Nuclear Engineering and Technology最新文献_第3页

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

Results of the IAEA coordinated research project enhancing computer security for radiation detection systems 原子能机构加强辐射探测系统计算机安全的协调研究项目的成果

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.2025.103998

Rodney Busquim e Silva , Michael T. Rowland , Ricardo Paulino Marques , Isabelle Coelho Franco , Jianghai Li , Tamas Holczer , Khalil El-Khatib , Nelson Agbemava , I Putu Susila , Jacek Gajewski , David Allison , Imbaby Mahmoud , Greg White

This work presents results of the International Atomic Energy Agency's Coordinated Research Project (CRP) on Enhancing Computer Security for Radiation Detection Systems. These systems include a wide range of fixed and mobile radiation detectors used in safety and security applications. The signals and data generated by radiation detection systems are transmitted to local or remote monitoring centers through various communication channels, enhancing the effectiveness of threat detection and enabling a timely response to alarm conditions. However, during the generation, processing, transmission and display of this information, data can be compromised. This CRP brought together 11 research institutes from 10 Member States to explore various topics, including threat modeling, cloud computing, malware propagation in large radiation detection networks, intrusion detection systems, defensive computer security architecture, wireless communication security, and simulation of integrated physical protection and radiation detection systems. The participating institutes created a reference architecture, designed models for synthetic radiation data and anomaly detection methods, performed vulnerability assessments of radiation detection systems, and developed prototypes for both virtual and hardware-in-the-loop testbeds. Their research also led to the creation of simulators, including a physical protection–radiation detector simulator that incorporates a 3D hospital model.

这项工作介绍了国际原子能机构关于加强辐射探测系统计算机安全的协调研究项目（CRP）的结果。这些系统包括用于安全和安保应用的各种固定和移动辐射探测器。辐射探测系统产生的信号和数据通过各种通信渠道传送到本地或远程监测中心，提高了威胁探测的有效性，并能及时对警报情况作出反应。然而，在生成、处理、传输和显示这些信息的过程中，数据可能会受到损害。该CRP汇集了来自10个成员国的11个研究机构，探讨各种主题，包括威胁建模、云计算、大型辐射检测网络中的恶意软件传播、入侵检测系统、防御性计算机安全体系结构、无线通信安全以及综合物理防护和辐射检测系统的模拟。参与研究的机构创建了一个参考架构，设计了合成辐射数据和异常检测方法的模型，对辐射检测系统进行了脆弱性评估，并开发了虚拟和硬件在环测试平台的原型。他们的研究还导致了模拟器的创建，包括一个物理保护辐射探测器模拟器，其中包含一个3D医院模型。

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引用次数: 0

A study on process information-driven cyber threat detection for I&C systems in NPP 核电站I&C系统过程信息驱动的网络威胁检测研究

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.2025.103879

Jae Hwan Kim, Kwang Seop Son, Jae Gu Song, Yong Gu Lee, Young Jun Lee

The increasing digitalization of Instrumentation and Control (I&C) systems in Nuclear Power Plants (NPPs) has improved operational efficiency while introducing cybersecurity vulnerabilities. Conventional network-based intrusion detection systems (IDS) face limitations in detecting sophisticated cyber threats targeting safety-critical controllers. To address these challenges, this study proposes a process information-driven cyber threat detection methodology based on real-time process data analysis and control logic consistency, enabling non-intrusive threat identification. The proposed methodology was examined through simulation and experimental testing using an APR-1400 Reactor Protection System (RPS) testbed. A cyber attack scenario targeting the High Pressurizer Pressure (HPP) Trip function was designed to assess the effectiveness of the detection mechanism. Simulation results demonstrated the detection algorithm's ability to identify unauthorized modifications to the trip setpoint, indicating the potential to detect cyber threats affecting reactor trip logic. Furthermore, experimental testing using the Safety Data Acquisition & Detection System (SDDS) demonstrated real-time anomaly detection while maintaining system integrity. These findings suggest that the proposed process-driven detection technique can enhance the cybersecurity resilience of NPPs without disrupting operational stability.

核电站仪表和控制（I&；C）系统的日益数字化提高了运行效率，同时引入了网络安全漏洞。传统的基于网络的入侵检测系统（IDS）在检测针对安全关键控制器的复杂网络威胁方面面临局限性。为了应对这些挑战，本研究提出了一种基于实时过程数据分析和控制逻辑一致性的过程信息驱动的网络威胁检测方法，从而实现非侵入式威胁识别。通过APR-1400反应堆保护系统（RPS）试验台的仿真和实验测试，验证了所提出的方法。设计了一个针对高稳压器压力（HPP）脱扣功能的网络攻击场景，以评估检测机制的有效性。仿真结果表明，该检测算法能够识别对脱扣设定值的未经授权的修改，表明检测影响反应堆脱扣逻辑的网络威胁的潜力。此外，使用安全数据采集和检测系统（SDDS）进行的实验测试表明，在保持系统完整性的同时，可以实时检测异常。这些发现表明，所提出的过程驱动检测技术可以在不破坏运行稳定性的情况下增强核电站的网络安全弹性。

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引用次数: 0

Benchmark analysis of SPERT III E-core critical experiments using the STREAM neutronics code 使用STREAM中子码对SPERT III E-core临界实验进行基准分析

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

Nuclear Engineering and Technology

Pub Date : 2025-12-31 DOI: 10.1016/j.net.2025.104112

Anisur Rahman , Saisundar Mohanty , Deokjung Lee

This study delivers a high-fidelity neutronic analysis of the SPERT III E-Core, a pressurized-water experimental reactor designed to probe fundamental transient behavior during reactivity-initiated accidents (RIAs). Using the advanced 3D transport code STREAM, we construct a detailed full-core representation—including fuel assemblies, cruciform transient control rods, control rod followers, and flux suppressors, to simulate both steady-state operation and rapid power excursions. Eigenvalue predictions at cold and hot zero-power conditions agree with measurements within 400 pcm, while simulated RIA responses, including reactivity evolution, peak power, and energy release, remain within 10 % of experimental observations. These results demonstrate that STREAM reliably captures fast transient dynamics in complex reactor configurations. Beyond validating a modern deterministic tool against historically important pulse-reactor experiments, this work establishes a foundation for next-generation transient modeling, supporting enhanced safety assessment, performance optimization, and informed regulatory decision-making in advanced reactor systems.

这项研究提供了SPERT III E-Core的高保真中子分析，这是一种压水实验反应堆，旨在探测反应性引发事故（ria）期间的基本瞬态行为。使用先进的3D传输代码STREAM，我们构建了一个详细的全核心表示-包括燃料组件，十字形瞬态控制棒，控制棒跟随器和通量抑制器，以模拟稳态运行和快速功率漂移。冷、热零功率条件下的特征值预测与400 pcm以内的测量结果一致，而模拟的RIA响应，包括反应性演化、峰值功率和能量释放，与实验观测值的误差仍在10%以内。这些结果表明STREAM可靠地捕获了复杂反应堆结构中的快速瞬态动力学。除了通过历史上重要的脉冲反应堆实验验证现代确定性工具之外，这项工作还为下一代瞬态建模奠定了基础，支持先进反应堆系统中增强的安全评估、性能优化和知情的监管决策。

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引用次数: 0