the design of a diagnostic layout suitable for the use in real machines, the following questions are here addressed: First, we evaluate the number of LoS required to satisfy the strict alignment precision necessary in a DEMO-like reactor and then provide a pre-conceptual design. Finally, the performance that could be obtained by a control system adopting such a diagnostic is evaluated and compared with the I-L and the Q-I-L schemes mentioned above.

通过电子回旋加热和电流驱动（ECH&；CD）驱动的局部电流，可以降低或抑制磁流体动力学不稳定性，如新经典撕裂模式（ntm）。在本文中，我们证明了通过电子回旋发射诊断阵列（ECE成像）的适当布局可以获得适当的定向天线。采用ECE成像的诊断原理是利用电子回旋频率下的传播互易性，这允许实施控制策略，如在线（van den Brand等人，2018）和准在线（Sozzi等人，2023）控制方案（I-L和Q-I-L方案）。然而，这些方案需要配备一个专用的ECE诊断设备，至少有一个可移动的天线。这一贡献是基于对demo样反应器的模拟，以证明基于ECE成像诊断提供的信息的NTM控制方案的可行性，该诊断使用一组固定的视线（LoS）。为了设计适合实际机器使用的诊断布局，这里解决了以下问题：首先，我们评估了满足演示式反应器所需的严格对准精度所需的LoS数量，然后提供了一个概念前设计。最后，对采用这种诊断方法的控制系统所能获得的性能进行了评估，并与上述的I-L和Q-I-L方案进行了比较。

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引用次数: 0

Brazing between W/Cu flat tiles and RAFM steel considering the thickness limit of Cu layer and the microscopic evolution of RAFM 考虑Cu层厚度极限和RAFM微观演化的W/Cu平瓦与RAFM钢的钎焊

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

Fusion Engineering and Design

Pub Date : 2025-12-17 DOI: 10.1016/j.fusengdes.2025.115593

Sixiang Zhao , Binghua Ren , Yuan Zhang

Joining the W/Cu flat tiles fabricated with vacuum casting to RAFM steel via brazing provides an alternative route for blanket manufacturing. Reducing the thickness of pure Cu in W/Cu tiles is favorable from the perspective of minimizing neutron irradiation-induced activation, and obtaining proper microstructures and properties of RAFM steel after the brazing thermal cycle is vital for component commissioning. This study concerns the above issues. The screening experiment reveals that the pure Cu layer is susceptible to alloying with elements that migrated from CuNiMn filler metal. By reducing the thickness of the original Cu layer in the W/Cu tiles to 0.15 ± 0.05 mm through machining, a small-scale mock-up has been successfully brazed. The retained pure Cu layer has a thickness of ∼90 μm, and results show that it can effectively relax thermal stresses. The RAFM steel subjected to the brazing thermal cycle contains less martensite than that heat-treated according to the recommended regulations. Our discussion indicates that this problem can be solved by introducing an enhanced cooling method, which can provide a constant cooling rate while preventing interfacial cracking, or by adopting an RAFM steel requiring a smaller critical cooling rate.

通过钎焊将真空铸造的W/Cu扁平瓦与RAFM钢连接起来，为毛毯制造提供了另一种途径。从减少中子辐照活化的角度来看，减小W/Cu瓦中纯Cu的厚度是有利的，并且在钎焊热循环后获得合适的RAFM钢的组织和性能对部件调试至关重要。本研究涉及上述问题。筛选实验表明，纯Cu层容易与从CuNiMn填充金属迁移而来的元素发生合金化。通过机械加工将原铜层厚度减小到0.15±0.05 mm，成功地钎焊了小规模模型。残留的纯Cu层厚度为~ 90 μm，可以有效地缓解热应力。经钎焊热循环处理的RAFM钢的马氏体含量低于按推荐规范热处理的RAFM钢。我们的讨论表明，这个问题可以通过引入一种增强的冷却方法来解决，这种方法可以提供恒定的冷却速率，同时防止界面开裂，或者采用需要更小临界冷却速率的RAFM钢。

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引用次数: 0

The effect of minority heating on the electron temperature profile recovery using ICRH for future real-time control applications in tokamak plasmas 少数加热对利用ICRH恢复电子温度分布的影响，用于未来托卡马克等离子体的实时控制应用

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

Fusion Engineering and Design

Pub Date : 2025-12-17 DOI: 10.1016/j.fusengdes.2025.115555

M. Cappelli , A. Cardinali , V.K. Zotta , G. Pucella , M. Brambilla , S. Gabriellini , R. Gatto , M. Zerbini , L. Garzotti , D. Van Eester , JET contributors , WPTE Team

Real-time control using Ion Cyclotron Resonance Heating (ICRH) has been proposed in JET operational scenarios to counteract temperature hollowing effects. Specifically, in cases of hollow electron temperature profiles, central ion cyclotron resonance heating could be employed to restore temperature peaking based on real-time Electron Cyclotron Emission (ECE) data. ICRH has been utilized to optimize the plasma ramp-down process, correcting the discharge's end and preventing plasma disruption. Before designing the real-time controller, it is necessary to carefully evaluate the ability of the ICRH to recover the temperature profile by depositing the power emitted in the desired way. For this purpose, the presented work conducted simulations of a JET discharge to evaluate power deposition using a full wave code (TORIC). To quantify the power transferred from hydrogen ions to electrons, a quasi-linear analysis was conducted. The effects of ICRH application on the power balance were assessed through predictive transport analysis using the JINTRAC suite of codes. The integrated study's findings demonstrate the potential of utilizing ICRH alongside ECE measurements for real-time control of the electron temperature profile, offering valuable insights for future plasma control strategies and advanced tokamak operation.

利用离子回旋共振加热（ICRH）对射流进行实时控制，以抵消温度空穴效应。具体来说，在空心电子温度分布情况下，基于电子回旋发射（ECE）实时数据，可以采用中心离子回旋共振加热来恢复温度峰值。ICRH已被用于优化等离子体下降过程，纠正放电结束并防止等离子体中断。在设计实时控制器之前，有必要仔细评估ICRH通过以期望的方式沉积发出的功率来恢复温度分布的能力。为此，本研究利用全波码（TORIC）对JET放电进行了模拟，以评估功率沉积。为了量化氢离子向电子传递的能量，进行了准线性分析。通过使用JINTRAC代码套件进行预测输运分析，评估ICRH应用对功率平衡的影响。综合研究结果表明，利用ICRH和ECE测量实时控制电子温度分布的潜力，为未来的等离子体控制策略和先进的托卡马克操作提供了有价值的见解。

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引用次数: 0

Numerical investigation of 3D MHD pressure drop in a prototypical fusion blanket manifold using OpenFOAM 用OpenFOAM对典型熔覆层歧管内三维MHD压降进行数值研究

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

Fusion Engineering and Design

Pub Date : 2025-12-17 DOI: 10.1016/j.fusengdes.2025.115592

Ronny Rives, LLuís Batet

Reliable prediction of magnetohydrodynamic (MHD) pressure losses in liquid-metal breeding blankets is essential for DEMO reactor design. In the European Dual Coolant Lead–Lithium (EU-DCLL) concept, manifold expansions and contractions are expected to dominate the total pressure drop. This work investigates the three-dimensional (3D) MHD pressure drop associated with a sudden expansion representative of the EU-DCLL bottom manifold, using a customized OpenFOAM solver. The solver is validated against analytical solutions and benchmark numerical codes, demonstrating superior stability and mesh efficiency. A set of 45 simulations is conducted for expansion ratios 4–8, Hartmann numbers 1000–5000, and Reynolds numbers 50–2000, spanning the viscous–electromagnetic (VE), inertial–electromagnetic (IE), and intermediate (IVE) regimes. The results reveal complex 3D current loops and flow reversals at high Hartmann numbers. Building on the Rhodes et al. (2018) formulation, we propose a modified correlation with a finite asymptotic term, applicable across VE, IVE, and IE regimes. The new model captures the numerical database with excellent accuracy

(R^{2} = 0.9914, R M S E = 0.0021)

and predicts a 3D MHD pressure drop of

Δ P_{3 D} = 1.50 k P a

under EU-DCLL operating conditions. These findings improve the theoretical consistency of MHD pressure-loss modeling and support manifold optimization for future DEMO blanket designs.

液态金属孕育包层磁流体动力（MHD）压力损失的可靠预测对DEMO反应堆设计至关重要。在欧洲双冷却剂铅锂（EU-DCLL）概念中，歧管膨胀和收缩预计将主导总压降。本研究使用定制的OpenFOAM求解器，研究了EU-DCLL底部歧管突然膨胀时的三维MHD压降。通过对解析解和基准数值代码的验证，显示出优越的稳定性和网格效率。在膨胀比为4-8、哈特曼数为1000-5000、雷诺数为50-2000的条件下，进行了45组模拟，涵盖粘电磁（VE）、惯性电磁（IE）和中间（IVE）模式。结果揭示了复杂的三维电流环和高哈特曼数下的流动逆转。在Rhodes等人（2018）公式的基础上，我们提出了与有限渐近项的修改相关性，适用于VE， IVE和IE制度。新模型以极好的精度捕获了数值数据库（R2=0.9914，RMSE=0.0021），并预测了EU-DCLL工况下MHD三维压降ΔP3D=1.50kPa。这些发现提高了MHD压力损失建模的理论一致性，并支持了未来DEMO毯层设计的流形优化。

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引用次数: 0

Preliminary study for a machine learning model for GENeuSIS GENeuSIS机器学习模型的初步研究

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

Fusion Engineering and Design

Pub Date : 2025-12-17 DOI: 10.1016/j.fusengdes.2025.115594

M. Damiano , R. Villari , A. Colangeli , D. Flammini , N. Fonnesu , P. Gaudio , M. Lungaroni , F. Moro , S. Noce , A. Previti , R. Rossi

In fusion reactors, a significant number of neutrons are generated, creating a harsh environment for reactor components. Testing sensitive devices, such as diagnostics and electronics is a key aspect to ensure proper and reliable operations in present and future tokamaks. To address this issue, the development of a dedicated facility is proposed: the GENeuSIS (General Experimental Neutron Systems Irradiation Station) project. GENeuSIS is a novel methodology designed to study and characterize the response of diagnostics, electronics, and other critical components of ITER, when exposed to the FNG (“Frascati Neutron Generator”) 14 MeV neutrons.

The GENeuSIS layout [1] consists of a layered structure made of moderating materials aimed at reproducing the expected neutron and gamma spectra in specific locations of the ITER machine under DT neutron irradiation.

Within this framework, a machine learning model helps automate the process of selection of the best materials and the configuration of assembly layouts to accurately reproduce the desired radiation environment. This work focuses on developing a supervised machine learning model (a neural network), that leverages a database generated from previous three-dimensional calculations of neutron and photon transport made using the Monte Carlo MCNP transport code. These simulations demonstrated the feasibility of GENeuSIS and its reliability in replicating the neutron spectrum in the ITER tokamak Port Interspace (GENeuSIS-I assembly) and the Port Cell (GENeuSIS-II assembly).

The machine learning model aims to streamline the pre-analysis phase and automatically determine the optimal combination of materials to replicate various neutron and gamma energy spectra.

This preliminary study presents the application of this new machine learning methodology to GENeuSIS, focusing first on reproducing fusion spectra given the different materials' configuration. The next step is to determine the best materials' configuration to replicate the ITER-relevant radiation field, given a chosen spectrum.

在聚变反应堆中，产生了大量的中子，为反应堆组件创造了一个恶劣的环境。测试敏感设备，如诊断和电子设备是确保当前和未来托卡马克正确可靠运行的关键方面。为了解决这个问题，建议开发一个专用设施：GENeuSIS（通用实验中子系统辐照站）项目。GENeuSIS是一种新颖的方法，用于研究和表征ITER的诊断、电子和其他关键部件在暴露于FNG（“弗拉斯卡蒂中子发生器”）14 MeV中子时的反应。genusis布局[1]由一层状结构组成，由减速材料制成，目的是在DT中子辐照下再现ITER机器特定位置的预期中子和伽马谱。在这个框架内，机器学习模型有助于自动化选择最佳材料和配置装配布局的过程，以准确地重现所需的辐射环境。这项工作的重点是开发一个有监督的机器学习模型（一个神经网络），该模型利用了以前使用蒙特卡洛MCNP传输代码进行的中子和光子传输的三维计算生成的数据库。这些模拟验证了GENeuSIS在ITER托卡马克端口空间（GENeuSIS- i组件）和端口单元（GENeuSIS- ii组件）中复制中子谱的可行性和可靠性。机器学习模型旨在简化预分析阶段，并自动确定材料的最佳组合，以复制各种中子和伽马能谱。这项初步研究介绍了这种新的机器学习方法在GENeuSIS中的应用，首先侧重于在给定不同材料配置的情况下再现融合光谱。下一步是确定最佳的材料配置来复制iter相关的辐射场，给定一个选定的光谱。

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引用次数: 0

A data-driven approach to estimate plasma density in TJ-II stellarator TJ-II仿星器等离子体密度估算的数据驱动方法

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

Fusion Engineering and Design

Pub Date : 2025-12-16 DOI: 10.1016/j.fusengdes.2025.115596

Paulo Aguayo , Gonzalo Farias , Alejandro González-Ganzábal , Ernesto Fabregas , Teresa Estrada , Boudewijn van Milligen , Alfonso Baciero , Belén López-Miranda , Francisco Medina , Giuseppe A. Rattá Gutiérrez

Magnetically confined fusion devices, such as the stellarator TJ-II, are highly complex infrastructures where plasma evolution is monitored through advanced diagnostic systems. Failures in these diagnostics can result in missing or unreliable data, compromising operational stability and experiment reliability. This work proposes a data-driven nowcasting approach to estimate missing plasma density signals using alternative sensor inputs, specifically validated for Electron Cyclotron Resonance Heating (ECRH) regimes. Our methodology uses a Two-Stage Learning Framework that integrates a Variational Autoencoder for latent feature extraction with Recurrent Neural Network blocks and a Multi-Head Attention mechanism. This architecture is designed to capture long-range temporal dependencies by broadcasting a single latent representation across multiple time steps, thus merging local and global temporal features. Extensive experiments on 201 ECRH-heated discharges from the TJ-II dataset demonstrate that deeper recurrent architectures, particularly those employing Long Short-Term Memory units, significantly outperform alternative models in nowcasting plasma density. The best-performing model achieves superior accuracy with a Weighted Mean Absolute Percentage Error (WMAPE) of 0.0328, complemented by low mean squared error and high coefficients of determination. This proof-of-concept study demonstrates the technical feasibility of deep learning-based nowcasting for diagnostic substitution in well-controlled ECRH operational conditions, establishing a methodological foundation for future extension to broader stellarator regimes.

磁约束聚变装置，如仿星器TJ-II，是高度复杂的基础设施，通过先进的诊断系统监测等离子体的演变。这些诊断失败可能导致数据丢失或不可靠，从而影响操作稳定性和实验可靠性。这项工作提出了一种数据驱动的临近投射方法，使用替代传感器输入来估计缺失的等离子体密度信号，特别针对电子回旋共振加热（ECRH）制度进行了验证。我们的方法使用两阶段学习框架，该框架集成了用于潜在特征提取的变分自编码器、递归神经网络块和多头注意机制。该架构旨在通过跨多个时间步广播单个潜在表示来捕获远程时间依赖性，从而合并本地和全局时间特征。对TJ-II数据集201个ecrh加热放电的大量实验表明，深层循环架构，特别是那些采用长短期记忆单元的架构，在临近投射等离子体密度方面明显优于其他模型。最佳模型的加权平均绝对百分比误差（WMAPE）为0.0328，具有较低的均方误差和较高的决定系数。这项概念验证研究证明了在控制良好的ECRH操作条件下，基于深度学习的临近预测用于诊断替代的技术可行性，为未来扩展到更广泛的仿星器系统奠定了方法学基础。

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引用次数: 0

Metallic glasses — Versatile radiation-tolerant materials for nuclear fusion applications 金属玻璃。核聚变用通用耐辐射材料

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

Fusion Engineering and Design

Pub Date : 2025-12-16 DOI: 10.1016/j.fusengdes.2025.115573

Martin E. Stiehler, Konstantinos Georgarakis

Nuclear fusion (NF) imposes unprecedented requirements on materials involved. Metallic glasses (MGs) offer an impressive set of properties that hold promise to overcome related challenges. These properties range from high corrosion resistance over high mechanical strength to high radiation tolerance including possible self-healing of irradiation-induced structural changes. Their high compositional flexibility allows MGs to be designed for optimal use in various areas of NF devices. Here we provide an introduction as to how these unique properties and related manufacturing processes can be exploited for a multitude of applications in NF. An outline of a development roadmap to expedite efforts in this direction is given.

核聚变（NF）对涉及的材料提出了前所未有的要求。金属玻璃（mg）提供了一系列令人印象深刻的特性，有望克服相关挑战。这些性能范围从高机械强度的高耐腐蚀性到高辐射耐受性，包括辐射引起的结构变化的可能自愈。它们的高组成灵活性允许mg被设计为在NF设备的各个领域的最佳使用。在这里，我们将介绍如何将这些独特的特性和相关的制造工艺用于NF中的众多应用。本文还概述了加快这方面努力的发展路线图。

引用次数: 0

Time domain reflectometry liquid level probe for the calibration of liquid lithium direct current conduction flowmeters 用于校准锂液直流传导流量计的时域反射式液位探头

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

Fusion Engineering and Design

Pub Date : 2025-12-15 DOI: 10.1016/j.fusengdes.2025.115583

S. Stemmley , B. Moore , D. O’Dea , R. Trendler , P.F. Buxton , P. Bunting , K. Moshkunov , M. Gryaznevich , D.N. Ruzic

Liquid lithium as a plasma-facing material has been shown to be beneficial to the performance of fusion plasmas due to it being low-Z and its strong gettering ability. A design that allows lithium to be circulated and cleaned ensures that lithium does not become saturated with fusion fuel and impurities. A liquid lithium loop has been developed at the University of Illinois with custom pumps and flowmeters to implement recirculating flow on a free-surface plasma-facing component. To de-risk and calibrate these components, a U-shaped vacuum chamber was constructed, enabling lithium to be pumped from a large reservoir tank, through a flowmeter, and into a level measurement chamber. A custom liquid level probe based on time domain reflectometry (TDR) with a 3 mm spatial resolution and a 1 ms temporal resolution was designed and constructed. The TDR probe was calibrated ex-situ and then used to calibrate the voltage signal from a direct current (DC) conduction flowmeter. The liquid level in the U-shaped vacuum chamber was measured as a function of time, allowing the mass flow rate of the lithium to be measured and matched to the flowmeter voltage signal. Flow rates up to 10 g s^-1 were measured and a calibration factor of

158 \pm 13

µV g^-1 s was determined for the custom DC conduction flowmeter.

液态锂作为等离子体表面材料，由于其低z和强吸散能力，已被证明有利于聚变等离子体的性能。允许锂循环和清洁的设计确保锂不会因聚变燃料和杂质而饱和。伊利诺伊大学（University of Illinois）开发了一种液体锂回路，配备了定制泵和流量计，可以在自由表面等离子体组件上实现再循环流动。为了降低风险并校准这些组件，设计了一个u形真空室，可以将锂从大型储液罐中抽出，通过流量计进入液位测量室。设计并制作了空间分辨率为3mm、时间分辨率为1ms的基于时域反射的定制液位探头。TDR探头在非原位校准，然后用于校准直流（DC）传导流量计的电压信号。测量u形真空室中的液位作为时间的函数，从而测量锂的质量流量，并与流量计电压信号匹配。测量了高达10 g s-1的流量，并确定了定制直流传导流量计的校准因子为158±13µV g-1 s。

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引用次数: 0

Distribution of He bubbles and dislocation loops in single-crystal W and W-ZrC materials after He2+ ion irradiation He2+辐照后W和W- zrc单晶材料中He气泡和位错环的分布

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

Fusion Engineering and Design

Pub Date : 2025-12-13 DOI: 10.1016/j.fusengdes.2025.115591

C.S. Ding , X.F. Xie , X.Y. Li , Y.J. Fu , H. Wang , R. Liu , X.B. Wu , X.P. Wang , Z.M. Xie

In this work, single-crystal W and W-ZrC alloys were irradiated with 500 keV helium (He) ions at both RT and 400 °C. Microstructural characterization revealed that both He bubble and dislocation loop densities within the grains of single-crystal W were higher than those in the W-ZrC alloy. The reduction in defect density in grains of W-ZrC is attributed to the presence of grain boundaries (GBs) and phase boundaries (PBs), which serve as effective sinks and provide preferential nucleation sites for irradiation-induced defects. Notably, PBs exhibited higher sink strength than GBs, resulting in the formation of He bubbles with greater size and density at PBs. Nanoindentation tests showed that single-crystal W exhibited more pronounced irradiation-induced hardening, with hardness increments of 2.8 GPa at room temperature (RT) and 2.3 GPa at 400 °C, which are higher than those of the W-ZrC alloy, demonstrating the enhanced irradiation tolerance of W-ZrC. The dispersed barrier hardening (DBH) model was employed to quantify the respective contributions of He bubbles and dislocation loops to hardening. The results indicated that He bubbles contributed approximately twice the hardening increment of dislocation loops in both materials. These findings clarify the critical role of interfaces in mediating defect evolution and irradiation responses, providing guidance for the design of W-based materials with improved irradiation tolerance for fusion applications.

本文采用500 keV氦离子辐照单晶W和W- zrc合金，在RT和400℃下辐照。显微组织表征表明，单晶W晶粒内He泡和位错环密度均高于W- zrc合金。W-ZrC晶粒中缺陷密度的降低是由于晶界（GBs）和相界（PBs）的存在，它们作为有效的“汇”，为辐照诱导缺陷提供了优先的形核位置。值得注意的是，PBs比gb表现出更高的沉降强度，导致在PBs下形成更大尺寸和密度的He气泡。纳米压痕实验表明，单晶W的辐照诱导硬化更为明显，室温下的硬度增量为2.8 GPa， 400℃时的硬度增量为2.3 GPa，高于W- zrc合金，表明W- zrc的辐照耐受性增强。采用分散势垒硬化（DBH）模型量化了He气泡和位错环对硬化的贡献。结果表明，He气泡对两种材料中位错环的硬化增量的贡献约为两倍。这些发现阐明了界面在介导缺陷演化和辐照响应中的关键作用，为设计具有更高辐照耐受性的w基材料提供了指导。

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引用次数: 0