Nuclear Engineering and Technology最新文献

Physical design of the 1.5 GeV LINAC injector for the WALS facility 用于WALS设施的1.5 GeV LINAC注入器的物理设计

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-15 DOI: 10.1016/j.net.2025.104086

Zeyi Dai , Jia Li , Pengwei Huang , Chaofan An , Yongjin Ding , Dengshi Shi , Hongwei Yue , Yuxin Zhang , Xinwu Yu , Xuyang Qiao , Lianmin Zheng , Yuancun Nie

The Wuhan Advanced Light Source (WALS) is a high-brightness fourth-generation synchrotron radiation light source designed to generate high-quality X-ray beams using a top-up linear accelerator (LINAC) as an injector. The LINAC will provide electron beams for a low-energy storage ring (1.5 GeV), a medium-energy storage ring (4 GeV), and a free-electron laser (FEL). In the first phase, a low-energy diffraction-limited storage ring (DLSR) operating at 1.5 GeV is proposed. To meet the high current requirements for the DLSR and low beam emittance for the FEL, a photoinjector-based top-up LINAC is identified as the optimal solution. This study employs a multi-objective optimization algorithm to improve the photoinjector's performance and uses a laser pulse delay scheme validated on the TTX platform at Tsinghua University to achieve a pulse train structure with a single bunch charge of 1 nC and a time gap between micro-bunches of 2.1 ns. Beam optimization simulations for the 1.5 GeV LINAC at a bunch charge of 1 nC yield an RMS energy spread below 0.1 %, and normalized emittances of 1.64 mm·mrad (horizontal) and 0.97 mm·mrad (vertical). These results demonstrate the feasibility of the LINAC system to simultaneously provide high-quality beams for both the DLSRs and the FELs.

武汉先进光源（WALS）是一种高亮度第四代同步辐射光源，设计用于使用充值直线加速器（LINAC）作为注入器产生高质量的x射线光束。LINAC将为低能量存储环（1.5 GeV）、中等能量存储环（4 GeV）和自由电子激光器（FEL）提供电子束。在第一阶段，提出了一种工作在1.5 GeV的低能衍射限制存储环（DLSR）。为了满足DLSR的高电流要求和FEL的低光束发射度要求，确定了基于光注入器的补强LINAC是最优方案。本研究采用多目标优化算法来提高光注入器的性能，并采用经过清华大学TTX平台验证的激光脉冲延迟方案，实现了单束电荷为1nc、微束间时间间隔为2.1 ns的脉冲串结构。对1.5 GeV LINAC在束荷为1 nC时进行的波束优化模拟结果显示，均方根能量分布小于0.1%，标准化发射率为1.64 mm·mrad（水平）和0.97 mm·mrad（垂直）。这些结果证明了LINAC系统同时为DLSRs和FELs提供高质量光束的可行性。

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引用次数: 0

The random ray method for challenging deep-penetration shielding problems: A rigorous comparison with multigroup Monte Carlo 挑战深穿透屏蔽问题的随机射线方法：与多群蒙特卡罗的严格比较

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-14 DOI: 10.1016/j.net.2025.104083

Shuai Qin, Jiacheng Li, Shihong Li, Xiangchun Tian, Qian Zhang

Deep-penetration radiation shielding problems present a significant computational challenge for the standard Monte Carlo (MC) method due to statistical inefficiency in low-flux regions. As a robust alternative, this study investigates The Random Ray Method (TRRM), which is founded on deterministic transport along randomly and uniformly sampled rays. A rigorous comparison between TRRM and the Multigroup Monte Carlo (MGMC) method was conducted by implementing both within a unified computational framework. Performance was assessed using two challenging shielding benchmarks—the three-dimensional Wagner model with thick shielding and a two-dimensional shielding facility with multi-bend maze—under four physics configurations that combines multigroup (47-group) and one-group energy treatments with isotropic and anisotropic scattering. The results show that while both methods agree in high-flux regions, MGMC performance degrades significantly as normalized flux has attenuated by 6–7 orders of magnitude, whereas TRRM remains statistically robust. Consequently, TRRM is several orders of magnitude more efficient in these deep-penetration regions, with its Figure of Merit (FOM) exceeding MGMC's by factors of over 10⁴. Critically, the study reveals that the computational advantage of TRRM is substantially amplified in the most physically realistic scenarios (multigroup with anisotropic scattering). Although these complexities increase TRRM's per-ray computational cost, the significant variance reduction from its global sampling strategy overwhelmingly compensates for it. These findings establish TRRM as a highly efficient deterministic alternative for high-fidelity shielding analyses.

由于低通量区域的统计效率低下，深穿透辐射屏蔽问题对标准蒙特卡罗（MC）方法提出了重大的计算挑战。作为一种可靠的替代方法，本研究研究了随机射线法（TRRM），该方法基于随机和均匀采样射线的确定性传输。通过在统一的计算框架内实现TRRM和多群蒙特卡罗（MGMC）方法，对两者进行了严格的比较。使用两个具有挑战性的屏蔽基准-具有厚屏蔽的三维Wagner模型和具有多弯曲迷宫的二维屏蔽设施-在四种物理配置下，将多群（47群）和单群能量处理与各向同性和各向异性散射相结合，对性能进行了评估。结果表明，虽然两种方法在高通量区域一致，但当归一化通量衰减6-7个数量级时，MGMC的性能显著下降，而TRRM在统计上保持稳健。因此，TRRM在这些深穿透区域的效率要高几个数量级，其优点系数（FOM）超过MGMC的104倍以上。至关重要的是，该研究表明，TRRM的计算优势在最实际的物理情况下（具有各向异性散射的多群）被大大放大。尽管这些复杂性增加了TRRM的每条射线计算成本，但其全局采样策略的显著方差减少压倒性地弥补了这一点。这些发现确立了TRRM作为高保真屏蔽分析的高效确定性替代方案。

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引用次数: 0

Integrated modeling of improving core confinement with ECW based on HL-3 hybrid scenario 基于HL-3混合场景的ECW改进堆芯约束集成建模

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-13 DOI: 10.1016/j.net.2025.104082

Peng Yu , Qianhong Huang , Xinlin Wang , Yijun Zhong , Qingyi Tan , Jun Wang , Zhe Wang , Zhanhui Wang

The control of safety factor profile helps to reduce turbulent transport and improve core confinement. Based on HL-3 device parameters, this study employs METIS to investigate control laws of safety factor profile through adjustments of ECW power peak deposition position, deposition width, ramp-up rate, ramp-up time, and plasma effective charge number, while analyzing their impacts on core confinement performance in hybrid scenarios. By appropriately adjusting the power deposition position and width of ECW, as well as regulating its power ramp-up time, safety factor profile can be maintained with characteristics of zero magnetic shear hybrid scenario. At the same time, transport barrier will form in the dynamic profiles, the transport coefficient will reduce, plasma parameters and core confinement will improve significantly. Moreover, the effect of ECW on the improvement of core confinement in the plasma current ramp-up phase is studied.

安全系数剖面的控制有助于减少湍流输运和改善堆芯约束。本研究以HL-3器件参数为基础，通过调整ECW功率峰值沉积位置、沉积宽度、爬坡速率、爬坡时间和等离子体有效电荷数，利用METIS研究安全系数分布的控制规律，并分析其对混合工况下堆芯约束性能的影响。通过适当调整ECW的功率沉积位置和宽度，以及调节ECW的功率爬坡时间，可以保持安全系数曲线的零磁剪切混合特性。同时，在动力学剖面中形成输运屏障，输运系数降低，等离子体参数和堆芯约束显著提高。此外，还研究了电子束对等离子体电流上升阶段磁芯约束改善的影响。

引用次数: 0

Neutronic performance analysis of U–Mn fuel and MgO-BeO tube material in the dual fluid reactor U-Mn燃料和MgO-BeO管材料在双流体反应堆中的中子性能分析

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-12 DOI: 10.1016/j.net.2025.104079

Semra Daydas, Ali Tiftikci

This study investigates the feasibility of using a Uranium–Manganese (U–Mn) alloy as an alternative fuel for the Dual Fluid Reactor (DFR_m) concept to increase the temperature margin, along with a Magnesium Oxide–Beryllium Oxide (MgO–BeO) ceramic fuel tube. Neutronic analyses were performed using the SERPENT 1.1.7 Monte Carlo code with the ENDF/B-VII cross-section library to evaluate fuel performance, reactivity behavior, and safety margins. The results indicate that the U–Mn fuel exhibits lower

k_{e f f}

values and shorter fuel cycle length to those of the U–Cr fuel, while providing the advantage of a lower eutectic temperature. Reactivity coefficients found to be negative for both fuel and coolant with the SiC fuel tube, ensuring inherent safety during temperature excursions. However, for the MgO–BeO configuration, the reactivity coefficients for MgO-BeO were found to be positive, which represents a critical drawback of this material; hence, further geometrical optimization is required. Consequently, although U–Mn fuel maintains negative temperature feedback under SiC-based configurations, alternative tube materials such as MgO–BeO require further optimization to ensure stable and inherently safe reactivity behavior throughout the fuel cycle. Future research could focus on optimizing reactor geometry to enhance the utilization potential of U–Mn fuel.

本研究探讨了使用铀-锰（U-Mn）合金作为双流体反应堆（DFRm）概念的替代燃料的可行性，以提高温度裕度，同时使用氧化镁-氧化铍（MgO-BeO）陶瓷燃料管。中子分析使用SERPENT 1.1.7 Monte Carlo代码和ENDF/B-VII截面库进行，以评估燃料性能、反应性行为和安全裕度。结果表明，与U-Cr燃料相比，U-Mn燃料具有更低的keff值和更短的燃料循环长度，同时具有更低的共晶温度。使用碳化硅燃料管的燃料和冷却剂的反应性系数均为负，确保了温度漂移时的固有安全性。然而，对于MgO-BeO结构，MgO-BeO的反应性系数被发现是正的，这代表了这种材料的一个关键缺点；因此，需要进一步的几何优化。因此，尽管U-Mn燃料在基于sic的配置下保持负温度反馈，但替代管材料（如MgO-BeO）需要进一步优化，以确保整个燃料循环过程中稳定和固有安全的反应性行为。未来的研究重点应放在优化反应堆结构上，以提高铀锰燃料的利用潜力。

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引用次数: 0

Nano-to-micro aerosol contaminants emissions from dismantling of nuclear reactor pressure vessel using mock-up experiments 核反应堆压力容器拆解过程中纳米至微气溶胶污染物排放的模拟实验

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-11 DOI: 10.1016/j.net.2025.104081

Wonseok Yang , Joonsoo Ock , Kwangseo Kim , Samuel Park , Nakkyu Chae , Haewoong Kim , Kwangsoo Park , Min-Ho Lee , Sungyeol Choi

The decommissioning of nuclear power plants presents significant challenges due to the release of radioactive aerosols from contaminated or activated metal cutting, posing risks of internal radiation exposure. To protect workers, it is crucial to characterize aerosol generation and verify the performance of air purification systems. Although previous studies relied on lab-scale experiments, full-scale mock-up testing is necessary to validate under field conditions. This study conducted remote oxy-fuel cutting experiments on a mock-up reactor pressure vessel (RPV) to evaluate aerosol characteristics and filtration efficiency. The mock-up, simulating the upper shell of the Kori Unit 1 RPV, was enclosed within a shielding tent connected to a ventilation system. During thermal cutting, we confirmed a bimodal size distribution, with nanoparticles (<100 nm) comprising a significant fraction. Chemical analysis identified that aerosol contained the key elements of RPV materials such as iron, chromium, nickel, and manganese. Filtration efficiency of mock-up system exceeded 99.87 % for particles under 10 μm. However, the dose conversion factors for inhalation calculated from experimental data were up to 4.71 times higher than the ICRP-recommended values. These findings emphasize the importance of precise aerosol monitoring and respiratory protective equipment to enhance safety protocols in nuclear decommissioning.

由于受污染或活化的金属切割释放放射性气溶胶，造成内部辐射暴露的风险，核电厂的退役提出了重大挑战。为了保护工人，至关重要的是表征气溶胶的产生和验证空气净化系统的性能。虽然以前的研究依赖于实验室规模的实验，但在现场条件下进行全尺寸模型测试是必要的。本研究在模拟反应堆压力容器（RPV）上进行了远程氧燃料切割实验，以评估气溶胶特性和过滤效率。该模型模拟了Kori 1号机组RPV的上部外壳，被封闭在一个与通风系统相连的屏蔽帐篷内。在热切割过程中，我们证实了一个双峰尺寸分布，纳米颗粒（<100 nm）占很大比例。化学分析表明，气溶胶含有RPV材料的关键元素，如铁、铬、镍和锰。模拟系统对10 μm以下颗粒的过滤效率超过99.87%。然而，根据实验数据计算的吸入剂量转换系数比icrp推荐值高出4.71倍。这些发现强调了精确的气溶胶监测和呼吸防护设备对加强核退役安全协议的重要性。

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引用次数: 0

GPU-based high-speed reactor signal generator for Ex-core neutron flux monitoring system validation 基于gpu的高速反应堆信号发生器用于前堆中子通量监测系统验证

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-11 DOI: 10.1016/j.net.2025.104078

Yujin Eom , Geon Shin , Heehun Yang , Soyeon Choi , Hyeongseok Eun , Joon-Ku Lee , Hoyoung Yoo

This paper proposes a GPU-based high-speed signal generation algorithm for effectively simulating the operational environment of the Ex-Core Neutron Flux Monitoring System (ENFMS), which is essential for advanced reactor systems such as Small Modular Reactors (SMRs). Accurate and rapid modeling of neutron, gamma-ray, and electrical noise signals is essential for reliable nuclear fuel monitoring and early anomaly detection. Although conventional CPU-based sequential simulation methods provide precise results, they become impractical under high reactor power conditions or extended simulation durations due to excessive computational demands. To resolve these limitations, we developed a parallel computing framework optimized for high-performance task distribution between CPU and GPU resources. Experimental results demonstrate that the proposed GPU-based implementation reduces elapsed times by up to 99.57 %, 99.43 %, and 98.54 % compared to CPU implementations using MATLAB, Python, and C, respectively. Therefore, the proposed GPU-based parallel algorithm significantly enhances feasibility of realistic and efficient ENFMS simulations, contributing to accelerated development and validation of digital and compact SMR systems.

本文提出了一种基于gpu的高速信号生成算法，用于有效模拟小型模块化反应堆等先进反应堆系统的前堆中子通量监测系统（ENFMS）的运行环境。中子、伽马射线和电气噪声信号的准确和快速建模对于可靠的核燃料监测和早期异常检测至关重要。尽管传统的基于cpu的顺序模拟方法提供了精确的结果，但由于计算量过大，它们在高反应堆功率条件下或延长的模拟持续时间下变得不切实际。为了解决这些限制，我们开发了一个并行计算框架，优化了CPU和GPU资源之间的高性能任务分配。实验结果表明，与使用MATLAB、Python和C语言的CPU实现相比，基于gpu的实现分别减少了99.57%、99.43%和98.54%的运行时间。因此，所提出的基于gpu的并行算法显著提高了真实高效的ENFMS仿真的可行性，有助于加速数字化和紧凑型SMR系统的开发和验证。

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引用次数: 0

Simulation of a time and spatial sensitive plastic scintillator detector 时间和空间敏感塑料闪烁体探测器的仿真

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-11 DOI: 10.1016/j.net.2025.104080

Shuaike Lv , Changsheng Dai , Dongdong Hu , Tiancheng Zhong , Weifeng Wu , Xinjian Wang

Muon tomography is a promising technique for the detection and imaging of high-Z materials. A detector with excellent timing and spatial resolution can significantly improve imaging accuracy. In this study, we propose a scintillation detector design based on a SiPM array readout and conduct detailed simulations to investigate its timing and spatial performances. Preliminary results indicate that the detector can achieve a time resolution better than 30 ps and a spatial resolution of approximately 1.5 mm. This design offers a compact, single-detector solution with high performance, which has great potential to simplify muon scattering tomography systems and further enhance image effect.

介子层析成像是一种很有前途的高z材料探测和成像技术。具有良好时序和空间分辨率的探测器可以显著提高成像精度。在这项研究中，我们提出了一种基于SiPM阵列读出的闪烁探测器设计，并进行了详细的仿真研究其时序和空间性能。初步结果表明，该探测器的时间分辨率优于30 ps，空间分辨率约为1.5 mm。该设计提供了一种紧凑、高性能的单探测器解决方案，在简化μ子散射断层成像系统和进一步增强图像效果方面具有很大的潜力。

引用次数: 0

Anticipating radioactive waste: A forecast for the Philippines' upcoming nuclear energy 预测放射性废物：对菲律宾即将到来的核能的预测

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-11 DOI: 10.1016/j.net.2025.104076

John Wilkin F. Lim , Ray Matthew A. Bunquin , Angelo A. Panlaqui , Ronald E. Piquero

This study forecasts annual radioactive waste arisings for a Philippine baseline deployment of a ∼1200 MWe light-water reactor (LWR), with emphasis on high-level waste (HLW; spent fuel), intermediate-level waste (ILW), and low-level waste (LLW). The objective is to inform infrastructure planning, regulatory preparedness, and long-term waste management. A desk review synthesized unit-normalized data from reactors of comparable capacity in China, Sweden, Switzerland, the United Kingdom, and the United States of America, integrating internationally recognized benchmarks with country-specific operating information. Waste classes follow IAEA GSG-1. Indicative ranges are HLW: ∼18–33.6 tons/yr (dependent on fuel management, burnup, and capacity factor), ILW: ∼2–79 m³/yr (dominated by resins, filters, and selected activated components), and LLW: ∼30–250 m³/yr, with variance driven by burnup, capacity factor, coolant chemistry, purification practice, and outage schedule. These ranges provide defensible inputs for sizing storage, treatment/conditioning, transport, and disposal systems, and for aligning regulatory preparedness with IAEA safety requirements. Early adoption of HLW, ILW, and LLW management provisions based on these planning values will help safeguard public health and the environment while enabling a safe, economically credible introduction of nuclear power in the Philippines and supporting long-term policy and financing decisions.

本研究预测了菲律宾基线部署的约1200兆瓦轻水反应堆（LWR）每年产生的放射性废物，重点是高水平废物（HLW；乏燃料），中水平废物（ILW）和低水平废物（LLW）。其目标是为基础设施规划、监管准备和长期废物管理提供信息。一项案头审查综合了来自中国、瑞典、瑞士、联合王国和美利坚合众国具有可比容量的反应堆的单元标准化数据，将国际公认的基准与具体国家的运行信息相结合。废物类别遵循IAEA GSG-1。指示范围为高流量：~ 18-33.6吨/年（取决于燃料管理、燃耗和容量因子），低流量：~ 2-79立方米/年（由树脂、过滤器和选定的活性成分主导），低流量：~ 30-250立方米/年，差异由燃耗、容量因子、冷却剂化学、净化实践和停机计划驱动。这些范围为确定储存、处理/调节、运输和处置系统的规模以及使监管准备与国际原子能机构的安全要求保持一致提供了可靠的投入。尽早采用基于这些规划价值的高放射性废物、低放射性废物和低放射性废物管理规定，将有助于保障公众健康和环境，同时使菲律宾能够安全、经济上可信地引进核电，并支持长期政策和融资决策。

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引用次数: 0

Enhanced fidelity of Monte Carlo coupled multi-physics simulations in the MCS code 增强的保真蒙特卡罗耦合多物理场模拟在MCS代码

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-10 DOI: 10.1016/j.net.2025.104077

Muhammad Imron , Deokjung Lee

This study integrates previously developed methods to enhance the fidelity of direct whole-core Monte Carlo coupled multi-physics simulations in the MCS code. First, it introduces multi-physics simulations with spatially continuous material properties by using the Functional Expansion Tally combined with delta-tracking. Second, it incorporates on-the-fly thermal expansion of reactor core components during Monte Carlo particle tracking. To evaluate the accuracy and overall performance improvement of the framework, several numerical experiments were conducted at both the assembly and whole-core levels. The incorporation of spatially continuous material properties produces eigenvalue solutions that asymptotically converge to those from conventional cell-based discretized simulations with infinitesimally small cells as demonstrated in the assembly and whole-core problems. In the whole-core problem, the framework reduces simulation times by around threefold and requires 80 % less memory than the traditional cell-based discretization using very small cells, while maintaining the high-fidelity solutions. Whereas the numerical results for on-the-fly thermal expansion demonstrate that the observed trends in reactor reactivity due to thermal expansion align with previous studies. These findings suggest that integrating the multi-physics framework into reactor modeling can enhance simulation fidelity while reducing simulation time.

本研究整合了先前开发的方法，以提高MCS代码中直接全核蒙特卡罗耦合多物理场模拟的保真度。首先，利用函数扩展计数法结合delta跟踪，引入了具有空间连续材料属性的多物理场仿真。其次，在蒙特卡罗粒子跟踪过程中，它结合了反应堆堆芯组件的动态热膨胀。为了评估框架的准确性和整体性能改进，在组装和整个核心水平上进行了一些数值实验。空间连续材料特性的结合产生了特征值解，该解渐近收敛于传统的基于单元的离散化模拟，该模拟具有无穷小的单元，如在装配和整个核心问题中所示。在全核问题中，该框架将模拟次数减少了大约三倍，并且比使用非常小的单元的传统基于单元的离散化减少了80%的内存，同时保持了高保真度的解决方案。而动态热膨胀的数值结果表明，观察到的热膨胀对反应堆反应性的影响趋势与前人的研究一致。这些发现表明，将多物理场框架集成到反应堆建模中可以提高仿真保真度，同时减少仿真时间。

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引用次数: 0

Seismic analyses of i-SMR CV supports employing a component mode synthesis technique 采用分量模态综合技术对i-SMR CV支承进行地震分析

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-12-09 DOI: 10.1016/j.net.2025.104072

Jun-Yeop Lee , Dong-Hyeon Choi , Yoon-Suk Chang

To ensure the safety of next-generation reactors, innovative design concepts and subsequent extensive engineering analyses are essential. However, recurrent modifications of major structures, systems and components require substantial resources for repeated evaluations. This study proposes an efficient component mode synthesis (CMS) technique tailored for a developing small modular reactor. First, the baseline seismic parameters of critical locations were calculated through conventional modal analysis (MA), response spectrum analysis and time history analysis (THA) corresponding to their original configuration. Secondly, benchmark MA and THA were performed using both Craig-Bampton and Hintz-Herting CMS techniques. Comparison with the reference analysis outcomes showed the superior suitability of the latter. Finally, four design alternatives were developed and analyzed using the Hintz-Herting CMS technique to determine the optimal structural arrangement of supports. The results demonstrated that the proposed technique significantly reduced computational time by more than 80 % while preserving dynamic fidelity.

为了确保下一代反应堆的安全，创新的设计理念和随后广泛的工程分析是必不可少的。但是，主要结构、系统和部件的反复修改需要大量资源进行反复评价。本研究提出了一种高效的组件模式合成（CMS）技术，该技术适用于正在开发的小型模块化反应堆。首先，通过常规模态分析（MA）、反应谱分析（response spectrum analysis）和时程分析（time history analysis， THA）计算出关键位置的基线地震参数。其次，使用Craig-Bampton和Hintz-Herting CMS技术进行基准MA和THA。与参考分析结果比较，后者的适宜性更强。最后，利用Hintz-Herting CMS技术，开发并分析了四种设计方案，以确定支撑的最佳结构布置。结果表明，该方法在保持动态保真度的同时，显著减少了80%以上的计算时间。

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引用次数: 0