Nuclear Engineering and Technology最新文献_第5页

STPA-based approach to identifying extraneous errors of commission in FOAK advanced reactors 基于stpa的FOAK先进反应堆外部调试误差识别方法

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

Nuclear Engineering and Technology

Pub Date : 2026-01-07 DOI: 10.1016/j.net.2026.104130

Sung-Min Shin, Yochan Kim, Jinkyun Park, Jin Hee Park

First-of-a-kind (FOAK) advanced nuclear reactors, including small modular reactors, increasingly rely on autonomous safety systems to achieve high levels of safety and efficiency. While such designs reduce the need for manual intervention, they also introduce new complexities in supervisory control that may lead to errors of commission (EOCs). In particular, extraneous EOCs, referring to operator actions that are unnecessary and potentially hazardous, have not been systematically addressed by conventional human reliability analysis methods. This study investigates the feasibility of applying Systems-Theoretic Process Analysis (STPA) to systematically identify extraneous EOCs in autonomous safety contexts. An application to a fail-safe passive safety system demonstrates how STPA can trace the causal mechanisms of inappropriate operator interventions, revealing loss scenarios and pathways specific to extraneous EOCs. Beyond this methodological validation, the study derives example requirements to support safe interaction between autonomous safety functions and human operators. These requirements illustrate how STPA results can be translated into general guidance for ensuring that human–automation interactions preserve system safety while accommodating supervisory flexibility. In doing so, the proposed approach extends the analytical scope of human reliability methods and provides a structured foundation for managing operator–system dynamics in FOAK advanced reactors.

包括小型模块化反应堆在内的首个先进核反应堆越来越依赖自主安全系统来实现高水平的安全性和效率。虽然这种设计减少了人工干预的需要，但它们也在监督控制中引入了新的复杂性，可能导致操作错误（eoc）。特别是，对于不必要的、潜在危险的操作，常规的人为可靠性分析方法还没有系统地解决。本研究探讨了应用系统理论过程分析（STPA）系统识别自主安全环境中外部eoc的可行性。故障安全被动安全系统的应用表明，STPA可以追踪操作人员不当干预的因果机制，揭示外部EOCs特有的损失情景和路径。除了这种方法验证之外，该研究还派生了支持自主安全功能与人类操作员之间安全交互的示例要求。这些要求说明了如何将STPA结果转化为一般指导，以确保人机交互在适应监管灵活性的同时保持系统安全。在此过程中，所提出的方法扩展了人类可靠性方法的分析范围，并为管理FOAK先进反应堆的操作系统动力学提供了结构化基础。

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引用次数: 0

Performance evaluation of tungsten coded-aperture masks with different tungsten material densities for a miniature gamma camera 小型伽玛相机不同钨材料密度钨编码孔径掩模性能评价

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

Nuclear Engineering and Technology

Pub Date : 2026-01-06 DOI: 10.1016/j.net.2026.104119

Seungho Lee, Manhee Jeong

This study presents a material-density engineering approach to further miniaturize gamma-ray imaging systems for unmanned platforms with strict payload limitations. Three coded-aperture masks were fabricated with identical geometry but different densities: pure tungsten (19.3 g/cm³) and tungsten filament composites (7.8 g/cm³ and 4.0 g/cm³). These masks were integrated into a miniature gamma camera and systematically evaluated in terms of spectroscopic and imaging performance, with results benchmarked against the commercial Energetic Particle Sensor for the Identification and Localization of Originating Nuclei-Gamma (EPSILON-G) system. Spectroscopic tests with a ¹³⁷Cs source demonstrated an energy resolution of 6.35 %, representing an improvement of about 2 % compared with EPSILON-G, along with favorable peak-to-Compton ratio (PCR) and peak-to-Valley ratio (PVR) values. Imaging results showed that lower mask density generally reduced field of view, angular resolution, and sensitivity. However, the 7.8 g/cm³ tungsten filament mask achieved the optimal balance, yielding 5.6° angular resolution and sensitivity 2–3 times higher than EPSILON-G. Notably, EPSILON-G required up to 150 s for image reconstruction under the same dose-rate conditions, whereas the miniature system localized sources more rapidly due to additional shielding suppressing background radiation. The 7.8 g/cm³ mask reduced weight by 57 % relative to pure tungsten, and the complete miniature gamma camera weighed only ∼700 g, underscoring its suitability for unmanned deployment.

该研究提出了一种材料密度工程方法，以进一步小型化具有严格有效载荷限制的无人平台的伽马射线成像系统。三种编码孔径掩模具有相同的几何形状，但密度不同：纯钨（19.3 g/cm3）和钨丝复合材料（7.8 g/cm3和4.0 g/cm3）。这些掩模被集成到一个微型伽马相机中，并在光谱和成像性能方面进行了系统评估，结果与商用高能粒子传感器（EPSILON-G）系统进行了基准测试，用于识别和定位原始核伽马（EPSILON-G）系统。137Cs光源的光谱测试表明，能量分辨率为6.35%，与EPSILON-G相比提高了约2%，同时具有良好的峰谷比（PVR）和峰康普顿比（PCR）值。成像结果表明，较低的掩模密度通常会降低视场、角分辨率和灵敏度。然而，7.8 g/cm3的钨丝掩膜达到了最佳平衡，产生5.6°角分辨率和灵敏度比EPSILON-G高2-3倍。值得注意的是，在相同剂量率条件下，EPSILON-G需要长达150秒的图像重建，而微型系统由于额外的屏蔽抑制背景辐射，可以更快地定位源。与纯钨相比，7.8 g/cm3的掩模重量减轻了57%，完整的微型伽马相机重量仅为~ 700 g，强调了其无人部署的适用性。

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引用次数: 0

An efficient Gauss-Seidel-based acceleration method for solving the MMPA burnup equation system in nuclear reactors 求解核反应堆MMPA燃耗方程系统的一种高效高斯-塞德尔加速方法

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

Nuclear Engineering and Technology

Pub Date : 2026-01-06 DOI: 10.1016/j.net.2026.104121

Yuqing Sun , Binhang Zhang , Hanyuan Gong , Changxiao Guan , Yonghong Zhang , Xianbao Yuan

Burnup calculation ensures the operational safety of nuclear reactors by determining the evolutionary behavior of radioactive nuclides through the solution of the burnup equations. The Mini-Max Polynomial Approximation (MMPA) method is an effective solution technique developed in recent years, and it offers several advantages over the Chebyshev Rational Approximation Method (CRAM). However, solving the MMPA system of equations using sparse Gaussian elimination (SGE) is computationally expensive because it involves repeated symbolic factorization, especially for large-scale problems. This study develops a Gauss-Seidel (GS)-based acceleration method, an iterative approach that avoids matrix preprocessing and reduces storage overhead by retaining only the necessary matrices and vectors. It offers fast convergence for diagonally dominant matrices. The method was rigorously implemented and verified through a light water reactor (LWR) pin-cell case, by utilizing three burnup databases containing the 71-, 221-, and 1487-nuclide inventories. The results obtained from all burnup databases indicate that once the approximation order exceeds 32, the average absolute relative difference of nuclide number densities reaches a magnitude of 10⁻¹⁰. The distribution of relative difference in nuclide number densities also becomes more concentrated and falls below 1.0 × 10⁻¹¹, confirming excellent computational accuracy. In terms of efficiency, the GS-based acceleration method outperforms the SGE method across the approximation order range of 32–48. For the 1487-nuclide database, the GS-based acceleration method achieves a runtime reduction of nearly 50 % compared to the SGE method. For computations involving the 221- and 71-nuclide databases, the GS-based acceleration method achieves a computational efficiency improvement of at least 70 %. This method provides an effective solution for enhancing the computational efficiency of burnup equations, which in turn contributes to improving the efficiency of large-scale burnup calculations.

燃耗计算通过求解燃耗方程来确定放射性核素的演化行为，从而保证核反应堆的运行安全。最小-最大多项式近似法（MMPA）是近年来发展起来的一种有效的求解方法，它与切比雪夫有理近似法（CRAM）相比具有许多优点。然而，使用稀疏高斯消去（SGE）求解MMPA方程组的计算成本很高，因为它涉及重复的符号分解，特别是对于大规模问题。本研究开发了一种基于Gauss-Seidel （GS）的加速方法，这是一种迭代方法，避免了矩阵预处理，并通过仅保留必要的矩阵和向量来减少存储开销。它提供了对角占优矩阵的快速收敛性。该方法在一个轻水反应堆（LWR）针槽案例中得到了严格的实施和验证，使用了包含71-、221-和1487-核素清单的三个燃用数据库。从所有燃用数据库得到的结果表明，一旦近似阶数超过32，核素数密度的平均绝对相对差达到10−10的量级。核素数密度的相对差分布也变得更加集中，降至1.0 × 10−11以下，证实了较好的计算精度。在效率方面，基于gs的加速方法在32-48阶近似范围内优于SGE方法。对于1487核素数据库，基于gs的加速方法与SGE方法相比，运行时间减少了近50%。对于涉及221和71核素数据库的计算，基于gs的加速方法实现了至少70%的计算效率提高。该方法为提高燃耗方程的计算效率提供了有效的解决方案，从而有助于提高大规模燃耗计算的效率。

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引用次数: 0

Study of the removal of Th(IV) and U(VI) from aqueous solutions using lemon charcoal 柠檬炭去除水溶液中Th（IV）和U（VI）的研究

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

Nuclear Engineering and Technology

Pub Date : 2026-01-06 DOI: 10.1016/j.net.2026.104124

Shrouq AlAzzeh, Fawwaz I. Khalili

This study evaluated the adsorption potential of lemon-derived charcoal for removing Th(IV) and U(VI) ions from aqueous solutions. The adsorbent was characterized using Fourier-transform infrared (FTIR) spectroscopy, thermogravimetric analysis (TGA), powder X-ray diffraction (P-XRD), scanning electron microscopy (SEM), and Brunauer–Emmett–Teller (BET) surface area analysis, revealing a specific surface area of 123.65 m²/g and a pore volume of 0.468 cm³/g. Additional physicochemical properties, including point of zero charge, bulk density, porosity, and cation exchange capacity, were also determined. Optimal adsorption occurred at an adsorbent dose of 0.03 g, pH 4.0, and contact times of 20 min for Th(IV) and 60 min for U(VI). Kinetic studies indicated that adsorption followed the pseudo-second-order model for both ions. The equilibrium data were fitted to four isotherm models—Freundlich, Langmuir, Dubinin–Radushkevich, and Temkin—yielding maximum adsorption capacities (q_m) of 75.15 mg/g for Th(IV) at 25.0 °C and 44.26 mg/g for U(VI). Thermodynamic analysis (ΔH°, ΔS°, ΔG°) confirmed that the adsorption process was spontaneous and exothermic.

本研究评价了柠檬衍生炭对水中Th（IV）和U（VI）离子的吸附潜力。采用傅里叶变换红外光谱（FTIR）、热重分析（TGA）、粉末x射线衍射（P-XRD）、扫描电镜（SEM）和brunauer - emmet - teller （BET）表面积分析对该吸附剂进行了表征，其比表面积为123.65 m2/g，孔隙体积为0.468 cm3/g。其他物理化学性质，包括零电荷点、体积密度、孔隙度和阳离子交换容量也被确定。吸附剂剂量为0.03 g， pH为4.0,Th（IV）接触时间为20 min， U（VI）接触时间为60 min，吸附效果最佳。动力学研究表明，两种离子的吸附均符合准二级模型。平衡数据符合freundlich、Langmuir、Dubinin-Radushkevich和temkin四种等温模型，在25.0℃条件下，Th（IV）的最大吸附量为75.15 mg/g， U（VI）的最大吸附量为44.26 mg/g。热力学分析（ΔH°，ΔS°，ΔG°）证实吸附过程为自发的放热过程。

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引用次数: 0

Improving the detection efficiency of IRan ANtineutrino Detector (IRAND) based on Convolutional Neural Network (CNN) 基于卷积神经网络（CNN）提高伊朗反中微子探测器（IRAND）的检测效率

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

Nuclear Engineering and Technology

Pub Date : 2026-01-06 DOI: 10.1016/j.net.2026.104118

Mahdieh Sadat Mousavi, Faezeh Rahmani

Discriminating reactor electron antineutrino from the cosmic muon is a fundamental challenge in antineutrino detection using Inverse Beta Decay (IBD) interaction in scintillator-based detectors. This study introduces an innovative approach by employing a Convolutional Neural Network (CNN) in the IRAND-Sim-02 simulation package to distinguish between muon and antineutrino in the IRAND (a 10 × 10 array of segmented plastic scintillator IRan ANtineutrino Detector) for improving IRAND's performance. A training dataset was generated using Geant4 via the IRAND-Sim-02 package (analytical images-Temporal Probability Density, Time vs. Photocathode ID, and photocathode activation topology-to encode the spatiotemporal patterns of the events). For model evaluation, an independent test dataset, reflecting the true antineutrino-to-cosmic-muon ratio, was automatically produced by establishing a real-time Geant4-Python TCP socket connection. The overall accuracy of 99.97 % by CNN model demonstrates the precise event classification. Compared with traditional machine learning approaches, such as Artificial Neural Network (ANN) and Decision Tree models, the proposed CNN demonstrates greater reliability in distinguishing IBD events from cosmic muon backgrounds, particularly under class imbalance conditions, which highlights the considerable potential of our method for improving nuclear reactor monitoring and represent a significant advancement in the application of deep learning to fundamental particle detection.

区分反应堆电子反中微子和宇宙介子是利用反比衰变（IBD）相互作用在闪烁体探测器中进行反中微子探测的一个基本挑战。本研究引入了一种创新的方法，通过在IRAND- sim -02仿真包中使用卷积神经网络（CNN）来区分IRAND（一个10 × 10阵列分段塑料闪烁体伊朗反中微子探测器）中的μ子和反中微子，以提高IRAND的性能。通过IRAND-Sim-02包使用Geant4生成训练数据集（分析图像-时间概率密度，时间与光电阴极ID，光电阴极激活拓扑-编码事件的时空模式）。为了对模型进行评估，通过建立实时的Geant4-Python TCP套接字连接，自动生成了一个独立的测试数据集，反映了真实的反中微子与宇宙介子的比率。CNN模型的总体准确率达到99.97%，表明了事件分类的准确性。与传统的机器学习方法（如人工神经网络（ANN）和决策树模型）相比，本文提出的CNN在区分IBD事件和宇宙μ子背景方面具有更高的可靠性，特别是在类不平衡条件下，这凸显了我们的方法在改进核反应堆监测方面的巨大潜力，并代表了深度学习在基本粒子检测方面的重大进步。

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引用次数: 0

First demonstration of single event effects induced by secondary heavy ion beams at RAON 二次重离子束在RAON诱导的单事件效应的首次演示

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

Nuclear Engineering and Technology

Pub Date : 2026-01-06 DOI: 10.1016/j.net.2025.104105

Minsik Kwag , Dong Geon Kim , Cheolmin Ham , Kwang-Bok Lee , Seong Jae Pyeun , Mijung Kim , Jae Cheon Kim , Changwook Son , CheongSoo Lee , Donghyun Kwak , Eunhee Kim , Geonhee Oh , Sangjin Lee , Guen-Young Park , Taehyo Kim , Woojun Lee , Kyoungho Tshoo

The first experimental demonstration of SEE (single event effect) induced by secondary heavy ion beams was performed at RAON. The secondary beams were produced via the projectile-like fragmentation, and delivered to a commercial LM4050 precision voltage reference under high vacuum conditions using KoBRA. The transient perturbations in output voltage, typical of SEEs, were observed in the device, without permanent damage. This work demonstrates the feasibility of employing secondary beams, including rare isotopes, for SEE testing of semiconductor devices and establishes a proof-of-concept for future radiation hardness evaluations.

在RAON进行了二次重离子束诱导的单事件效应的首次实验验证。二次光束通过类似弹丸的破片产生，并在高真空条件下使用KoBRA交付给商用LM4050精密电压基准。在器件中观察到输出电压的瞬态扰动，典型的see，没有永久性损坏。这项工作证明了利用二次光束（包括稀有同位素）对半导体器件进行SEE测试的可行性，并为未来的辐射硬度评估建立了概念验证。

引用次数: 0

Analysis of tritium levels in drinking water around Korean nuclear power plants and a proposal for radioactivity standards in drinking water 韩国核电站周边饮用水氚含量分析及饮用水放射性标准提案

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

Nuclear Engineering and Technology

Pub Date : 2026-01-06 DOI: 10.1016/j.net.2025.104106

Na Young Lee , Tae Young Kong

Many countries have established national guidelines for radionuclides in drinking water based on recommendations from the International Commission on Radiological Protection and the World Health Organization (WHO). However, the Republic of Korea lacks comprehensive radiological standards for all drinking water sources, only addressing saline groundwater under the Drinking Water Management Act (DWMA). This study aims to enhance radiological standards by analyzing radioactive effluent discharges from Korean nuclear power plants (NPPs), particularly focusing on tritium activity levels and evaluating annual effective doses. From 2015 to 2024, data indicated that tritium made up the majority of radionuclides discharged, with pressurized heavy water reactors (PHWRs) releasing about nine times more tritium than pressurized water reactors (PWRs) in gaseous effluents. These effluents can affect groundwater and surface water, making tritium essential for monitoring drinking water quality near NPPs. The highest tritium concentration found in drinking water near PHWRs was 19.64 Bq/L, corresponding to only 0.258 μSv/y of the public dose, with a dose limit of 1 mSv/y. The study recommends that Korea adopt a guideline level of 7000 Bq/L for tritium in drinking water, in accordance with WHO standards, and suggests revising the DWMA to set specific radiological guidelines.

许多国家根据国际放射防护委员会和世界卫生组织（卫生组织）的建议制定了饮用水中放射性核素的国家准则。但是，大韩民国缺乏对所有饮用水源的全面放射性标准，仅根据《饮用水管理法》处理含盐地下水。这项研究的目的是通过分析韩国核电站（NPPs）的放射性废水排放来提高放射性标准，特别是关注氚活度水平和评估年有效剂量。从2015年到2024年，数据显示氚占排放放射性核素的大部分，压力重水反应堆（PHWRs）释放的气态流出物中的氚约为压力水反应堆（pwr）的9倍。这些流出物会影响地下水和地表水，因此氚对于监测核电站附近的饮用水质量至关重要。PHWRs附近饮用水中氚的最高浓度为19.64 Bq/L，仅相当于公共剂量的0.258 μSv/y，剂量限值为1 mSv/y。研究结果建议，根据世界卫生组织（WHO）的标准，将饮用水中的氚含量设定为7000 Bq/L，并修改《水环境管理条例》，制定具体的放射性标准。

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引用次数: 0

Comparative study on neutronic characteristics of cylindrical and three-petal fuel rod 圆柱形和三瓣燃料棒中子特性的比较研究

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

Nuclear Engineering and Technology

Pub Date : 2026-01-06 DOI: 10.1016/j.net.2026.104120

Deping Du , Dabin Sun , Jincheng Wang , Xunjian Che , Jianchuang Sun , Weihua Cai

To make up for deficiencies in neutronics calculation of 3-Pl-shaped fuel rods (TPF), further determine neutron transport characteristics of TPF in conventional assemblies. This paper uses DGA-OpenMC to build neutronic calculation models for cylindrical and petal-shaped fuel assemblies (CFA and TPFA) under different

V_{H_{2} O} / V_{U}

. It compares influences of fuel rod types and

V_{H_{2} O} / V_{U}

on neutronic characteristics. Results show the following. First, when

V_{H_{2} O} / V_{U}

is within [3.18, 7.38], k_∞ of CFA is 1342 ± 40pcm to 2125 ± 40pcm higher than that of TPFA, and flux distribution of CFA is more uniform. Analysis of nuclear reaction rates finds that fission nuclear reaction rate of CFA is higher, while resonance absorption nuclear reaction rate of TPFA is higher. Second, when

V_{H_{2} O} / V_{U}

increases, neutron energy spectrum of assemblies softens, and uniformity of flux distribution decreases. Data shows that when water uranium ratio increases from 3.18 to 7.38, f_R of CFA and TPFA increase by 1.22 %.

为了弥补3- pl型燃料棒（TPF）中子电子学计算的不足，进一步确定常规组件中TPF的中子输运特性。本文利用DGA-OpenMC建立了圆柱形和花瓣形燃料组件（CFA和TPFA）在不同VH2O/VU下的中子计算模型。比较了燃料棒类型和VH2O/VU对中子特性的影响。结果显示如下。首先，当VH2O/VU在[3.18,7.38]范围内时，CFA的k∞比TPFA高1342±40pcm ~ 2125±40pcm，且CFA的通量分布更加均匀。核反应速率分析发现，CFA的裂变核反应速率更高，而TPFA的共振吸收核反应速率更高。当VH2O/VU增大时，组件中子能谱软化，通量分布均匀性降低。数据表明，当水铀比从3.18增加到7.38时，CFA和TPFA的fR增加了1.22%。

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引用次数: 0

Optimizing pressurized-water reactor equilibrium cycle using a novel loading pattern encoding and rule-based genetic crossover operators 利用新型加载模式编码和基于规则的遗传交叉算子优化压水堆平衡循环

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.2026.104113

Khang Hoang Nhat Nguyen , Junyung Kim , Nicholas Rollins , Juan C. Luque-Gutierrez , Jason Hou , Svetlana Lawrence , Congjian Wang , Mohammad Abdo

This work presents an extended multibatch approach applied in a shuffling scheme optimization for the pressurized-water reactor equilibrium cycle using genetic algorithms (GAs). A new ruled-based GA crossover operator called inherited location and batch (ILB) was introduced to enhance offsprings reproduction efficiency specialized for the equilibrium cycle optimization problem. This approach was implemented within the Plant ReLoad Optimization (PRLO) framework and validated using a generic reactor model based on the AP1000 design, with core parameters calculated via the CASMO/SIMULATE software package. The ILB approach is then applied for both single- and multi-objective problems in maximizing cycle length and core average exposure while minimizing the average enrichment of the 57 fresh fuel assemblies per cycle. The optimal solutions are selected based on their dominance from all feasible solutions. This research identified three optimal solutions that satisfied safety constraints: the first minimizes feed enrichment costs with a cycle length of 338.8 days and core exposure of 25.39 MWd/MT, the second extends the cycle length to 361.2 days and core exposure of 26.84 MWd/MT using a 3.75 wt% average fuel enrichment, and the third balances both objectives with a cycle length of 349.6 days and core exposure of 25.82 MWd/MT with a slight enrichment increase compared to the first solution. Collectively, these findings underscore the efficiency and effectiveness of the proposed approach in achieving practical multiobjective optimal equilibrium cycle designs using GAs optimizer.

本文提出了一种扩展的多批方法，应用于利用遗传算法优化压水堆平衡循环的洗牌方案。针对平衡周期优化问题，提出了一种新的基于规则的遗传交叉算子ILB，以提高后代的繁殖效率。该方法在电厂重新装载优化（PRLO）框架内实现，并使用基于AP1000设计的通用反应堆模型进行验证，并通过CASMO/ simulation软件包计算核心参数。然后将ILB方法应用于单目标和多目标问题，即最大化循环长度和堆芯平均暴露，同时最小化每个循环57个新燃料组件的平均富集。根据最优解在所有可行解中的优势度选择最优解。本研究确定了满足安全约束的三种最佳解决方案：第一种方案将饲料浓缩成本降至最低，周期长度为338.8天，堆芯暴露量为25.39 MWd/MT；第二种方案将周期长度延长至361.2天，堆芯暴露量为26.84 MWd/MT，平均燃料富集量为3.75%；第三种方案平衡了两个目标，周期长度为349.6天，堆芯暴露量为25.82 MWd/MT，与第一种方案相比，浓缩量略有增加。总的来说，这些发现强调了所提出的方法在使用GAs优化器实现实际多目标最优平衡循环设计方面的效率和有效性。

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引用次数: 0

Integration of DICE and MELCOR for dynamic event tree analysis: Case study for RCS failure phenomena 基于DICE和MELCOR的动态事件树分析：RCS故障现象的案例研究

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.2026.104115

Dohun Kwon, Gyunyoung Heo

Dynamic Event Tree Analysis enhances NPP safety assessment by systematically introducing stochastic variability into deterministic simulations and explicitly representing operator actions, system availability, and temporal dependencies. Following the Fukushima accident, the importance of severe accident risk evaluation has grown, and in South Korea, Level 2 PSA is closely tied to safety objectives such as the LERF and Cs-137 release frequency. Physics-based codes such as MELCOR are widely used to support these analyses, yet their efficient integration with dynamic tools remains challenging.

This study presents a practical methodology for coupling the DICE platform with MELCOR 2.x using the Analytic Control Function (ACF). Unlike traditional external interfaces, ACF enables direct, bidirectional communication, reducing data-transfer overhead and improving scalability for large simulations. The coupled DICE–MELCOR framework automates scenario generation while capturing operator response times, system availability, and thermal-hydraulic behavior. A station blackout case study in a two-loop PWR demonstrates that the approach explicitly represents uncertainty and yields more realistic insights into accident progression.

The results show that ACF-based integration enhances Level 2 PSA fidelity by enabling scenario exploration that better reflects plant dynamics and operator interactions. This methodology provides a robust foundation for reevaluating severe accident management strategies and supporting regulatory safety goals.

动态事件树分析通过系统地将随机变异性引入确定性模拟，并明确表示操作员行为、系统可用性和时间依赖性，增强了核电站安全评估。福岛核事故发生后，严重事故风险评估的重要性不断提高，在韩国，二级PSA与安全目标密切相关，如LERF和Cs-137释放频率。基于物理的代码（如MELCOR）被广泛用于支持这些分析，但它们与动态工具的有效集成仍然具有挑战性。本研究提出了一种将DICE平台与MELCOR 2相结合的实用方法。x使用分析控制函数（ACF）。与传统的外部接口不同，ACF支持直接的双向通信，减少了数据传输开销，提高了大型模拟的可扩展性。耦合的DICE-MELCOR框架可以自动生成场景，同时捕获操作人员的响应时间、系统可用性和热液行为。一个双环压水堆的停电案例研究表明，该方法明确地代表了不确定性，并对事故进展产生了更现实的见解。结果表明，基于acf的集成可以通过场景探索更好地反映工厂动态和操作员互动，从而提高2级PSA的保真度。该方法为重新评估严重事故管理策略和支持监管安全目标提供了坚实的基础。

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引用次数: 0