Fusion Engineering and Design最新文献_第8页

Numerical analysis of 60° V-ribs for helium-cooled high heat flux loaded first wall, challenges and contributions 氦冷高热流负载第一壁60°v型肋的数值分析、挑战和贡献

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

Fusion Engineering and Design

Pub Date : 2025-12-02 DOI: 10.1016/j.fusengdes.2025.115527

Ch. Klein, F. Arbeiter, M Enke

The HCPB (Helium Cooled Pebble Bed) blanket concept for EU DEMO fusion reactors employs high-pressure (8 MPa) helium gas as coolant for the plasma facing first wall (FW). Up-to-date estimates for the total maximum of heat flux go up to 0.73 MW/m². Higher short-term transient loads are possible. 60°-V-shaped ribs show high heat transfer and are thus the subject of the presented studies. Although Scale-Resolving Simulation (SRS) techniques such as LES (Large Eddy Simulation) are able to calculate heat transfer and pressure drop precisely, their application is limited to an individual ribs or a few mm channel segment due to the high required mesh count. Nevertheless, SRS techniques can be used to compare different ribs and to evaluate the performance of RANS (Reynolds-Averaged Navier-Stokes Simulations). Selected RANS models can be used to evaluate the development of secondary flow structures along the channel and compare complete channels with different rib configurations for thermohydraulic performance.

The objectives of the present paper are (i) to offer guidance on the range and limits of applicability of numerical methods when dealing with cooling flows in structured channels (sections 1–4) and (ii) to provide results on specific design features of surface structures (sections 5–7) that help designers in implementing thermal-hydraulic efficient yet fabrication friendly structured channels

Challenges like long entrance length and high material properties gradients are shown. Strategies for ribs height reduction with increasing heat transfer and reduction of pressure drop resulting in higher Cooling Performance Numbers (CPN) are found. Thermohydraulic performance of fabrication friendly ribs is calculated along the channel.

用于EU DEMO聚变反应堆的HCPB（氦冷却球床）包层概念采用高压（8 MPa）氦气作为面向第一壁（FW）的等离子体的冷却剂。最新估计的最大总热通量高达0.73 MW/m²。更高的短期暂态负载是可能的。60°v形肋具有高的传热性能，因此是本研究的主题。尽管像LES（大涡模拟）这样的尺度解析模拟（SRS）技术能够精确地计算传热和压降，但由于需要很高的网格数，它们的应用仅限于单个肋或几毫米的通道段。然而，SRS技术可以用来比较不同的肋，并评估RANS （reynolds - average Navier-Stokes simulation）的性能。所选择的RANS模型可用于评估通道沿线二次流结构的发展，并比较不同肋形的完整通道的热水力性能。本论文的目的是(i)在处理结构通道中的冷却流动时，提供关于数值方法的适用范围和限制的指导（第1-4节）；（ii）提供表面结构的特定设计特征的结果（第5-7节），帮助设计师实现热水力高效且制造友好的结构通道。研究了降低肋部高度、增加传热和降低压降从而提高冷却性能数值的策略。沿通道计算了加工友好肋的热工性能。

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引用次数: 0

Nuclear, thermal, and shielding design of test cell in A-FNS A-FNS试验单元的核、热、屏蔽设计

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

Fusion Engineering and Design

Pub Date : 2025-12-02 DOI: 10.1016/j.fusengdes.2025.115549

Shogo Honda, Saerom Kwon, Shunsuke Kenjo, Makoto Oyaidzu, Kentaro Ochiai, Satoshi Sato

Significant quantities of neutrons and gamma rays deduce the nuclear heating on the shielding walls of the test cell (TC) in the A-FNS. This study presents nuclear and thermal analyses of the shielding wall in the A-FNS to evaluate its radiation-shielding effectiveness and cooling capacity. Previous designs incorporated cooling water pipes embedded in the concrete shielding wall for thermal management. However, we determined that this approach failed to maintain concrete temperatures within specified limits due to the low thermal conductivity of concrete and the challenge of ensuring adequate contact between the concrete and piping. We developed a new shielding wall design that eliminates the need for cooling pipes inside the concrete. This updated design integrates an 85 cm of stainless steel 316 L (SS316L) structure containing 20 % cooling water positioned in front of the concrete, which maintains concrete temperatures within acceptable limits. In addition, nuclear assessments of this revised shielding wall structure were conducted to verify its radiation shielding capacity. Results indicate that the effective dose criteria are met at thicknesses of 255 cm for heavy concrete and 335 cm for ordinary concrete when the 85 cm of combing structure of SS316L/water (20 % water) is included.

在A-FNS中，大量的中子和伽马射线推断出测试单元（TC）屏蔽壁上的核加热。本文对A-FNS屏蔽墙进行了核分析和热分析，以评估其辐射屏蔽效果和冷却能力。以前的设计将冷却水管嵌入混凝土屏蔽墙中进行热管理。然而，由于混凝土的低导热性和确保混凝土与管道之间充分接触的挑战，我们确定这种方法无法将混凝土温度保持在规定的范围内。我们开发了一种新的屏蔽墙设计，消除了混凝土内部冷却管道的需要。这个更新的设计集成了一个85厘米的不锈钢316L （SS316L）结构，其中20%的冷却水位于混凝土前面，将混凝土温度保持在可接受的范围内。此外，还对改进后的屏蔽墙结构进行了核评估，验证了其辐射屏蔽能力。结果表明，当SS316L/水（20%水）混合结构为85 cm时，在厚混凝土厚度为255 cm、普通混凝土厚度为335 cm时满足有效剂量标准。

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引用次数: 0

Design and initial results from the “Junior” Levitated Dipole Experiment “少年”悬浮偶极子实验的设计和初步结果

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

Fusion Engineering and Design

Pub Date : 2025-12-02 DOI: 10.1016/j.fusengdes.2025.115551

C.S. Chisholm , T. Berry, D.T. Garnier, R.A. Badcock, G. Bioletti, K. Bouloukakis , E. Brewerton, M.A. Buchanan, P.J. Burt, E.V.W. Chambers, K.B. Chappell, P. Coulson, R.J. Davidson, J.P.M. Ellingham, P. Geursen, K. Hamilton, R. Hu, E. Hunter, J.P. Jones, P. Kusay, N. Zhou

OpenStar Technologies is a private fusion company exploring the levitated dipole concept for commercial fusion energy production. OpenStar has manufactured a new generation of levitated dipole experiment, called “Junior”, leveraging recent advances made in high-temperature superconducting magnet technologies. Junior houses a

\sim

5.6 T REBCO high-temperature superconducting magnet in a 5.2 m vacuum chamber, with plasma heating achieved via

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50 kW of electron cyclotron resonance heating power. Importantly, this experiment integrates novel high temperature superconductor power supply technology on board the dipole magnet. Recently OpenStar has completed first experimental campaigns with the Junior experiment, achieving first plasmas in late 2024. Experiments conducted with the full levitated system are planned for 2025. This article provides an overview of the main results from these experiments and details improvements planned for future campaigns.

OpenStar Technologies是一家私营核聚变公司，正在探索将悬浮偶极子概念用于商业核聚变能源生产。OpenStar利用高温超导磁体技术的最新进展，制造了新一代悬浮偶极子实验装置，称为“Junior”。Junior在5.2 m的真空室中放置了一个5.6 T的REBCO高温超导磁体，通过50 kW的电子回旋共振加热功率实现等离子体加热。重要的是，本实验将新型高温超导电源技术集成在偶极磁体上。最近，OpenStar已经完成了初级实验的第一次实验活动，在2024年底实现了第一个等离子体。全悬浮系统的实验计划在2025年进行。本文概述了这些实验的主要结果，并详细介绍了未来活动的改进计划。

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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 : 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

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 : 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

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 : 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

Hierarchical robust optimization framework for tokamak in-vessel maintenance manipulator design 托卡马克船内维修机械手设计的层次鲁棒优化框架

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

Fusion Engineering and Design

Pub Date : 2025-11-29 DOI: 10.1016/j.fusengdes.2025.115546

Fei Li, Wusheng Chou, Zhongyang Li

Remote maintenance inside the Tokamak vacuum vessel is constrained by extreme radiation, high temperature, and limited space, posing stringent requirements on manipulator design. This paper presents a hierarchical robust optimization framework that decomposes the design process into macro-level feasibility assurance and micro-level worst-case performance optimization. At the macro level, a feasibility heatmap method is introduced, which systematically identifies the minimum feasible configuration. Results show that a 4-DOF planar manipulator with

L_{total} = 5645 mm

and joint limits of

\pm

150° provides the optimal macro design. At the micro level, a Minimax robust optimization model is formulated to minimize the worst-case Jacobian condition number, and an improved Refined Pattern Search–Simulated Annealing (RPSA) algorithm is developed to solve it efficiently. Case studies demonstrate that the proposed method reduces the worst-case condition number from 9942.5 to 5021.2, with an average improvement of 28% and up to 55% at critical task points. The framework offers a systematic and generalizable pathway for early-stage manipulator design in Tokamak in-vessel maintenance, improving both feasibility assurance and robustness under extreme operating conditions.

托卡马克真空容器内部的远程维护受到极端辐射、高温和有限空间的限制，对机械手的设计提出了严格的要求。本文提出了一种分层鲁棒优化框架，将设计过程分解为宏观层面的可行性保证和微观层面的最坏情况性能优化。在宏观层面，引入可行性热图方法，系统地识别最小可行构型。结果表明，Ltotal=5645mm、关节极限为±150°的4自由度平面机械臂提供了最优的宏观设计。在微观层面，建立了最小化最坏情况雅可比条件数的Minimax鲁棒优化模型，并提出了改进的精细模式搜索-模拟退火（RPSA）算法来有效地求解该问题。案例研究表明，该方法将最坏情况数从9942.5个减少到5021.2个，在关键任务点平均提高28%，最高可达55%。该框架为托卡马克船内维修操作机的早期设计提供了系统的、可推广的途径，提高了极端工况下的可行性保证和鲁棒性。

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引用次数: 0

Applicability of two-color pyrometer for surface temperature measurements of ceramics, promising as plasma-facing materials 双色高温计在陶瓷表面温度测量中的适用性，有望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 : 2025-11-28 DOI: 10.1016/j.fusengdes.2025.115545

G.A. Ryzhkov , D.E. Cherepanov , M.A. Golosov , A.A. Kasatov , V.A. Popov , L.N. Vyacheslavov , N.I. Baklanova , G.G. Lazareva

Temperature measurement in plasma-surface interaction studies is an important task. Pyrometry is widely used for these purposes. This study evaluates the accuracy of a two-color pyrometer developed to investigate thermal shock effects in high-temperature ceramics – promising plasma-facing materials of fusion devices. Based on emissivity data of such ceramic materials as boron carbide (B

_{4}

C), silicon carbide (SiC) and zirconium diboride (ZrB

_{2}

), calculations showed the possibility of using this method to measure temperatures in the range of 1200–2000 K. Experimental temperature measurements during the pulsed heating of the specified ceramics showed that the deviations of single color temperatures from two-color ones were less than 5%, which demonstrates the suitability of the two-color method for measuring the surface temperatures of these materials.

温度测量是等离子体表面相互作用研究中的一项重要任务。高温法被广泛用于这些目的。本研究评估了一种双色高温计的准确性，该双色高温计用于研究高温陶瓷-聚变装置中有前途的等离子体表面材料的热冲击效应。基于碳化硼（B4C）、碳化硅（SiC）和二硼化锆（ZrB2）等陶瓷材料的发射率数据，计算表明该方法可以测量1200 ~ 2000 K范围内的温度。脉冲加热陶瓷时的实验温度测量结果表明，单色温度与双色温度的偏差小于5%，证明了双色法测量这些材料表面温度的适用性。

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引用次数: 0

Construction and preliminary discharge investigation of a proton-boron linear plasma device 质子-硼线性等离子体装置的构建与初步放电研究

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

Fusion Engineering and Design

Pub Date : 2025-11-27 DOI: 10.1016/j.fusengdes.2025.115544

Shuang Yang , Lei Li , Shangzhi Wu , Yanqing Wang , Yumin Wang , Haishan Zhou , Xiang Liu , Kaiming Feng , Minsheng Liu

ENN Science and Technology Development Co., Ltd. (ENN) has designed and constructed a specialized proton-boron linear plasma device, ENN-PSI, to investigate the irradiation-resistance performance of divertor materials. The plasma source, which employs a cascaded arc and hot cathode configuration, has successfully achieved stable proton-boron plasma discharges using diborane gas. The device was operated under a magnetic field exceeding 0.6 T and the plasma beam diameter was around 15 mm. Langmuir probe diagnostics results indicate electron temperature (T_e) above 8 eV, particle flux exceeding 1 × 10²² m^-²s^-1, and electron density (n_e) greater than 1 × 10¹⁸ m^-³. These parameters meet the fundamental experimental requirements for proton-boron plasma material irradiation research, providing a robust platform for advancing the understanding of divertor material performance under proton-boron fusion conditions.

新奥科技发展有限公司（ENN）设计并制造了专用质子-硼线性等离子体装置ENN- psi，用于研究导流材料的耐辐照性能。等离子体源采用级联电弧和热阴极结构，利用二硼烷气体成功地实现了稳定的质子-硼等离子体放电。该装置在超过0.6 T的磁场下运行，等离子体束直径约为15 mm。Langmuir探针诊断结果表明，电子温度（Te）大于8 eV，粒子通量大于1 × 10²m-²s-1，电子密度（ne）大于1 × 10¹⁸m-³。这些参数满足质子-硼等离子体材料辐照研究的基本实验要求，为进一步了解质子-硼聚变条件下的导流材料性能提供了坚实的平台。

引用次数: 0

Simulated bombardment of diamond grain boundaries with deuterium 模拟氘对金刚石晶界的轰击

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

Fusion Engineering and Design

Pub Date : 2025-11-27 DOI: 10.1016/j.fusengdes.2025.115535

J.A. Pittard , M.Y. Lavrentiev , N.A. Fox

Diamond has several possible applications within fusion reactors, including windows, sensors/diagnostics and has shown promise as a plasma facing material. For some of these applications, polycrystalline diamond may be preferable to single crystal, meaning the impact of grain boundaries on retention mechanisms needs to be understood. As such, this work presents molecular dynamics simulations of deuterium bombardment normal to the (110) surface of four grain boundaries common to diamond grown via chemical vapour deposition. Repeated single bombardments of pristine structures showed channelling effects for some grain boundaries, that resulted in very high penetration depths. Furthermore, the additional space present in the grain boundaries allowed vacancies to form along the grain boundary at depths comparable to the deuterium depth - in contrast to bulk regions for which vacancy formation was limited to the surface. For continuous bombardment simulations, the formation of a disordered layer prevented channelling effects from playing a significant role, particularly for higher energies. A small increase in retention was observed in grain boundaries which was thought to be a result of the additional space within the grain boundary. Results presented here suggest changes in retention would be small for polycrystalline diamond of reasonable grain size.

金刚石在核聚变反应堆中有几种可能的应用，包括窗口、传感器/诊断，并且已经显示出作为等离子体表面材料的前景。对于其中的一些应用，多晶金刚石可能比单晶金刚石更好，这意味着需要了解晶界对保留机制的影响。因此，本研究提出了通过化学气相沉积生长的金刚石常见的四个晶界（110）表面的氘轰击分子动力学模拟。原始构造的重复单次轰击在某些晶界上显示出通道效应，这导致了非常高的穿透深度。此外，晶界中存在的额外空间允许沿晶界在与氘深度相当的深度形成空位，这与空位形成仅限于表面的大块区域形成对比。对于连续轰击模拟，无序层的形成阻止了通道效应发挥重要作用，特别是对于高能量。在晶界中观察到少量的滞留，这被认为是晶界内额外空间的结果。本文的研究结果表明，对于合理晶粒尺寸的聚晶金刚石，保留的变化很小。

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引用次数: 0