Fusion Engineering and Design最新文献_第4页

Experimental study on particle crushing and pressure drop characteristics of Li4SiO4 breeder pebble beds Li4SiO4增殖层颗粒破碎及压降特性试验研究

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

Fusion Engineering and Design

Pub Date : 2025-12-30 DOI: 10.1016/j.fusengdes.2025.115604

Zheng Fang , Hao Cheng , Bing Zhou , Baoping Gong , Zhenzhong Li , Qiang Lian , Shanshan Bu , Deqi Chen

During long-term operation of tritium breeding blankets in fusion reactors, breeder particles are subjected to both irradiation and thermal stress, which can lead to particle fracture, thereby affecting the structural integrity of the pebble bed and the tritium breeding performance. This study investigates the fracture behavior of Li₄SiO₄ particles used in Helium-Cooled Ceramic Breeder (HCCB) blankets. In this work, Uniaxial cyclic compression tests were performed on breeder pebble beds to evaluate their mechanical response under different stress and temperature conditions. The particle breakage rate and fragment size distribution were obtained through sieving. Results indicated that increasing compressive stress and temperature led to higher breakage rates and a greater mass fraction of small fragments. Building on these fragmentation characteristics, multiple crushed packed beds with varying breakage rates (3–15%) and size distributions were configured to investigate particle breakage effects on purge-gas pressure drops, revealing that the helium pressure drop increases with the breakage rate. Crucially, the Ergun equation reliably predicted pressure drops for breakage rates ≤15%, with a maximum deviation of 10.6% under extreme fragmentation.

在聚变反应堆氚增殖包层长期运行过程中，增殖粒子受到辐照和热应力的双重作用，会导致粒子断裂，从而影响球床的结构完整性和氚增殖性能。本文研究了用于氦冷陶瓷增殖毯（HCCB）的Li₄SiO₄颗粒的断裂行为。在本工作中，进行了单轴循环压缩试验，以评估其在不同应力和温度条件下的力学响应。通过筛分得到颗粒破碎率和碎片大小分布。结果表明，压应力和温度的升高导致了更高的破碎率和更大的小碎片质量分数。在此破碎特性的基础上，配置不同破碎率（3-15%）和粒度分布的多个破碎充填层，研究颗粒破碎对吹扫气压降的影响，发现氦气压降随破碎率的增加而增加。至关重要的是，Ergun方程可靠地预测了破碎率≤15%时的压降，在极端破碎情况下最大偏差为10.6%。

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引用次数: 0

Design and simulation of a beam extraction and acceleration system for a small high-intensity neutron generator 小型高强度中子发生器束流提取与加速系统的设计与仿真

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

Fusion Engineering and Design

Pub Date : 2025-12-30 DOI: 10.1016/j.fusengdes.2025.115606

Jingtian Xu , Wen Wang , Qi Yang , Minghuang Wang , Shiyou Yang , FDS Consortium

A small high-intensity neutron generator imposes constraints on the beam extraction and acceleration system, which can deliver a deuterium/tritium (D/T) mixed ion beam with an energy of more than 200 keV and a current of more than 126 mA to the target within a limited space of 500 mm in length and 60 mm in radius. The beam at the target should have a spot radius of less than 40 mm and a peak current density of less than 50 A/m². In this work, beam transport simulations were conducted using the IBSIMU code. A preliminary design was obtained by iteratively optimizing the electrode geometry, which enables the transportation of a 200 keV, 126 mA D-T beam with a spot radius of 37 mm and a peak current density of 49.2 A/m² at the target. Based on this design, the effects of key geometric parameters, including the extraction gap, extraction aperture radius, acceleration gap, and acceleration aperture radius, on the beam spot radius and peak current density, were systematically analyzed. The results indicate that the variations in the extraction and acceleration gaps significantly affect the beam focusing condition, thus exerting a strong influence on the beam spot size and beam distribution. Under-focused transport conditions are more favorable for meeting the design requirements of the neutron generator. Variations in the extraction aperture radius and acceleration aperture radius do not modify the beam focusing condition and only marginally affect the beam spot and density, thereby allowing fine adjustments to be made according to practical requirements.

一个小型的高强度中子发生器对束流提取和加速系统施加了限制，该系统可以在长度为500mm、半径为60mm的有限空间内向目标输送能量超过200kev、电流超过126ma的氘/氚（D/T）混合离子束。激光束的光斑半径应小于40mm，峰值电流密度应小于50a /m²。在这项工作中，使用IBSIMU代码进行了波束输运模拟。通过对电极几何形状的迭代优化，得到了一个初步的设计方案，该设计方案可使200 keV、126 mA、光斑半径为37 mm、峰值电流密度为49.2 A/m2的D-T束流在目标处传输。在此基础上，系统分析了提取间隙、提取孔径半径、加速间隙和加速孔径半径等关键几何参数对光束光斑半径和峰值电流密度的影响。结果表明，提取间隙和加速间隙的变化会显著影响光束聚焦条件，从而对光束光斑大小和光束分布产生强烈影响。欠聚焦输运条件更有利于满足中子发生器的设计要求。提取孔径半径和加速孔径半径的变化不会改变光束聚焦条件，只会对光束光斑和密度产生轻微影响，可以根据实际需要进行微调。

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引用次数: 0

Demonstrating powder metallurgically produced long tungsten fiber-reinforced tungsten composite to serve as plasma-facing material 演示了粉末冶金法制备的长钨纤维增强钨复合材料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 : 2025-12-27 DOI: 10.1016/j.fusengdes.2025.115605

Yiran Mao , Jan Willem Coenen , Johann Riesch , Thomas Schwarz-Selinger , Elena Tejado , Arkadi Kreter , Alexis Terra , Marius Wirtz , Marcin Rasinski , Juan Du , Xiaoyue Tan , Yaohui Liu , Rudolf Neu , Christoph Broeckmann , Christian Linsmeier

For future fusion devices, tungsten is the main candidate materials for the application as plasma facing materials (PFMs). However, considering the challenging operational condition with high thermal loading/thermal stress combining plasma exposure and neutron irradiation/embrittlement, one of the major concern for tungsten as PFMs is its intrinsic brittleness. To avoid cracking and components failure, toughening tungsten is widely investigated, among which tungsten fiber reinforced tungsten composites (W_f/W) are developed using an extrinsic toughening mechanism. Recently, a new type of aligned long fiber W_f/W (L-W_f/W) with dedicated weak interface have been prepared by powder metallurgy process, combing the advantages of superb damage resilience with a much easier production compared to conventional chemical vapor deposition process. In this work, the newly developed material is characterized, including, mechanical tests, high heat flux tests, exposure to plasma for erosion and fuel retention tests. The l-W_f/W composite could improve significantly the damage resilience compared to pure W without altering much of other properties.

在未来的聚变装置中，钨是用作等离子体表面材料（pfm）的主要候选材料。然而，考虑到高热负荷/热应力结合等离子体暴露和中子辐照/脆化的具有挑战性的操作条件，钨作为pfm的主要问题之一是其固有的脆性。为了避免钨的断裂和部件失效，人们对钨的增韧进行了广泛的研究，其中利用外部增韧机制开发了钨纤维增强钨复合材料（Wf/W）。近年来，利用粉末冶金技术制备了一种专用弱界面定向长纤维Wf/W (L-Wf/W)，该材料具有优异的损伤回弹性和比传统化学气相沉积工艺更容易生产的优点。在这项工作中，对新开发的材料进行了表征，包括机械测试、高热流密度测试、暴露于等离子体进行侵蚀和燃料保留测试。与纯W相比，l-Wf/W复合材料在不改变其他性能的情况下显著提高了损伤回弹性。

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引用次数: 0

Design and analysis of PCHE-type recuperator for helium cooling system in CN HCCB TBS CN HCCB TBS氦冷却系统pche型回热器的设计与分析

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

Fusion Engineering and Design

Pub Date : 2025-12-27 DOI: 10.1016/j.fusengdes.2025.115603

Zhengning Zhao , Xinghua Wu , Jie Liu , Xingfu Ye , Hong Yang , Xiaoyu Wang

The Helium Cooling System (HCS) is an important ancillary system of the Chinese Helium-Cooled Ceramic Breeder Test Blanket System (CN HCCB-TBS) that provides cooling to remove heat from the fusion reactor blanket during plasma operation. The HCS is an “8″-shaped loop, in which a circulator provides the pressure head for the helium, while two heat exchangers and a heater are arranged to convert heat during operation. The recuperator is positioned at the center of the loop to transfer heat between the cold and hot helium streams, thereby enabling energy recovery and reducing loop energy consumption. Consequently, the design and selection of the recuperator significantly influence the operational stability and energy balance of the HCS. Printed Circuit Heat Exchangers (PCHEs) exhibit superior performance in terms of high-temperature and high-pressure capability, thermal efficiency, compactness, and operational reliability, making them widely applicable in petrochemical and hydrogen energy systems. This article presents the design and analysis of a PCHE-type recuperator based on specified requirements and project experience, providing valuable support for the design and manufacturing of future helium cooling loops and related applications.

氦冷却系统（HCS）是中国氦冷却陶瓷增殖试验包层系统（CN HCCB-TBS）的重要辅助系统，在等离子体运行过程中为聚变反应堆包层提供冷却以去除热量。HCS是一个“8″”形状的回路，其中一个循环器为氦气提供压力头，而两个热交换器和加热器则在运行过程中转换热量。回热器位于回路中心，在冷氦流和热氦流之间传递热量，从而实现能量回收，降低回路能耗。因此，回热器的设计和选择对HCS的运行稳定性和能量平衡有重要影响。印刷电路热交换器（PCHEs）在高温高压性能、热效率、紧凑性和运行可靠性方面表现出优异的性能，广泛应用于石化和氢能系统。本文根据规定的要求和项目经验，介绍了pche型回热器的设计和分析，为未来氦气冷却回路的设计和制造及相关应用提供了有价值的支持。

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引用次数: 0

Development and application of A-M combined TIG welding techniques for the ITER Blanket Shield Block 国际热核聚变实验堆包层屏蔽块A-M组合TIG焊接技术的开发与应用

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.2025.115600

Sa-Woong Kim , Jun-Sung Chang , Ji-Young Jeong , Duck-Hoi Kim

Active water cooling is designed to remove the nuclear heat generation in the Shield Block (SB). In some modules, the surface heat flux is also considered due to lack of First Wall (FW) coverage. According to the manufacturability assessment, the cooling channels in the SB are made by drilling process because it is preferable to manufacture the SBs from one single stainless steel forged block. The water headers are machined on the side of the SB, and closed by cover plates which have a thickness from 8 mm to 10 mm.

In this study, it is present a novel hybrid welding technique that combines the advantages of manual welding and robotic welding to address the unique challenges posed by conventional manual TIG welding. Manual TIG welding offers the flexibility and applicability required for variable weld geometries, while robotic welding provides the benefits of precision, repeatability, and increased productivity.

The development of the A-M combined welding process involves optimizing parameters such as welding speed, heat input and arc stability to achieve a seamless integration of manual and robotic welding techniques. Additionally, considerations for joint accessibility, weld quality and overall process efficiency are addressed to ensure the successful application of the hybrid approach in a complex welding environment.

The proposed approach not only meets the stringent requirements of ITER components but also provides a versatile solution that can be adapted to similar applications in advanced manufacturing scenarios.

主动水冷却设计用于消除屏蔽块（SB）中的核热产生。在一些模块中，由于缺乏第一壁（FW）覆盖，还考虑了表面热通量。通过可制造性评价，考虑到单根不锈钢锻件加工SBs的效果较好，采用钻孔工艺制作了SB的冷却通道。水集管被加工在SB的侧面，并由厚度从8 mm到10 mm的盖板封闭。本研究提出了一种新型的混合焊接技术，结合了手工焊接和机器人焊接的优点，以解决传统手工TIG焊接所面临的独特挑战。手工TIG焊接提供了可变焊缝几何形状所需的灵活性和适用性，而机器人焊接提供了精度、可重复性和提高生产率的好处。a - m组合焊接工艺的开发涉及到焊接速度、热输入和电弧稳定性等参数的优化，以实现人工和机器人焊接技术的无缝集成。此外，还考虑了接头可及性、焊接质量和整体工艺效率，以确保混合方法在复杂焊接环境中的成功应用。所提出的方法不仅满足ITER组件的严格要求，而且提供了一种通用的解决方案，可以适应先进制造场景中的类似应用。

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引用次数: 0

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