Fusion Engineering and Design最新文献_第5页

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

Progress on the design and related R&D activities for the novel solid-type PbxLiy breeding blanket for CFETR CFETR新型固体型PbxLiy育种毯的设计与研发进展

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.2025.115587

Kecheng Jiang , Lei Chen , Qiuran Wu , Yang Xiao , Songsen Wang , Songlin Liu

In this paper, we present a solid-type Pb_xLi_y blanket and related R&D activities. This blanket concept is designed to enhance the Technical Readiness Level (TRL) by addressing risks identified in both current solid and liquid blanket designs. It employs Pb_xLi_y with a high melting point as both neutron multiplier and tritium breeder, configured in the form of pebble beds within the solid blanket. This approach leverages mature tritium extraction technologies already developed for solid blankets, while eliminating the need for expensive beryllium. At this stage, a conceptual design of the blanket has been developed to verify its compliance with neutronics and thermal-hydraulics performance requirements. Additionally, initial fabrication of this material has been attempted, and preliminary characterizations, including density, chemical reactivity with water, and composition, have been conducted. The results confirm that the dominate composition is the Pb_xLi_y alloy with high melting point. i.e. Li₄Pb, Li₃Pb, Li₅Pb₂ and Li₁₀Pb₃. However, there is still some purely lithium and Pb_xLi_y at lower melting point 481.9 °C. Therefore, we need to improve the manufacturing methods to make it much more purely with high melting point, e.g. Pb₂₈Li₇₂ at 650 °C. In the following, we will find new way to make the element Pb/Li mixing much more uniformly, and cool them instantly during the mixing to make the solid-type Pb_xLi_y more purely.

本文介绍了一种固体型PbxLiy毛毯及其研发活动。该包层概念旨在通过解决当前固体和液体包层设计中确定的风险来提高技术准备水平（TRL）。它采用高熔点的PbxLiy作为中子倍增器和氚增殖剂，在固体包层内以卵石床的形式配置。这种方法利用了已经为固体包层开发的成熟的氚提取技术，同时消除了对昂贵的铍的需求。在这个阶段，已经开发了一个毯层的概念设计，以验证其符合中子和热工性能要求。此外，已经尝试了这种材料的初始制造，并进行了初步表征，包括密度、与水的化学反应性和成分。结果表明，合金的主要成分为高熔点的PbxLiy合金。即Li4Pb， Li3Pb， Li5Pb2和Li10Pb3。然而，在较低的熔点481.9℃下仍有一些纯锂和PbxLiy。因此，我们需要改进制造方法，使其更加纯净，具有高熔点，例如Pb28Li72在650℃下。接下来，我们将寻找新的方法，使元素Pb/Li的混合更加均匀，并在混合过程中立即冷却，使固体型PbxLiy更加纯净。

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引用次数: 0

Corrigendum to “Predictive modelling of tritium breeding ratio (TBR) in EU DEMO WCLL blankets: OpenMC simulations and analytical insights” [FUSION, 222, January 2026, 115516] “EU DEMO WCLL包层中氚增殖比（TBR）的预测建模：OpenMC模拟和分析见解”的勘误表[FUSION]， 222, January 2026, 115516]

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.2025.115589

Maxime Chiletti, Noureddine Rebiai, Dahmane Mazed, Frédéric Gérardin

引用次数: 0

Convective heat transfer of high-temperature nitrogen in the geometrically intricate EAST divertor: experimental study and correlation for baking process 几何复杂的EAST导流器中高温氮气的对流换热：烘烤过程的实验研究与关联

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

Fusion Engineering and Design

Pub Date : 2025-12-12 DOI: 10.1016/j.fusengdes.2025.115590

Zhe Liu , Peng Fu , Bin Guo

To enhannce the baking efficiency and improve operational safety of the EAST tokamak, this work experimentally investigates the convective heat transfer characteristics of high-temperature nitrogen flowing through the geometrically intricate and confined passages of the EAST divertor under baking process. A dedicated experiment system was designed and constructed to cover the full operational parameter range of the EAST baking process. The experimental investigations covered full parameter range of the EAST baking process. Results demonstrate that both the convective heat transfer coefficient and the inlet-outlet temperature difference in the test section are significantly governed by the combined effects of the inlet temperature and flow velocity. A modified convective heat transfer correlation was developed by extending the classical formulation, based on statistical analysis of the experimental data. Validation results show that predictions using the modified correlation agree well with experimental measurements, within deviations consistently constrained within

\pm 10 %

. The findings provide essential foundations for baking efficiency optimization in fusion devices.

为了提高EAST托卡马克的焙烧效率和运行安全性，本文对高温氮气在焙烧过程中流经EAST导流器几何形状复杂且密闭通道的对流换热特性进行了实验研究。设计并搭建了一个专门的实验系统，涵盖了EAST烘焙过程的全部操作参数范围。实验研究涵盖了EAST烘烤过程的全部参数范围。结果表明：试验段的对流换热系数和进出口温差受入口温度和流速的综合影响显著；在对实验数据进行统计分析的基础上，对经典公式进行了推广，建立了一个修正的对流换热关系式。验证结果表明，使用修正相关性的预测与实验测量结果吻合良好，偏差一致限制在±10%以内。研究结果为优化核聚变装置的烘烤效率提供了必要的基础。

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引用次数: 0

Evidence of silver impurities in irradiated Cu-based alloys and implications for the long-lived radioactive waste from ITER 辐照铜基合金中银杂质的证据及其对ITER长寿命放射性废物的影响

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

Fusion Engineering and Design

Pub Date : 2025-12-12 DOI: 10.1016/j.fusengdes.2025.115575

A. Wójcik-Gargula , R. Kierepko , U. Wiącek , A. Valentine , C.L. Grove , J.W. Mietelski , L.W. Packer , X. Litaudon , R. Villari , JET Contributors

The activation of trace silver impurities in CuCrZr alloys has been investigated in relation to their radiological relevance for ITER. While silver is not an intentional alloying element, its presence in raw copper or introduced during processing can lead to the formation of long-lived radionuclides. Gamma spectrometry measurements confirmed the production of Ag-110m in irradiated CuCrZr samples, while the potential contribution of Ag-108m was assessed through activation modelling. FISPACT-II calculations were used to quantify their activity and shutdown dose rates (SDR) under ITER-relevant neutron spectra. The results show that Ag-110m can generate initial contact dose rates of approximately 400 µSv h⁻¹ per kg, remaining above 100 µSv h⁻¹ for about one year post-irradiation, before decreasing to ∼20 µSv h⁻¹ after 3 years and ∼0.016 µSv h⁻¹ after 10 years. In contrast, Ag-108m contributes consistently low dose rates (∼0.5 µSv h⁻¹), but owing to its 438-year half-life it remains a persistent part of the radiological inventory. While silver isotopes do not dominate the total SDR compared to major contributors such as Cu-64 and Co-60, minor impurities may have an impact on the radiological behaviour of structural alloys that is larger than expected from their concentration. These findings highlight the importance of reliable impurity characterisation for structural alloys used in fusion devices, particularly when relying on commercial feedstocks or uncertified batches.

研究了CuCrZr合金中痕量银杂质的活化与ITER的放射性相关性。虽然银不是故意的合金元素，但它在铜原料中的存在或在加工过程中引入可能导致长寿命放射性核素的形成。伽马能谱测量证实了辐照CuCrZr样品中Ag-110m的产生，而Ag-108m的潜在贡献通过激活模型进行了评估。使用FISPACT-II计算，在iter相关中子谱下量化其活度和关闭剂量率（SDR）。结果表明，Ag-110m可以产生大约400µSv h -每公斤的初始接触剂量率，在照射后大约一年内保持在100µSv h -⁻，3年后下降到~ 20µSv h -⁻，10年后下降到~ 0.016µSv h -⁻。相反，Ag-108m的剂量率一直很低（~ 0.5 μ Sv h⁻），但由于其438年的半衰期，它仍然是放射性清单的一部分。虽然与Cu-64和Co-60等主要贡献者相比，银同位素在总SDR中并不占主导地位，但少量杂质可能对结构合金的放射性行为产生比其浓度预期更大的影响。这些发现强调了用于熔合装置的结构合金的可靠杂质表征的重要性，特别是当依赖于商业原料或未经认证的批次时。

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引用次数: 0

Large-scale indexing system for ITER data handling ITER数据处理的大规模索引系统

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.2025.115577

R. Castro , Y. Makushok , L. Abadie , J. Vega

ITER, one of the most advanced fusion projects, requires handling massive amounts of data generated in real time and stored in distributed repositories. The diversity in the nature of the data, from control variables to fast acquisition signals, poses significant challenges for efficient access and organization of the information. This paper presents a large-scale indexing system designed to meet these needs. The system, integrated into ITER's CODAC core, implements a distributed and scalable architecture that ensures real-time indexing, robustness, and fault tolerance. Its design, implementation and performance are described here, highlighting its capacity to handle more than one petabyte of data per day and respond in real time to user and system requests. This breakthrough contributes significantly to efficient data handling in long-lived fusion environments.

ITER是最先进的核聚变项目之一，需要处理实时生成并存储在分布式存储库中的大量数据。数据性质的多样性，从控制变量到快速采集信号，对信息的有效访问和组织提出了重大挑战。本文提出了一个大型标引系统，旨在满足这些需求。该系统集成到ITER的CODAC核心中，实现了分布式和可扩展的架构，确保了实时索引、鲁棒性和容错性。这里描述了它的设计、实现和性能，重点介绍了它每天处理超过1pb数据的能力，并实时响应用户和系统请求。这一突破为在长寿命的聚变环境中高效处理数据做出了重大贡献。

引用次数: 0