Nuclear Engineering and Technology最新文献_第6页

Towards a strategic path for the Republic of Korea's nuclear energy policy: Insights for the next revision of the ROK-U.S. nuclear cooperation agreement 走向大韩民国核能政策的战略路径：对韩美合作协定下一次修订的见解。核能合作协议

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

Nuclear Engineering and Technology

Pub Date : 2026-01-05 DOI: 10.1016/j.net.2026.104117

Keonhee Lee , Eunju Jun

This paper examines a multifaceted strategic approach for Republic of Korea's future nuclear energy policy within the complex framework of the ROK-U.S. Nuclear Cooperation Agreement. This agreement serves as the core legal basis for extensive nuclear cooperation between the two nations, evolving from a supplier-consumer relationship to one aiming for mutual exercise of authority and reciprocity following its 2015 revision. However, the U.S. prior consent requirement continues to impose constraints on Korea's nuclear autonomy and technological sovereignty, particularly concerning sensitive nuclear activities such as spent fuel management and enrichment. This study explores the challenges faced by Korea through a comparative analysis of the differentiated prior consent practices applied by the U.S. to various partner countries. It seeks to derive strategic insights for reconciling Korea's energy needs and technological aspirations with U.S. nonproliferation and regional security objectives, while managing potential friction points within the alliance. Ultimately, by proposing a proactive and multifaceted strategic approach - including strengthening domestic research and development (R&D) capabilities, advancing diplomatic efforts, leveraging joint research outcomes, and enhancing Korea's responsible leadership in international nonproliferation - this paper aims to contribute to improving Korea's energy security and technological self-reliance within the framework of the ROK-U.S. alliance.

本文探讨了在韩美关系的复杂框架下，韩国未来核能政策的多方面战略方针。核能合作协定。该协议是两国广泛核合作的核心法律基础，在2015年修订后，从供应商-消费者关系演变为旨在相互行使权力和互惠的关系。然而，美国的事先同意要求继续限制韩国的核自主权和技术主权，特别是在乏燃料管理和浓缩等敏感核活动方面。本研究通过比较分析美国对各伙伴国实行的不同的事先同意惯例，探讨了韩国面临的挑战。它寻求获得战略见解，以协调韩国的能源需求和技术抱负与美国的防扩散和地区安全目标，同时管理联盟内部潜在的摩擦点。最终，通过提出一种积极主动的、多方面的战略方针——包括加强国内研发能力、推进外交努力、利用联合研究成果，以及加强韩国在国际防扩散方面负责任的领导地位——本文旨在为改善韩国的能源安全和在韩美安全框架内的技术自立做出贡献。联盟。

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引用次数: 0

A variable universe fuzzy control method for the HCOTSG feedwater system of small pressurized water reactor 小型压水堆HCOTSG给水系统的变域模糊控制方法

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

Nuclear Engineering and Technology

Pub Date : 2026-01-05 DOI: 10.1016/j.net.2026.104116

Zhihui Yan , Xuan She , Shijia Yang , Wenjie Zeng , Zhifeng Li

Helical-Coil Once-Through Steam Generator (HCOTSG) is a key energy conversion component in the secondary circuit system of Small Pressurized Water Reactor (SPWR), exhibiting lower heat storage capacity and great difficulty in steam pressure regulation. The traditional fuzzy control method adopts a fixed domain of discourse, which has limited adaptability under load change conditions, and it is difficult to meet the requirements of HCOTSG for high precision control. Therefore, this paper proposes a variable universe fuzzy control (VUFC) method for the HCOTSG feedwater system, with the nonlinear mathematical model of the secondary circuit, the real-time adjustment domain of the scaling factor based on fuzzy rules is used to realize the online adaptive control of HCOTSG feedwater system. Simulation results of the SPWR under step load changes show that the VUFC offers faster response speed, smaller overshoot and stronger robustness than traditional fuzzy control, which mitigates the impacts of steam pressure on secondary circuit equipment and improves the operation safety of SPWR.

螺旋盘管式蒸汽发生器（HCOTSG）是小型压水堆（SPWR）二次回路系统中关键的能量转换部件，其蓄热能力较低，蒸汽压力调节难度较大。传统的模糊控制方法采用固定的话语域，对负载变化条件的适应性有限，难以满足HCOTSG高精度控制的要求。为此，本文提出了一种HCOTSG给水系统的变域模糊控制（VUFC）方法，结合二次回路的非线性数学模型，利用基于模糊规则的比例因子实时调整域，实现了HCOTSG给水系统的在线自适应控制。负荷阶跃变化下的SPWR仿真结果表明，与传统模糊控制相比，VUFC具有更快的响应速度、更小的超调量和更强的鲁棒性，减轻了蒸汽压力对二次回路设备的影响，提高了SPWR的运行安全性。

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引用次数: 0

Systematic investigation on neutronics and thermal-hydraulics model for multi-physics analysis of micro molten salt fast reactor with moderating reflector 带慢化反射镜的微熔盐快堆多物理场分析的中子学和热工力学模型的系统研究

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

Nuclear Engineering and Technology

Pub Date : 2026-01-03 DOI: 10.1016/j.net.2026.104114

Wooseong Park, Yong Hoon Jeong

A moderating reflector in Molten Salt Fast Reactors (MSFRs) enables dual‐spectrum core—combining advantages of both fast and thermal spectra—but introduces strong local power peaking and a positive reflector temperature coefficient (RTC), whose impacts in steady and transient states remain largely unexplored. To address the research gap, we systematically evaluated neutronics and thermal-hydraulics model effects on the multi-physics behavior of an MSFR with moderating reflector, using GeN-Foam and OpenMC. First, multi-group diffusion analysis with various multi-group cross section (MGXS) models was conducted, demonstrating that refined MGXS (30-group structure with multi-region spatial homogenization) model can provide reasonably accurate predictions for MSFR with moderating reflector. Next, the influences of different neutronics (N) and thermal-hydraulics (TH) models on steady-state multi-physics calculations were examined. The results show that explicit reflector region modeling in TH simulation, together with the refined MGXS model, is crucial for accurate multi-physics simulation. Finally, transient analysis of accident scenarios was performed to investigate the basic dynamic behavior of the system and to assess the impacts of the positive RTC and MGXS model. The results show that simple MGXS model exhibits delayed power response to negative temperature feedback, and that positive RTC effects are not significant over short-term periods.

熔盐快堆（MSFRs）中的慢化反射器能够实现双光谱堆芯——结合快光谱和热光谱的优势——但引入了强的局部功率峰值和正反射器温度系数（RTC），其对稳态和瞬态的影响在很大程度上仍未被探索。为了弥补研究空白，我们使用GeN-Foam和OpenMC系统地评估了中子力学和热工力学模型对带调节反射器的MSFR多物理场行为的影响。首先，利用不同的多组截面（multi-group cross section， MGXS）模型进行了多组扩散分析，结果表明，改进的MGXS（30组结构，多区域空间均匀化）模型能够较为准确地预测具有调节反射镜的MSFR。其次，研究了不同的中子模型(N)和热工模型（TH）对稳态多物理场计算的影响。结果表明，在TH模拟中，明确的反射区建模以及改进的MGXS模型对于精确的多物理场模拟至关重要。最后，进行了事故场景的瞬态分析，研究了系统的基本动态行为，并评估了正RTC和MGXS模型的影响。结果表明，简单MGXS模型对温度负反馈的功率响应延迟，且短期内正RTC效应不显著。

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引用次数: 0

Regulatory analysis and enhancement opportunities for supply chain cybersecurity in Korean nuclear facilities 韩国核设施供应链网络安全的监管分析和改进机会

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

Nuclear Engineering and Technology

Pub Date : 2026-01-01 DOI: 10.1016/j.net.2025.103803

Hyunwoo Yoo , Manhyun Chung , Moonsu Jang , Jaehoon Lee

The surge in cyber incidents such as the SolarWinds, Log4j, and MOVEit attacks, underscores the need for a comprehensive supply chain cybersecurity framework. It is particularly important for critical infrastructure, such as nuclear facilities, where a breach could have catastrophic human and environmental consequences. This study defines the necessary scope of supplier organizational and linkage security management throughout the entire lifecycle of nuclear facilities. A comparative analysis is then conducted with Korean nuclear cybersecurity regulations, focusing on the regulatory standard KINAC/RS-015 and its 101 cybersecurity controls. Certain controls requiring supplier organizational and linkage security serve as a solid foundation for comprehensive supply chain cybersecurity management. The controls within the development organizational security scope are generally well established, which is encouraging given the growing emphasis on secure software development and continuous vulnerability management. Some deficiencies are also identified. The current framework primarily focuses on the licensee, outlining cybersecurity implementation from its perspective. As a result, regulations remain largely confined to activities within nuclear facilities and impose few explicit requirements on suppliers. However, given the inevitability of supply chain threats, the regulatory focus must extend beyond nuclear facilities to ensure their safety.

SolarWinds、Log4j和MOVEit等网络攻击事件的激增，凸显了建立全面供应链网络安全框架的必要性。这对核设施等关键基础设施尤其重要，因为一旦违反，可能会对人类和环境造成灾难性后果。本研究明确了核设施全生命周期中供应商组织与联动安全管理的必要范围。然后与韩国核网络安全法规进行比较分析，重点关注监管标准KINAC/RS-015及其101项网络安全控制措施。对供应商组织和联动安全的控制是全面供应链网络安全管理的坚实基础。开发组织安全范围内的控制通常是很好的建立起来的，考虑到对安全软件开发和持续漏洞管理的日益强调，这是令人鼓舞的。还发现了一些不足之处。目前的框架主要关注被许可方，从其角度概述网络安全实施。因此，管制仍然主要局限于核设施内的活动，对供应商没有多少明确的要求。然而，鉴于供应链威胁的必然性，监管的重点必须超越核设施，以确保其安全。

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引用次数: 0

Development of a 3D reconstruction method using a pendulum RGB-D camera 基于摆式RGB-D相机的三维重建方法研究

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

Nuclear Engineering and Technology

Pub Date : 2026-01-01 DOI: 10.1016/j.net.2025.103922

Shigeaki Futagami, Kimi Ueda, Hirotake Ishii, Hiroshi Shimoda

In recent years, 3D models that imitate the real environment have been used in various fields, such as work support at nuclear power plants and disaster experiences using VR. One of the methods to create such 3D models is the 3D reconstruction method which uses images taken by a camera. In most cases, this method estimates the camera pose, including the 3D position and orientation of the camera at the time the image was taken by image processing. Then, a 3D model is created based on the estimated camera pose. However, since estimating the camera pose of an image with few features is difficult, regions with few features, such as a monochromatic flat wall, are missing from the 3D model created. Therefore, this study aims to develop a 3D reconstruction method without missing regions with few features by using the laws of the pendulum motion. In this method, the entire pendulum motion is estimated from a portion of the pendulum motion estimated by image processing. A 3D model is then created based on the estimated entire motion. The evaluation shows that the proposed method can reconstruct the environment which includes the area with few features.

近年来，模拟真实环境的3D模型已经应用于各个领域，例如核电站的工作支持和使用VR的灾难体验。创建这种3D模型的方法之一是使用相机拍摄的图像的3D重建方法。在大多数情况下，该方法估计相机姿态，包括相机在图像处理时的3D位置和方向。然后，根据估计的相机姿态创建3D模型。然而，由于估计具有少量特征的图像的相机姿态是困难的，因此具有少量特征的区域，例如单色平面墙，在创建的3D模型中会丢失。因此，本研究旨在利用钟摆运动规律，开发一种无特征缺失区域的三维重建方法。在该方法中，由图像处理估计的钟摆运动的一部分来估计整个钟摆运动。然后根据估计的整个运动创建一个3D模型。评价结果表明，该方法可以重建包含特征较少区域的环境。

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引用次数: 0

Automating power-increase operation for small modular reactors based on task analysis with proximal policy optimization 基于任务分析和近端策略优化的小型模块化反应堆增功率运行自动化

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

Nuclear Engineering and Technology

Pub Date : 2026-01-01 DOI: 10.1016/j.net.2025.103767

Hee-Jae Lee , Daeil Lee , Jonghyun Kim

Interest in small modular reactors (SMRs) has been growing for their enhanced safety design and operational flexibility. For their adoption, one related challenge to be resolved is the increase in the task load of operators, as SMRs are designed for multi-module operation. This challenge is further heightened during the power-increase operation, which requires continuous monitoring and manual adjustments for an extended period. To address this, this study proposes an autonomous algorithm for the tasks involved in the power-increase operation of SMRs. Utilizing an integral pressurized water reactor simulator that mimics the operation of an SMR, this study first performed a task analysis of the power-increase operation to identify candidate tasks for automation and to derive automation strategies. Based on the task analysis results, an algorithm was designed by combining a deep reinforcement learning–based system with a rule-based system, specifically proximal policy optimization and if-then rules, respectively. Experimental results showed that the autonomous algorithm successfully managed the power-increase operation, achieving 100 % reactor power while staying within operational constraints. Additionally, the developed algorithm was implemented and visualized through a graphical user interface, providing real-time monitoring of key parameters during the power-increase operation.

小型模块化反应堆（smr）因其增强的安全设计和操作灵活性而受到越来越多的关注。由于smr是为多模块操作而设计的，因此需要解决的一个相关挑战是操作人员的任务负荷增加。在功率增加作业期间，这一挑战进一步加剧，因为这需要长时间的连续监测和手动调整。为了解决这一问题，本研究提出了一种自主算法，用于smr功率增加操作中涉及的任务。利用模拟SMR运行的整体式压水堆模拟器，本研究首先对功率增加操作进行了任务分析，以确定自动化的候选任务并得出自动化策略。在任务分析结果的基础上，将基于深度强化学习的系统与基于规则的系统相结合，分别设计了基于近端策略优化和if-then规则的算法。实验结果表明，自主算法成功地管理了功率增加操作，在不受运行约束的情况下实现了100%的反应堆功率。此外，开发的算法通过图形用户界面实现和可视化，在功率增加操作期间提供关键参数的实时监控。

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引用次数: 0

Coordinated control of the World's first multi-modular high temperature gas-cooled reactor power plant HTR-PM 协调控制世界首个多模块高温气冷堆电厂HTR-PM

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

Nuclear Engineering and Technology

Pub Date : 2026-01-01 DOI: 10.1016/j.net.2025.103940

Di Jiang, Zhe Dong, Yunlong Zhu, Hui Yu, Xiaojin Huang

The modular high temperature gas-cooled reactor (mHTGR) adopts helium as coolant, graphite as moderator and structural material, and TRISO particle-based fuel elements. The HTR-PM is the world's first multi-modular high temperature gas-cooled reactor power plant, having successfully entered to its commercial operation. To ensure inherent safety, the two reactors of HTR-PM are designed with the features of low power density, strong negative temperature feedback and large surface-to-volume ratio, giving a rated reactor thermal power of 200MWt. To enlarge plant power rating, the scheme of two reactor modules driving a common steam turbine is deployed. Since the modules are coupled by the turbine, the coordinated control is key in providing a stable and efficient operation. In this paper, the design of implementing coordinated control laws on distributed control system (DCS) is given. Then, the response of key process variables under power step conditions is analyzed This work manifest the feasibility of multi-modular nuclear power plant (NPP) scheme for the first time, showing the promising future in building large-scale NPPs by small modular reactors (SMRs).

模块化高温气冷堆（mHTGR）采用氦气作为冷却剂，石墨作为慢化剂和结构材料，采用TRISO颗粒基燃料元件。HTR-PM是世界上第一个多模块高温气冷堆电厂，已成功进入商业运行。为保证固有安全，两台HTR-PM反应堆采用了低功率密度、强温度负反馈、大面容比的设计，额定反应堆热功率为200MWt。为了提高机组的额定功率，采用了两个反应堆模块驱动一台普通汽轮机的方案。由于各模块由涡轮机耦合，因此协调控制是提供稳定高效运行的关键。本文给出了在集散控制系统（DCS）上实现协调控制律的设计。在此基础上，分析了关键过程变量在功率阶跃条件下的响应，首次证明了多模块化核电站方案的可行性，展示了小型模块化反应堆建设大型核电站的广阔前景。

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引用次数: 0

Enhanced learning for nuclear power plant condition diagnoses using information metric based on Bayesian neural networks and UMAP 基于贝叶斯神经网络和UMAP的信息度量在核电厂状态诊断中的强化学习

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

Nuclear Engineering and Technology

Pub Date : 2026-01-01 DOI: 10.1016/j.net.2025.103886

Young Ho Chae , Seo Ryong Koo , Jeonghun Choi , Jonghyun Kim

This study introduces an enhanced active learning framework utilizing Bayesian neural networks for nuclear power plant condition diagnoses. A novel multi-component information need metric combining uncertainty, density, entropy, and diversity with adaptive weighting is proposed to efficiently identify informative training samples. Validation using the International Atomic Energy Agency's integral pressurized water reactor simulator with 26 abnormal conditions across 10 independent runs demonstrates significant improvements. Our approach achieved 70.24 ± 2.18 % accuracy, outperforming both BALD (67.03 ± 2.12 %) and random selection (52.68 ± 5.62 %). Notably, the method required 50 % fewer samples than random selection to achieve equivalent performance, while maintaining superior stability. F1-Macro scores (0.726 vs BALD's 0.672) indicate balanced performance across all conditions. UMAP visualizations confirmed that the multi-component metric effectively identifies samples at decision boundaries and sparse regions. The framework demonstrates that integrating multiple information components provides superior accuracy, stability, and data efficiency compared to single uncertainty-based methods, making it valuable for safety-critical applications where labeled abnormal data is scarce and limited.

本文介绍了一种利用贝叶斯神经网络进行核电厂状态诊断的增强主动学习框架。提出了一种结合不确定性、密度、熵和多样性与自适应加权相结合的多分量信息需求度量，以有效识别信息丰富的训练样本。使用国际原子能机构的整体压水堆模拟器进行验证，在10次独立运行中有26个异常条件，显示出显着的改进。该方法的准确率为70.24±2.18%，优于BALD（67.03±2.12%）和随机选择（52.68±5.62%）。值得注意的是，该方法所需的样本比随机选择少50%，以达到相同的性能，同时保持优越的稳定性。F1-Macro得分（0.726 vs BALD的0.672）表明在所有条件下的平衡表现。UMAP可视化证实了多分量度量在决策边界和稀疏区域有效地识别样本。该框架表明，与基于不确定性的单一方法相比，集成多个信息组件提供了更高的准确性、稳定性和数据效率，使其对标记异常数据稀缺和有限的安全关键应用具有价值。

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引用次数: 0

Dependency assessment in human reliability analysis based on performance shaping factors 基于性能塑造因素的人的可靠性分析中的依赖性评估

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

Nuclear Engineering and Technology

Pub Date : 2026-01-01 DOI: 10.1016/j.net.2025.103831

Gyun Seob Song, Man Cheol Kim

Human actions are significant risk contributors in the probabilistic safety assessment of nuclear power plants. In the human reliability analysis (HRA), human failure events are typically treated as dependent events. Accordingly, various studies have been conducted for the dependency assessment in HRA. Performance shaping factors (PSFs), which influence human performance, are a key element in HRA. In conventional HRA models, PSFs are analyzed based on specific conditions affecting human performance. However, in reality, PSFs inherently involve randomness, and this uncertainty should be incorporated into the estimation of human error probabilities. This paper proposes a dependency assessment method that integrates the randomness of PSFs. A statistical framework is presented to explain the sources of dependency and to provide a calculation method based on PSFs. A case example is included to demonstrate the impact of such dependency. The proposed approach is particularly useful in situations where PSFs exhibit large variability.

在核电厂概率安全评价中，人的行为是重要的风险因素。在人的可靠性分析（HRA）中，人的故障事件通常被视为依赖事件。因此，对HRA的依赖性评估进行了各种研究。绩效形成因素（psf）是影响人类绩效的关键因素。在传统的HRA模型中，psf是根据影响人类表现的特定条件来分析的。然而，在现实中，psf本质上涉及随机性，这种不确定性应该纳入人为错误概率的估计中。本文提出了一种综合psf随机性的依赖评估方法。提出了一个统计框架来解释依赖的来源，并提供了一种基于psf的计算方法。包括一个案例示例来演示这种依赖关系的影响。所建议的方法在psf表现出较大变异性的情况下特别有用。

引用次数: 0

Optimization and parameter sizing of nuclear-battery hybrid system for distributed power source 分布式电源核电池混合系统的优化与参数确定

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

Nuclear Engineering and Technology

Pub Date : 2026-01-01 DOI: 10.1016/j.net.2025.103859

Jingkang Li , Zunyan Hu , Zeguang Li , Liangfei Xu , Jianqiu Li

Nuclear hybrid energy system (NHES) composed of micro modular reactor (MMR) and energy storage system (ESS) has promising applications in distributed power sources like islands or remote regions. In this article, to fulfill a typical dynamic power demand with a mean value of 1MWe and a peak-to-average ratio of 1.25, a novel NHES configuration, including an MMR composed of heat pipe cooled reactor (HPR) and closed Brayton cycle (CBC), and a battery storage system (BSS) as its ESS, is proposed and comprehensively analyzed for the first time. Considering the output power of MMR as the control variable, the efficiency optimization of the NHES is conducted using DP. Based on the optimization results, there is a lower limit for BSS capacity of about 1.4 MWh and a lower limit for MMR maximum output power of 1.1MWe. The efficiency of the NHES is strongly related to the scale of MMR. With the increase of the MMR scale, the average load of MMR is reduced, resulting in lower mean energy conversion efficiency. An LSTM-based control strategy is proposed based on typical optimization results for real-time control, which can achieve near-optimal efficiency and has good adaptability to different power demands.

由微模块堆（MMR）和储能系统（ESS）组成的核混合能源系统（NHES）在孤岛或偏远地区等分布式电源中具有广阔的应用前景。为了满足平均功率为1MWe、峰均比为1.25的典型动态功率需求，本文首次提出了一种新型的NHES配置，其中包括热管冷却堆（HPR）和闭式布雷顿循环（CBC）组成的MMR，以及电池储能系统（BSS）作为其ESS。以MMR的输出功率为控制变量，利用DP对NHES进行效率优化。根据优化结果，BSS容量的下限约为1.4 MWh， MMR最大输出功率的下限约为1.1MWe。国家卫生系统的效率与MMR的规模密切相关。随着MMR规模的增大，MMR的平均负荷减小，导致平均能量转换效率降低。根据典型的实时控制优化结果，提出了一种基于lstm的控制策略，该策略可以达到接近最优的效率，并且对不同的功率需求具有良好的适应性。

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引用次数: 0