Annals of Nuclear Energy最新文献_第7页

Effects of coating layer thicknesses on the thermo-mechanical coupling behaviors of FCM fuels 涂层厚度对FCM燃料热-机械耦合行为的影响

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2026-01-03 DOI: 10.1016/j.anucene.2025.112104

Jing Zhang, Shurong Ding

FCM fuel, composed of TRISO particles and SiC matrix, is a typical accident tolerant fuel that holds a promising application prospect in various advanced nuclear reactors. Optimization of the microstructure of TRISO (Tri-Structural Isotropic) particles is crucial for enhancing both the safety and economy of nuclear fuel systems. In this study, the recently published novel fission gas swelling model or volume-growth strain models for the fuel kernel and the buffer layer are involved, enabling more accurate simulation of the irradiation thermo-mechanical coupling behaviors of FCM fuel. The three-dimensional mechanical constitutive relations, stress update algorithms and consistent stiffness moduli for the points within the buffer layer and PyC layer are newly formulated, and the corresponding procedures are developed. With the fuel kernel volume fraction and SiC layer dimensions kept constant, the effects of the thicknesses of the buffer layer, IPyC layer, and OPyC layer on the safety of FCM fuel are investigated. The research findings indicate that: (1) Increasing the buffer layer thickness can effectively improve its ability to accommodate kernel swelling, thereby markedly weakening the mechanical interactions between different parts; (2) With an increase of the buffer layer thickness from 50 µm to 80 µm, the peak first principal stresses in the SiC layer and the matrix decrease by 51 % and 79 %, respectively, leading to a significantly reduced failure risk; (3) A strategic redistribution of layer thicknesses can significantly strengthen the TRISO fuel safety, particularly by increasing the buffer layer thickness while decreasing both inner and outer dense PyC layer thicknesses, without altering other microstructural parameters. This study can provide theoretical guidance and analytical tools for the advanced manufacturing and optimization design of FCM fuel.

FCM燃料由三iso颗粒和SiC基体组成，是一种典型的耐事故燃料，在各种先进核反应堆中具有广阔的应用前景。优化三结构各向同性粒子的微观结构对提高核燃料系统的安全性和经济性至关重要。本研究采用了最近发表的新型裂变气体膨胀模型或燃料核和缓冲层的体积增长应变模型，可以更准确地模拟FCM燃料的辐照热-力学耦合行为。提出了缓冲层和PyC层内各点的三维力学本构关系、应力更新算法和一致刚度模量，并编制了相应的计算程序。在保持燃料核体积分数和SiC层尺寸不变的情况下，研究了缓冲层、IPyC层和OPyC层厚度对FCM燃料安全性的影响。研究结果表明：(1)增加缓冲层厚度可有效提高缓冲层对仁粒膨胀的容纳能力，从而显著减弱不同部位间的力学相互作用；(2)当缓冲层厚度从50µm增加到80µm时，SiC层和基体的第一主应力峰值分别降低了51%和79%，破坏风险显著降低；(3)在不改变其他微观结构参数的情况下，策略性地重新分配层厚度可以显著增强三iso燃料的安全性，特别是通过增加缓冲层厚度，同时减少内外致密PyC层厚度。该研究可为FCM燃料的先进制造和优化设计提供理论指导和分析工具。

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引用次数: 0

Research on the characteristics of interfacial area transport and flow resistance for upward two-phase flow in a 5 × 5 rod bundle 5 × 5杆束上向两相流界面输运特性及流动阻力研究

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2026-01-03 DOI: 10.1016/j.anucene.2025.112101

Jiaxing Ren , Quanbo Li , Gongyao Liu , Weiqiang Xu , Ruifeng Tian , Puzhen Gao , Shouxu Qiao , Sichao Tan

Due to the complex effects of advection, pressure drop, and bubble interactions, the two-phase flow parameters change dynamically with flow development. This paper conducted an experimental study on air–water two-phase flow in a 5 × 5 rod bundle using a four-sensor conductivity probe and differential pressure transducers. An interfacial area parameter database containing over 5000 measurement points is established from the entire cross-sectional measurement at five axial positions. The enhanced bubble coalescence efficiency due to the geometry of subchannels results in an increasing trend of bubble velocity and a decreasing trend of interfacial area concentration. Cap-bubbly flows are found to have larger relative velocities than bubbly flows through the one-dimensional drift-flux analysis. The two-phase frictional pressure drop is calculated by the measured void fraction with the probe and used to evaluate the existing prediction models. The coupling relationship between the void fraction and pressure drop is also analyzed through operating flow parameters.

由于平流、压降和气泡相互作用的复杂影响，两相流参数随流动的发展而动态变化。利用四传感器电导率探头和差压传感器对5 × 5棒束中空气-水两相流动进行了实验研究。从五个轴向位置的整个截面测量中建立了包含5000多个测点的界面面积参数数据库。子通道的几何形状提高了气泡的聚结效率，导致气泡速度增大，界面面积浓度减小。通过一维漂移通量分析，发现帽状气泡流比气泡流具有更大的相对速度。利用探针测量的空隙率计算两相摩擦压降，并用于评估现有的预测模型。通过运行流量参数分析了空隙率与压降之间的耦合关系。

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引用次数: 0

Computer vision-based detection and dynamic tracking of multiple micro bubbles in transparent liquid similarity experiments for SGTR in lead-cooled fast reactor 铅冷快堆SGTR透明液体相似实验中多微气泡的计算机视觉检测与动态跟踪

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2026-01-02 DOI: 10.1016/j.anucene.2025.112100

Ying Guan , Yang Li , Hualei Jiang , Daqing Wang , Daochuan Ge , Huaping Mei , Gui Fang , Lifu Gao , Haixia Wang

Bubble migration during a steam generator tube rupture (SGTR) accident in lead-cooled fast reactor (LFR) has garnered significant attention. This phenomenon can cause localized heat transfer deterioration and power fluctuations, posing substantial safety risks to the reactor. This paper presents a novel detection approach integrated with dynamic tracking for multiple micro bubbles, specifically designed for transparent liquid similarity experiments in SGTR research. The proposed method, named DAM-YOLO, incorporates dual attention mechanisms, a lightweight upsampling operator, and content-aware reassembly of features to enhance feature extraction capability and feature fusion performance for micro bubbles. Furthermore, by adopting the DeepSORT algorithm combined with the complete intersection over union (CIoU) matching metric, the issue of multiple target loss during tracking process is effectively addressed. In this study, bubble datasets were acquired from a self-developed similarity experimental facility. The results demonstrate that the precision (P), mean average precision (mAP), multiple object tracking accuracy (MOTA), multiple object tracking precision (MOTP), and id f1 score (IDF1) of the proposed model reach 96.4%, 95.6%, 85.27%, 86.99%, and 92.63%, respectively. This research can provide efficient intelligent technical support for analyzing the migration process of multiple micro bubbles in fluid dynamics studies.

铅冷快堆蒸汽发生器管破裂（SGTR）事故中的气泡迁移引起了人们的广泛关注。这种现象会引起局部传热恶化和功率波动，对反应堆构成重大安全风险。针对SGTR研究中的透明液体相似实验，提出了一种结合动态跟踪的多微气泡检测方法。该方法结合了双注意机制、轻量级上采样算子和内容感知特征重组，增强了微气泡的特征提取能力和特征融合性能。此外，采用DeepSORT算法结合CIoU匹配度量，有效解决了跟踪过程中多目标丢失的问题。在本研究中，气泡数据集是从自主开发的相似性实验设备中获得的。结果表明，该模型的精度(P)、平均精度（mAP）、多目标跟踪精度（MOTA）、多目标跟踪精度（MOTP）和id f1得分（IDF1）分别达到96.4%、95.6%、85.27%、86.99%和92.63%。该研究可为流体力学研究中分析多微泡运移过程提供高效的智能技术支持。

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引用次数: 0

A development of a new slightly moderated reference field in graphite insertion in the LR-0 reactor 在LR-0反应堆中石墨插入一个新的微慢化参考场的发展

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2026-01-02 DOI: 10.1016/j.anucene.2025.112106

Tomáš Peltan , Tomáš Czakoj , Vlastimil Juříček , Jan Šimon , Michal Košťál

This study of a slightly moderated neutron reference field shaped by graphite has been established at the LR-0 reactor. This experimental configuration modifies the reference neutron spectrum toward lower energies while preserving spatial homogeneity using graphite. This core configuration was characterized through an extensive neutron flux mapping by four independent irradiation campaigns utilizing activation foil detectors. High-purity and well-known dosimetry reactions using activation foils of Au, Cu, Mn, Ta, and Ni were strategically positioned throughout the graphite insertion for neutron shape mapping. The resulting reaction rates were derived from gamma spectrometry using a well-defined HPGe detector. The measured data provide detailed spatial and spectral information on the neutron flux distribution and confirm the reproducibility and stability of the investigated volume in the graphite field, which can be validated as a new neutron reference field. This field can be used to research in advanced reactor systems and IV. gen reactors.

在LR-0反应堆上建立了石墨形成的微慢化中子参考场的研究。这种实验配置修改了参考中子能谱向较低的能量，同时保持空间均匀性使用石墨。通过利用激活箔探测器的四个独立辐照活动进行广泛的中子通量映射来表征该核心配置。利用Au， Cu, Mn， Ta和Ni的活化箔进行高纯度和众所周知的剂量测定反应，这些反应战略性地定位在整个中子形状映射的石墨插入中。所得的反应速率由伽马能谱法推导，使用定义良好的HPGe探测器。测量数据提供了中子通量分布的详细空间和光谱信息，证实了所研究体积在石墨场中的再现性和稳定性，可作为新的中子参考场。该领域可用于先进反应堆系统和四代反应堆的研究。

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引用次数: 0

Research on fault diagnosis method for nuclear power plants based on crossformer-SVM 基于交叉变形-支持向量机的核电厂故障诊断方法研究

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2025-12-31 DOI: 10.1016/j.anucene.2025.112109

Ji Liu , Yongkuo Liu , Zhouxin Shi , Jiarong Gao , Yukun Liu , Zhen Wang , Guohua Wu

Due to the unique nature of nuclear power plants, highly reliable fault diagnosis methods are required to ensure operational safety and stability. To fully capture the spatiotemporal dependencies in multivariate time series (MTS) data and improve the accuracy of fault diagnosis in nuclear power plant systems, this paper proposes a hybrid diagnostic framework integrating Crossformer and Support Vector Machine (SVM), referred to as the Crossformer-SVM model. First, using the PCTRAN simulation platform and the Fuqing simulation machine as data sources, fault datasets with noise and without noise are constructed. Then, the Crossformer model is employed to hierarchically extract the spatiotemporal features of the system fault data, which are used as inputs for the SVM classifier. Finally, the SVM classifier is used to identify the fault modes of the system. In addition, a comparative experiment is conducted between the proposed Crossformer-SVM model and other deep learning models, such as CNN-LSTM. The experimental results show that, compared to other deep learning fault diagnosis models, the proposed method achieves the highest accuracy, with a minimum accuracy of 99.20% for the two types of noise-free datasets. It also maintains excellent diagnostic performance under noise, with diagnostic accuracies of 98.92% and 98.88% for the Fuqing simulator and PCTRAN data, respectively. This provides a reliable fault diagnosis method for nuclear power plant systems.

由于核电站的特殊性，需要高可靠性的故障诊断方法来保证运行的安全性和稳定性。为了充分捕捉多变量时间序列（MTS）数据的时空相关性，提高核电站系统故障诊断的准确性，本文提出了一种融合了Crossformer和支持向量机（SVM）的混合诊断框架，简称Crossformer-SVM模型。首先，以PCTRAN仿真平台和福清仿真机为数据源，分别构建了带噪声和无噪声故障数据集；然后，利用Crossformer模型分层提取系统故障数据的时空特征，作为支持向量机分类器的输入；最后，利用支持向量机分类器对系统的故障模式进行识别。此外，还将本文提出的crossform - svm模型与CNN-LSTM等其他深度学习模型进行了对比实验。实验结果表明，与其他深度学习故障诊断模型相比，本文提出的方法在两类无噪声数据集上达到了最高的准确率，最低准确率为99.20%。该方法在噪声下也保持了良好的诊断性能，对福清模拟器和PCTRAN数据的诊断准确率分别为98.92%和98.88%。这为核电厂系统提供了可靠的故障诊断方法。

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引用次数: 0

Effects of two-dimensional hills combination with distance variation on the aerosols dispersion based on wind tunnel experiment 基于风洞试验的二维山丘组合与距离变化对气溶胶扩散的影响

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2025-12-31 DOI: 10.1016/j.anucene.2025.112088

Siyuan Wu, Jinpeng He, Weiguo Gu, Deyi Chen, Baojie Nie, Dezhong Wang

The dispersion uplift of the aerosol plume due to the complex mountain subsurface and the residence of the plume in the clockwise turnaround flow behind the hill are still a major obstacle in accurately predicting the dispersion concentration distributions of aerosols in the atmospheric emissions from nuclear power plants, despite the use of complex numerical models. In particular, the effect of hill combination on dispersion trajectories and concentration distributions has not received widely attention in previous experimental studies. The focus of this study is on the effect of the distance between two identical parallel aligned hills on the dispersion trajectory and concentration distribution of the aerosol plume under neutral atmospheric conditions. A combination of planar particle laser concentration measurement method and CFD simulation was used to characterize the flow reattachment and plume trajectories as well as the dispersion distribution. The results show that when the interval between the two hills is less than

4 H

, the total reattachment length remains at

9 H

as in the case of a single hill, and the dispersion trajectory is basically consistent with that of a single hill. The concentration accumulates on the windward side of the second hill between valleys. When the distance between the two hills is greater than

12 H

, the reattachment length of the first hill recovers to

9 H

as in the case of a single hill, and the second hill begins to move away from the influence area of the first hill.

尽管采用了复杂的数值模型，但由于复杂的山地地下造成的气溶胶羽流弥散抬升和羽流在山后顺时针旋转流中的停留仍然是准确预测核电站大气排放中气溶胶弥散浓度分布的主要障碍。特别是山丘组合对色散轨迹和浓度分布的影响在以往的实验研究中没有得到广泛的关注。本研究的重点是在中性大气条件下，两个相同的平行排列山丘之间的距离对气溶胶羽流扩散轨迹和浓度分布的影响。采用平面粒子激光浓度测量方法和CFD模拟相结合的方法，对流动再附着和羽流轨迹以及弥散分布进行了表征。结果表明：当两个山丘之间的间隔小于4H时，总再附着长度与单山丘时保持在9H，且色散轨迹与单山丘时基本一致；浓度集中在山谷间第二座山的迎风面。当两个山丘之间的距离大于12H时，第一个山丘的再附着长度恢复到单个山丘时的9H，第二个山丘开始远离第一个山丘的影响区域。

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引用次数: 0

Thermomechanics coupling to Monte Carlo particle transport on unstructured mesh geometries using Cardinal 热力学耦合到蒙特卡罗粒子输运在非结构网格几何使用基数

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2025-12-31 DOI: 10.1016/j.anucene.2025.112068

Mahmoud Eltawila , Pierre-Clément A. Simon , Guillaume L. Giudicelli , Helen Brooks , Nicholas Wozniak , April J. Novak

Geometry deformation due to thermal expansion influences neutron transport in many systems. Studying this phenomenon involves coupling models for neutronics, thermal hydraulics, and solid mechanics. To enable high fidelity modeling of these coupled physics, new capabilities were introduced in Cardinal, coupling OpenMC Monte Carlo particle transport models with MOOSE thermomechanical physics on unstructured moving-mesh geometries. In this work, we present a fully open-source capability leveraging on-the-fly mesh skinning to automatically regenerate OpenMC geometry, which allows multiphysics feedback from temperature, density, and geometry changes. The new capability is verified using an analytic benchmark slab problem, which couples S

_{2}

neutron transport with thermal conduction, convective boundary conditions, Doppler-broadened cross sections, and nonlinear thermal expansion effects along the heated slab. Cardinal reproduces the analytic solutions for the neutron flux, heating, k

_{eff}

, and temperature with demonstrated convergence in various error terms including mesh resolution and cross section temperature library spacing. For the nominal benchmark conditions and with a fine mesh, maximum relative errors for neutron flux, temperature, and heating are lower than 1%, while errors in integral quantities such as

k_{eff}

and slab length are within 1 pcm and 48 µm, respectively. This work (i) presents a new numerical approach to thermomechanics coupling with OpenMC models, (ii) is the first (to our knowledge) to utilize a mechanical partial differential equation (PDE) solution to solve the (Griesheimer and Kooreman, 2022) analytic benchmark, and (iii) develops this verified capability within an open-source package.

在许多系统中，热膨胀引起的几何变形影响中子输运。研究这种现象涉及到中子学、热工水力学和固体力学的耦合模型。为了实现这些耦合物理的高保真建模，Cardinal引入了新的功能，将OpenMC蒙特卡罗粒子输运模型与MOOSE热机械物理在非结构化移动网格几何上耦合。在这项工作中，我们提出了一个完全开源的功能，利用实时网格蒙皮来自动重新生成OpenMC几何形状，它允许来自温度、密度和几何形状变化的多物理场反馈。利用一个解析基准板问题验证了这一新能力，该问题将S2中子输运与热传导、对流边界条件、多普勒展宽截面和沿加热板的非线性热膨胀效应耦合在一起。Cardinal再现了中子通量、加热、keff和温度的解析解，并在各种误差项（包括网格分辨率和截面温度库间距）中展示了收敛性。在标称基准条件和细网格条件下，中子通量、温度和加热的最大相对误差小于1%，而keff和slab长度等积分量的误差分别在1 pcm和48µm以内。这项工作(i)提出了一种新的数值方法来与OpenMC模型耦合热力学，（ii）是第一个（据我们所知）利用机械偏微分方程（PDE）解决方案来解决（Griesheimer和Kooreman， 2022）分析基准，（iii）在一个开源包中开发了这种验证能力。

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引用次数: 0

Vibration analysis of large equipment with Non-Uniform mass under road transportation 大型非均匀质量设备公路运输振动分析

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2025-12-31 DOI: 10.1016/j.anucene.2025.112102

Tiandi Fan , Huajie Wu , Changzheng Chen , Xianming Sun , lipeng Wang

During the transportation of large-scale equipment, road excitation can trigger resonance, potentially impairing the structural stability of the vehicle system. Moreover, due to its special structure and non-uniform mass distribution—such as reactor pool mass concentration from high-density Lead-Bismuth Eutectic (LBE) coolant—transportation vibration response and stability have become urgent key technical issues. Besides, liquid LBE coolant may slosh during transportation, requiring stricter stability rules. However, current research focuses more on anti-vibration design or isolation, with few studies on the equipment’s vibration. To solve this problem, this study uses Lagrange’s differential equations to create a new separated vibration model. It explains how mobile LBE reactors respond to vibration, and analyzes vibration responses under different road classes, driving speeds, and loading masses. This study confirms the developed separated model’s ability to capture on-board equipment and vehicle body vibration responses, offering references for large equipment transportation safety and insights for mobile LBE reactor design.

在大型设备的运输过程中，道路激励会引发共振，可能会损害车辆系统的结构稳定性。此外，由于其特殊的结构和不均匀的质量分布，如高密度铅铋共晶（LBE）冷却液的堆池质量浓度，输送振动响应和稳定性已成为迫切需要解决的关键技术问题。此外，液态LBE冷却剂在运输过程中可能会晃动，需要更严格的稳定性规则。但目前的研究多集中在设备的抗振设计或隔振上，对设备的振动研究较少。为了解决这一问题，本研究利用拉格朗日微分方程建立了一个新的分离振动模型。介绍了移动LBE电抗器对振动的响应，并分析了不同道路等级、行驶速度和装载质量下的振动响应。该研究证实了所开发的分离模型能够捕获车载设备和车身振动响应，为大型设备运输安全提供参考，并为移动LBE反应堆设计提供见解。

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引用次数: 0

Radiological shielding performance for offsite emergency center near research reactor 研究堆旁应急中心的辐射屏蔽性能

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2025-12-30 DOI: 10.1016/j.anucene.2025.112108

Arya Pramana Sembiring , Juyoul Kim

Gerrit Agustinus Siwabessy Multi-Purpose Reactor (RSG-GAS) is Indonesia’s largest research reactor. This research reactor needs radiation risk mitigation in a densely populated area. This study examines the radiation shielding effectiveness of Building No. 93 as an offsite emergency center during a Beyond Design-Basis Accident (BDBA). An Anticipated Transient Without Scram (ATWS) scenario with five fuel element meltdowns was simulated using HotSpot, a Gaussian plume-based atmospheric dispersion software, and dose attenuation was performed using Monte Carlo. The result shows that the dual-layered concrete wall can reduce the incoming total dose rate to 0.558 mSv/hour, allowing safe occupancy for 3.74 days before reaching Indonesia’s emergency dose limit of 50 mSv for workers and the public. This study confirms that Building No. 93 meets regulatory standards and is suitable as an offsite emergency center for emergency operators during severe nuclear incidents. This study established a framework for future emergency evaluation and management strategy.

Gerrit Agustinus Siwabessy多用途反应堆（RSG-GAS）是印度尼西亚最大的研究反应堆。这个研究反应堆需要在人口密集的地区降低辐射风险。本研究考察了93号楼作为非现场应急中心在超设计基础事故（BDBA）中的辐射屏蔽效能。使用基于高斯羽流的大气扩散软件HotSpot模拟了5个燃料元件熔毁的预期瞬态无Scram （ATWS）情景，并使用蒙特卡罗进行了剂量衰减。结果表明，双层混凝土墙可将入射总剂量率降低至0.558毫西弗/小时，在达到印度尼西亚对工作人员和公众50毫西弗的紧急剂量限值之前，允许安全居住3.74天。本研究证实93号楼符合规范标准，适合作为严重核事故应急操作人员的场外应急中心。本研究为未来的应急评估和管理策略建立了框架。

引用次数: 0

An open source multiphysics workflow for the analysis of subcritical transmutation systems 用于分析亚临界嬗变系统的开源多物理场工作流

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy

Pub Date : 2025-12-30 DOI: 10.1016/j.anucene.2025.112072

Matthew Nyberg , Joseph Eickman , Una Baker , Patrick Shriwise , Ben Lindley

Two challenges were identified in modeling externally driven systems (EDS) for transuranic (TRU) burning with existing workflows: complex, spatially varying sources and flexible open-source production of cross-sections. A workflow is presented coupling the source and multi-group cross-section generation within OpenMC to the GeN-Foam multiphysics solver. First, OpenMC generated nuclear data was exported for transuranic-based molten salt reactor GeN-Foam model, and neutronics characteristics were verified against an equivalent OpenMC model. This TRU-based fueled salt was compared to uranium-thorium molten salt at steady state and over a range of potential accident scenarios. Secondly, a method utilizing the OpenMC C++ API sampled a fusion source onto a mesh used within GeN-Foam simulations, enabling closely coupled EDS multiphysics analysis. This spatially accurate source definition was verified against OpenMC models, and then was demonstrated for transient scenarios. This workflow enables closely coupled multiphysics analysis of complex critical or subcritical systems using open-source tools.

在利用现有工作流程为超铀（TRU）燃烧建模外部驱动系统（EDS）时，确定了两个挑战：复杂的、空间变化的来源和灵活的开源截面生产。提出了将OpenMC中的源和多组截面生成与GeN-Foam多物理场求解器相耦合的工作流程。首先，导出OpenMC生成的超铀熔盐堆GeN-Foam模型的核数据，并与等效OpenMC模型进行中子特性验证。在稳定状态和一系列潜在事故情景下，将这种基于trur的燃料盐与铀钍熔盐进行了比较。其次，利用OpenMC c++ API将融合源采样到GeN-Foam模拟中使用的网格上，从而实现紧密耦合的EDS多物理场分析。在OpenMC模型中验证了这种空间精确的源定义，然后在瞬态场景中进行了演示。该工作流可以使用开源工具对复杂的关键或次关键系统进行紧密耦合的多物理场分析。

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引用次数: 0