Fusion Engineering and Design最新文献_第7页

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 : 2026-03-01 Epub 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

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 : 2026-03-01 Epub 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

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 : 2026-03-01 Epub 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

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 : 2026-03-01 Epub 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

Integrated design of a snake endoscopic manipulator system for in-vessel observation of fusion reactors 用于聚变反应堆容器内观测的蛇形内窥镜操作系统集成设计

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

Fusion Engineering and Design

Pub Date : 2026-02-01 Epub Date: 2025-12-10 DOI: 10.1016/j.fusengdes.2025.115582

Shijie Liu , Kun Lu , Yong Cheng , Youzhi Xu , Lei Zheng , Guodong Qin , Hongtao Pan

Addressing the challenge of real-time monitoring for fusion reactor vacuum vessel components during operational intervals, this paper proposes an integrated observation system design based on a snake endoscopic manipulator (SEM). The system adopts a compact integrated design, installed at a specific 20-degree inclination angle within the reactor’s lower port to optimize spatial layout. Its core components include: a SEM with storage tube and end-effector observation equipment, a tube plug flipping mechanism, and a bellows dynamic sealing device. The storage tube is welded to the observation window of the passive plate and penetrates the blind flange; the innovatively designed plug flipping mechanism seals the window during non-observation periods, with its drive unit located in the non-vacuum area outside the blind flange and motion controlled via drive rods sealed by metal bellows; the manipulator executes inspection tasks using a trajectory tracking algorithm. Integrated with digital twin technology for design and verification, this system efficiently accomplishes full-process tasks—including trajectory planning, target localization, online observation, and system reset—during reactor operational intervals, significantly enhancing inspection efficiency, reducing operational costs, and providing a highly reliable in-service observation solution to support fusion reactor commercialization.

针对核聚变反应堆真空容器部件运行间隔实时监测的挑战，提出了一种基于蛇形内窥镜操作器的集成观测系统设计。系统采用紧凑的集成化设计，安装在反应器下孔内特定的20度倾角，优化空间布局。其核心部件包括：带存储管和末端执行器观察设备的扫描电镜、管塞翻转机构、波纹管动态密封装置。存储管焊接在被动式板的观察窗上，并穿透盲法兰；创新设计的塞子翻转机构在非观测期间密封窗户，其驱动单元位于盲法兰外的非真空区域，通过金属波纹管密封的驱动杆控制运动；该机械手使用轨迹跟踪算法执行检测任务。该系统集成了用于设计和验证的数字孪生技术，在反应堆运行间隔期间有效地完成全过程任务，包括轨迹规划、目标定位、在线观测和系统复位，显著提高了检查效率，降低了运行成本，并提供了高度可靠的在役观测解决方案，以支持聚变反应堆商业化。

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引用次数: 0

Mathematical modeling and design of a microwave polarizer for DTT ECRH applications DTT ECRH微波偏振器的数学建模与设计

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

Fusion Engineering and Design

Pub Date : 2026-02-01 Epub Date: 2025-12-03 DOI: 10.1016/j.fusengdes.2025.115552

Sofia Bertolami , Franco Di Paolo , Alessandro Bruschi , Francesco Fanale , Alessandro Moro , Saul Garavaglia , Gustavo Granucci , Afra Romano , Alessandro Simonetto

In an Electron Cyclotron Resonance Heating (ECRH) system, to efficiently couple the signal power to the plasma, the signal wave polarization must be accurately matched to the plasma conditions at the plasma boundary. However, the millimeter-wave radiation from the power source (gyrotron) is normally linearly polarized: consequently, some kind of polarization matching is required. This study focuses on the design of a grating polarizer with sinusoidal grooves for the 170 GHz ECRH system, with an application specifically intended for the Divertor Tokamak Test (DTT), currently under construction in Frascati, Italy. To enable the generation of all possible output polarization states, a pair of polarizer mirrors will be employed and integrated into the Quasi-Optical (QO) transmission line connecting the gyrotrons to the Electron Cyclotron (EC) waves launchers. The primary objective of this study is to describe an analytical tool capable of providing detailed insights into the polarization characteristics of the reflected electric field resulting from the interaction between the incident wave and the polarizer. Additionally, the proposed program tool calculates the precise combinations of rotation angles required for the polarizers to achieve the desired output polarization states. The accuracy and reliability of the model’s prediction have been validated by comparing them with simulations conducted using commercial electromagnetic software.

在电子回旋共振加热（ECRH）系统中，为了有效地将信号功率与等离子体耦合，必须精确匹配等离子体边界处的信号波极化情况。然而，来自电源（回旋管）的毫米波辐射通常是线极化的，因此需要进行某种极化匹配。本研究的重点是为170 GHz ECRH系统设计一种带有正弦沟槽的光栅偏振器，该偏振器专门用于目前正在意大利弗拉斯卡蒂进行的托卡马克转向器测试（DTT）。为了能够产生所有可能的输出偏振状态，将使用一对偏振镜并将其集成到连接回旋加速器和电子回旋加速器（EC）波发射器的准光学（QO）传输线中。本研究的主要目的是描述一种分析工具，该工具能够提供详细的见解，以了解由入射波和偏振器之间的相互作用产生的反射电场的偏振特性。此外，所提出的程序工具计算所需的旋转角度的精确组合，以实现所需的输出偏振状态的偏振器。通过与商用电磁软件模拟结果的对比，验证了模型预测的准确性和可靠性。

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引用次数: 0

Preliminary study on the development of the fluidic system for the fabrication of pebble with core–shell structure 核-壳结构卵石制备流体系统开发的初步研究

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

Fusion Engineering and Design

Pub Date : 2026-02-01 Epub Date: 2025-12-02 DOI: 10.1016/j.fusengdes.2025.115547

Young Ah Park , Yi-Hyun Park , Mu-Young Ahn , Young Soo Yoon

Li₄SiO₄, used as a tritium breeder material in fusion reactors, has high lithium density but suffers from lower mechanical strength compared to another promising material, Li₂TiO₃. In this study, a fluidic system was designed to fabricate core-shell structured pebbles (Li₄SiO₄–Li₂TiO₃) consisting of a Li₄SiO₄ core and a Li₂TiO₃ shell. The system was constructed using a T–shaped fluid flow channel with a double–tube design, enabling the controlled formation of core-shell droplets by adjusting the flow rates of the continuous and dispersed phases. The resulting Li₄SiO₄–Li₂TiO₃ pebbles exhibited a crush load approximately 2.03 times higher than that of single-phase Li₄SiO₄ pebbles, and the stable formation of the core–shell structure was confirmed. This study presents a novel fabrication process with the potential to enhance the mechanical performance of Li₄SiO₄ as a tritium breeder material.

Li4SiO4，用作聚变反应堆中的氚增殖材料，具有高锂密度，但与另一种有前途的材料Li2TiO3相比，机械强度较低。在本研究中，设计了一个流体系统来制造由Li4SiO4核和Li2TiO3壳组成的核-壳结构鹅卵石（Li4SiO4 - Li2TiO3）。该系统采用双管设计的t型流体流道，通过调节连续相和分散相的流速来控制核壳液滴的形成。所得Li4SiO4 - li2tio3鹅卵石的破碎载荷比单相Li4SiO4鹅卵石高约2.03倍，并证实了核壳结构的稳定形成。本研究提出了一种新的制造工艺，有可能提高Li4SiO4作为氚增殖材料的机械性能。

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引用次数: 0

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 : 2026-02-01 Epub 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

An optimization approach for cryogenic distillation-based protium removal systems in magnetic fusion energy fuel cycles 磁聚变能燃料循环中基于低温蒸馏的脱丙系统的优化方法

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

Fusion Engineering and Design

Pub Date : 2026-02-01 Epub Date: 2025-12-09 DOI: 10.1016/j.fusengdes.2025.115534

Alex D. Somers, P. Arron Rowell, Collin R. Malone, Holly B. Flynn, George K. Larsen

Tritium inventory reduction for fusion power plants is central to the successful adoption of fusion energy. The advent of direct internal recycling in deuterium-tritium fusion fuel cycle design has led to significant reduction in startup tritium inventory estimates for fusion power plants but requires an isotope rebalancing and protium removal (IRPR) system to ensure acceptable isotopic fuel composition. Cryogenic distillation is a potential solution for near-term deployment in an IRPR system due to its demonstrated performance in similar operating regimes. Using protium removal in the fuel cycle as the primary performance metric, this paper presents an optimization methodology for a single-column continuous cryogenic distillation-based IRPR system for a 500 MW_fus magnetic fusion device. Distillation column optimization was performed using the CryOgenic Distillation For Isotopic Separation of Hydrogen (CODFISH) code developed at Savannah River National Laboratory. The distillation column design presented maximizes direct recycling of hydrogen isotopes from the fusion chamber exhaust to the fueling system while minimizing IRPR system steady-state tritium inventory. The optimized IRPR distillation column presented achieves direct recycling of 60 % of the hydrogen isotopes in the fusion chamber exhaust with an estimated steady-state system tritium inventory <30 g. The optimized IRPR distillation column operation was then used to estimate the design requirements for a detritation column to treat the IRPR system effluent stream.

减少核聚变发电厂的氚库存是成功采用核聚变能源的关键。氘-氚聚变燃料循环设计中直接内部循环的出现导致聚变发电厂启动氚库存估算显著降低，但需要同位素再平衡和除protium （IRPR）系统来确保可接受的同位素燃料组成。由于低温蒸馏在类似的操作系统中具有良好的性能，因此它是近期在IRPR系统中部署的潜在解决方案。以燃料循环中protium的去除为主要性能指标，提出了一种500 MWfus磁聚变装置单柱连续低温蒸馏IRPR系统的优化方法。精馏塔优化使用萨凡纳河国家实验室开发的氢同位素分离低温蒸馏（CODFISH）代码进行。精馏塔设计最大限度地从聚变室废气中直接回收氢同位素到燃料系统，同时最大限度地减少IRPR系统稳态氚库存。所提出的优化的IRPR精馏塔可以直接回收聚变室废气中60%的氢同位素，估计稳态系统氚库存为30 g。然后利用优化后的IRPR精馏塔操作来估计处理IRPR系统出水的精馏塔的设计要求。

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引用次数: 0

Fueling control system integration and control simulation for ITER start of research operation ITER研究运行启动燃料控制系统集成与控制仿真

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.2025.115580

D. Weldon , R. Nouailletas , P. Moreau , L. Zabeo , P.C. de Vries , T. Ravensbergen , L. Pangione , O. Kudlacek , T. Keenan , A. Sanchez-Mora

ITER's Start of Research Operation (SRO) operations target the generation of plasmas reaching ∼7.5 MA for durations exceeding 100 seconds. Effective control of fueling, density, impurity dosing, edge-localized modes (ELMs), and H-mode transitions is critical. To enable model-based design, the Gas Injection System (GIS) and Pellet Injection System (PIS) have been developed as models such that a complete fueling control system can be designed to address the complex requirements and challenges unique to ITER. These challenges involve lag-time due to lengthy gas lines, fueling efficiency decay at high plasma temperatures and densities, synchronization of multiple actuators, and balancing ELM pacing with fueling needs. An Actuator Manager (AM) coordinates the GIS and PIS operations to optimize performance.

The GIS and PIS models utilize 1-D particle transport models for the gas flow and diffusion through the pipe as well as the pellet transport through the Flight Tubes (FTs), which have been implemented within the Plasma Control System Simulation Platform (PCSSP). Furthermore, the particle deposition into the plasma as well as the plasma-neutral interactions are modeled through the RApid Plasma DENsity Simulator (RAPDENS). The results presented here demonstrate the successful integration of the GIS, PIS, AM, and RAPDENS for modeling the smooth transitions between fueling modes, and effective handling of actuator failures. This paper presents the architectural design, simulation results, and future strategies for optimizing fueling control during ITER's Augmented First Plasma operations.

ITER的开始研究操作（SRO）操作目标是产生持续超过100秒的等离子体，持续时间达到~ 7.5 MA。有效控制燃料、密度、杂质剂量、边缘局域模式（elm）和h模式转换是至关重要的。为了实现基于模型的设计，气体喷射系统（GIS）和颗粒喷射系统（PIS）已经被开发为模型，这样一个完整的燃料控制系统就可以设计出来，以解决ITER独特的复杂要求和挑战。这些挑战包括由于长输气管线造成的滞后、在高等离子体温度和密度下的燃料效率下降、多个致动器的同步，以及平衡ELM起搏器与燃料需求。执行器管理器（AM）协调GIS和PIS操作以优化性能。GIS和PIS模型利用一维粒子输运模型来模拟气体在管道中的流动和扩散，以及颗粒在飞行管（FTs）中的输运，这些模型已经在等离子体控制系统仿真平台（PCSSP）中实现。此外，通过快速等离子体密度模拟器（RAPDENS）模拟了粒子在等离子体中的沉积以及等离子体-中性相互作用。这里展示的结果表明，GIS、PIS、AM和RAPDENS的成功集成可以模拟加油模式之间的平稳过渡，并有效处理执行器故障。本文介绍了ITER增强型第一等离子体运行过程中的结构设计、仿真结果和优化燃料控制的未来策略。

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引用次数: 0