Nuclear Engineering and Technology最新文献_第8页

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

Sandstone-type uranium mineralization coupled with extensional tectonics 砂岩型铀矿化与伸展构造相耦合

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.2025.104075

Bocheng Zhang , Zhibing Feng , Fengjun Nie , Chunlian Wang , Fei Xia , Li Jiang , Tengfei Ren , Jingyi Wang

While compressional tectonics has long been recognized as a significant factor in uranium mineralization, the role of extensional tectonics remains comparatively understudied. This investigation analyzes representative sandstone-hosted uranium provinces, including the Colorado Plateau (North America), the Agadez region (West Africa), the North China–Transbaikal region (Northeast Asia), and the Massif Central (Western Europe). Our systematic analysis reveals that extensional tectonics, building upon pre-existing rifting structures, amplify tectono-magmatic activity, which in turn exerts spatiotemporally control on uranium deposition and gives rise to diverse mineralization ages. Key structural elements within tectonic transition zones, such as uplifts, fault systems, and volcanism, play critical roles: uplifts and shallow-level faults govern the recharge and migration of supergene fluid, whereas deep-seated faults facilitate the transport of reductants (e.g., hydrocarbons) and magma. These deep pathways provide the essential thermal energy and additional components for uranium precipitation. Collectively, these processes collectively form high-relief transition zones that act as prime sites for uranium enrichment. In addition, multi-phase extensional events generate permeable conduits and thermal anomalies that are crucial for mobilizing and concentrating uranium from source rocks. This study provides an enhanced understanding of the genesis of sandstone-hosted uranium deposits and offers a theoretical framework for future exploration targeting.

虽然挤压构造长期以来被认为是铀矿化的重要因素，但伸展构造的作用研究相对较少。本研究分析了具有代表性的砂岩含铀省份，包括科罗拉多高原（北美）、阿加德兹地区（西非）、华北-外贝加尔地区（东北亚）和中部地块（西欧）。系统分析表明，在原有裂陷构造的基础上，伸展构造放大了构造-岩浆活动，从而对铀矿沉积产生时空控制作用，形成了不同的成矿年龄。构造过渡带中的关键构造要素，如隆升、断裂系统和火山作用，起着至关重要的作用：隆升和浅层断裂控制着表生流体的补给和运移，而深层断裂则促进还原剂（如碳氢化合物）和岩浆的输送。这些深层途径为铀沉淀提供了必需的热能和额外的成分。总的来说，这些过程共同形成了高起伏过渡区，作为铀浓缩的主要场所。此外，多期张拉事件会形成渗透管道和热异常，这对从烃源岩中动员和富集铀至关重要。该研究加深了对砂岩型铀矿床成因的认识，并为今后的找矿目标提供了理论框架。

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引用次数: 0

Research on internal exposure and assessment from food intake using a whole body counter and self-administered questionnaires 利用全身计数器和自我管理问卷对食物摄入的内部暴露和评估进行研究

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.2025.104071

Jieun Lee, HyoJin Kim, HeeJin Jang, Yong UK. Kye, Wol Soon Jo, Joo Yeon Song, Jeung Kee Kim, Mi Hee Jo, Chang Geun Lee, Yeong-Rok Kang

Radioactive nuclides can enter the human body through inhalation or ingestion, with internal exposure from food depending on the radionuclide type and intake. This study aimed to assess dietary radiological effect using whole body counting (WBC) measurements and self-administered food intake questionnaires. A survey was conducted on 105 people between July 31, 2023, and February 6, 2024. Food intake questionnaires analysis estimated the average internal exposure dose from ⁴⁰K due to food ingestion at 208.42 μSv/y, and from ¹³⁷Cs at 254.24 μSv/y. WBC detected only ⁴⁰K, while ¹³⁷Cs was undetectable. Internal exposure factors differed significantly by age, height, weight, body mass index, and whole-body index. The highest activity among men was 5012.7 Bq in their 20s, and among women, 2999.5 Bq in their 50s. Internal exposure from ingested food was negligible compared with the average annual natural background radiation dose of 2.4 mSv/y received by the general public. WBC measurements show that ⁴⁰K intake through food remains relatively constant, underscoring its role as a physiological marker, while the non-detection of anthropogenic radionuclides suggests minimal radiological risk from the current food supply.

放射性核素可通过吸入或摄入进入人体，根据放射性核素的种类和摄入量，可从食物中获得内部暴露。本研究旨在通过全身计数（WBC）测量和自我管理的食物摄入问卷来评估饮食的放射效应。这项调查是在2023年7月31日至2024年2月6日期间对105人进行的。食物摄入问卷分析估计，40K和137Cs的平均内暴露剂量分别为208.42 μSv/y和254.24 μSv/y。WBC仅检测到40K，而137Cs未检测到。内部暴露因素因年龄、身高、体重、体质指数和全身指数而有显著差异。男性在20多岁时的活跃度为5012.7 Bq，女性在50多岁时的活跃度为2999.5 Bq。与公众平均每年接受2.4毫西弗/年的自然本底辐射剂量相比，从食物中摄取的内部辐射可以忽略不计。白细胞测量显示，通过食物摄入的40K保持相对恒定，强调了其作为生理标志物的作用，而未检测到人为放射性核素表明当前食物供应的辐射风险最小。

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引用次数: 0

Enhancing CMFD acceleration in MOC-based direct transport code 增强基于moc的直接传输代码中的CMFD加速

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.2025.104074

Fathurrahman Setiawan, Siarhei Dzianisau, Deokjung Lee

The implementation of CMFD acceleration and recent enhancements in STREAM deterministic transport code are presented in this study. A comprehensive description of the two-level CMFD approach in STREAM is provided, including its parallelization strategies and iteration algorithms. The main performance improvement comes from adopting an improved odCMFD method, complemented with code optimization at the programming level. Numerical evaluations against various realistic core problems demonstrate that the adopted odCMFD significantly improve the efficiency and robustness of CMFD acceleration in STREAM, enabling stable and accurate simulations with coarser meshes and reduced computational time.

本研究介绍了CMFD加速的实现和STREAM确定性传输代码的最新增强。对STREAM中的两级CMFD方法进行了全面的描述，包括其并行化策略和迭代算法。主要的性能改进来自于采用改进的odCMFD方法，并辅以编程级别的代码优化。针对各种现实核心问题的数值评估表明，所采用的odCMFD显著提高了STREAM中CMFD加速的效率和鲁棒性，实现了更粗网格下稳定、准确的模拟，减少了计算时间。

引用次数: 0

A practical safeguardability evaluation framework and tool supporting SBD implementation for new nuclear facilities 支持新核设施实施SBD的实用安全性评估框架和工具

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

Nuclear Engineering and Technology

Pub Date : 2025-12-08 DOI: 10.1016/j.net.2025.104070

Bong Young Kim , Seong-Kyu Ahn

A safeguardability evaluation methodology was developed to support the implementation of safeguards by design (SBD) approach. Evaluation factors were derived and classified into quantitative and qualitative factors. The evaluation methodology comprises five steps. Step 1 involves defining a set of design information for the facility. Step 2 involves defining a set of safeguards measures for the facility. Step 3 involves setting the diversion time for each diversion pathway. Step 4 involves producing a fault tree and examining the diversion detection probability. Step 5 involves quantitative analysis of various diversion pathways and qualitative analysis. Moreover, a safeguardability evaluation tool (SET) capable of implementing these steps was developed. Whereas previous studies on proliferation resistance or safeguardability have mainly relied on qualitative or comparative analyses, this study introduced a structured and executable methodology that enables quantitative, scenario-based, and regulation-aligned evaluation of safeguardability. The implementation of this method in the SET provides a practical foundation for operationalizing the IAEA's SBD principle in both the design and regulatory review stages of new nuclear facilities, including advanced and non-traditional types.

开发了一种安全性评估方法，以支持设计保障（SBD）方法的实施。导出评价因子，并将其分为定量因子和定性因子。评价方法包括五个步骤。步骤1包括为设施定义一组设计信息。步骤2涉及为该设施定义一套保障措施。步骤3设置各导流路径的导流时间。步骤4生成故障树，检查导流检测概率。第五步是对各种导流途径进行定量分析和定性分析。此外，还开发了能够实施这些步骤的安全性评估工具（SET）。鉴于以往关于防扩散或安全性的研究主要依赖于定性或比较分析，本研究引入了一种结构化和可执行的方法，可以对安全性进行定量、基于场景和与法规一致的评估。该方法在SET中的实施为在包括先进和非传统类型在内的新核设施的设计和监管审查阶段实施原子能机构的SBD原则提供了实际基础。

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引用次数: 0