Nuclear Engineering and Technology最新文献_第7页

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。

{"title":"Enhanced fidelity of Monte Carlo coupled multi-physics simulations in the MCS code","authors":"Muhammad Imron , Deokjung Lee","doi":"10.1016/j.net.2025.104077","DOIUrl":"10.1016/j.net.2025.104077","url":null,"abstract":"<div><div>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.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104077"},"PeriodicalIF":2.6,"publicationDate":"2025-12-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787531","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

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。

{"title":"Seismic analyses of i-SMR CV supports employing a component mode synthesis technique","authors":"Jun-Yeop Lee , Dong-Hyeon Choi , Yoon-Suk Chang","doi":"10.1016/j.net.2025.104072","DOIUrl":"10.1016/j.net.2025.104072","url":null,"abstract":"<div><div>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.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104072"},"PeriodicalIF":2.6,"publicationDate":"2025-12-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787951","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

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。

{"title":"Sandstone-type uranium mineralization coupled with extensional tectonics","authors":"Bocheng Zhang , Zhibing Feng , Fengjun Nie , Chunlian Wang , Fei Xia , Li Jiang , Tengfei Ren , Jingyi Wang","doi":"10.1016/j.net.2025.104075","DOIUrl":"10.1016/j.net.2025.104075","url":null,"abstract":"<div><div>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.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104075"},"PeriodicalIF":2.6,"publicationDate":"2025-12-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787953","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

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。

{"title":"Research on internal exposure and assessment from food intake using a whole body counter and self-administered questionnaires","authors":"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","doi":"10.1016/j.net.2025.104071","DOIUrl":"10.1016/j.net.2025.104071","url":null,"abstract":"<div><div>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 <sup>40</sup>K due to food ingestion at 208.42 μSv/y, and from <sup>137</sup>Cs at 254.24 μSv/y. WBC detected only <sup>40</sup>K, while <sup>137</sup>Cs 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 <sup>40</sup>K 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.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104071"},"PeriodicalIF":2.6,"publicationDate":"2025-12-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787533","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

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。

{"title":"A practical safeguardability evaluation framework and tool supporting SBD implementation for new nuclear facilities","authors":"Bong Young Kim , Seong-Kyu Ahn","doi":"10.1016/j.net.2025.104070","DOIUrl":"10.1016/j.net.2025.104070","url":null,"abstract":"<div><div>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.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104070"},"PeriodicalIF":2.6,"publicationDate":"2025-12-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145787948","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

A comparative study on machine learning models for estimating cathode material compositions in black powders using prompt gamma-ray spectra 利用提示伽玛射线谱估计黑粉末正极材料成分的机器学习模型的比较研究

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

Nuclear Engineering and Technology

Pub Date : 2025-12-06 DOI: 10.1016/j.net.2025.104069

Yohan Lee , Byoungil Jeon , Soobin Lim

According to the rapid growth of the Lithium-ion battery (LIB) recycling industry, the demands for rapid and non-destructive analysis of black powder, the key product in this recycling process, has increased to enable effective recovery of valuable materials and the formulation of optimal recycling strategies. This study aims to evaluate the feasibility of a deep learning application that estimates the composition of valuable materials in black powder in prompt gamma-ray activation analysis (PGAA). Reference data for major target materials, Nickel, Cobalt, Manganese, and Iron, were acquired using the Four-circle single-crystal diffractometer at the HANARO research reactor, and synthetic datasets with varying counting statistics were generated for model training. To identify the most suitable model for PGAA-based composition estimation, we conducted a comparative analysis of six machine learning algorithms, including machine learning (Lasso, Decision Tree, XGBoost) and deep learning architectures (MLP, CNN, Transformer). Among them, the Transformer architecture demonstrated best performance, achieving an r² score of over 0.99 for all components. Furthermore, uncertainty quantification using deep ensembles confirmed that the model provides reliable confidence intervals, essential for industrial decision-making. These results demonstrate the promising potential of the deep learning method for effective and high-throughput battery recycling applications.

随着锂离子电池（LIB）回收行业的快速增长，对黑粉这一回收过程中的关键产品进行快速、无损分析的需求日益增加，以实现有价值材料的有效回收和优化回收策略的制定。本研究旨在评估在快速伽马射线激活分析（PGAA）中估计黑火药中有价值物质组成的深度学习应用的可行性。主要目标材料镍、钴、锰和铁的参考数据使用HANARO研究堆的四圆单晶衍射仪获取，并生成具有不同计数统计量的合成数据集用于模型训练。为了确定最适合基于pgaa的成分估计的模型，我们对六种机器学习算法进行了比较分析，包括机器学习（Lasso, Decision Tree, XGBoost）和深度学习架构（MLP， CNN, Transformer）。其中，Transformer体系结构表现出最好的性能，所有组件的r2得分都超过0.99。此外，使用深度集成的不确定性量化证实了该模型提供可靠的置信区间，这对工业决策至关重要。这些结果证明了深度学习方法在有效和高通量电池回收应用中的巨大潜力。

{"title":"A comparative study on machine learning models for estimating cathode material compositions in black powders using prompt gamma-ray spectra","authors":"Yohan Lee , Byoungil Jeon , Soobin Lim","doi":"10.1016/j.net.2025.104069","DOIUrl":"10.1016/j.net.2025.104069","url":null,"abstract":"<div><div>According to the rapid growth of the Lithium-ion battery (LIB) recycling industry, the demands for rapid and non-destructive analysis of black powder, the key product in this recycling process, has increased to enable effective recovery of valuable materials and the formulation of optimal recycling strategies. This study aims to evaluate the feasibility of a deep learning application that estimates the composition of valuable materials in black powder in prompt gamma-ray activation analysis (PGAA). Reference data for major target materials, Nickel, Cobalt, Manganese, and Iron, were acquired using the Four-circle single-crystal diffractometer at the HANARO research reactor, and synthetic datasets with varying counting statistics were generated for model training. To identify the most suitable model for PGAA-based composition estimation, we conducted a comparative analysis of six machine learning algorithms, including machine learning (Lasso, Decision Tree, XGBoost) and deep learning architectures (MLP, CNN, Transformer). Among them, the Transformer architecture demonstrated best performance, achieving an <em>r</em><sup>2</sup> score of over 0.99 for all components. Furthermore, uncertainty quantification using deep ensembles confirmed that the model provides reliable confidence intervals, essential for industrial decision-making. These results demonstrate the promising potential of the deep learning method for effective and high-throughput battery recycling applications.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104069"},"PeriodicalIF":2.6,"publicationDate":"2025-12-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145734731","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Enhancing SEU tolerance efficacy in advanced FinFET FPGA devices using system-level fine-grained spatial redundancy techniques 利用系统级细粒度空间冗余技术增强先进FinFET FPGA器件的SEU容差效率

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

Nuclear Engineering and Technology

Pub Date : 2025-12-04 DOI: 10.1016/j.net.2025.104047

Chang Cai , Hong-Jie Zeng , Ze-Qi Huang , Xue-Zhi Zheng , Yi Sun , Jing Zhang , Min-Chi Hu , Han-Tao Jing , Zhi-Xin Tan , Rui-Rui Fan , Jun Ge , Shu-Sheng Pan

This paper investigates the Single Event Upset (SEU) sensitivity, system-level hardening effectiveness, and potential applications of high-performance 16 nm Field Programmable Gate Arrays (FPGAs) in radiation environments. Representative circuits incorporating flip-flops and configured arithmetic logic units were specifically designed using FPGA internal resources. This integration introduces extra upset errors due to the additional utilization of arithmetic logics, contributing to a better understanding of SEU sensitivity in FPGA-based circuits within actual application designs. The irradiation tests were conducted to evaluate the SEU sensitivity of D flip-flops (DFFs) and Configuration Memories (CRAMs) under various application conditions. The results indicate that Fine-Grained (FG) Triple Modular Redundancy (TMR) circuits play a critical role in achieving high SEU tolerance, whereas general TMR hardening circuits often prove ineffective in most experiments, even with triplicated flip-flops. FG TMR circuits were developed to address the limitations of general TMR circuits, achieving SEU tolerance improvements by three orders of magnitude for output protection. Notably, FG TMR circuits showed no global signal-induced failures during proton irradiation tests. Furthermore, these system-level radiation tolerance designs present promising applications for Commercial Off-The-Shelf (COTS) devices in spaceflight and ground accelerator facility.

本文研究了高性能16nm现场可编程门阵列（fpga）在辐射环境中的单事件扰动（SEU）灵敏度、系统级硬化效率和潜在应用。利用FPGA内部资源，设计了包含触发器和配置算术逻辑单元的代表性电路。由于算术逻辑的额外利用，这种集成引入了额外的干扰误差，有助于在实际应用设计中更好地理解基于fpga的电路中的SEU灵敏度。通过辐照试验，评价了D触发器（dff）和组态存储器（cram）在不同应用条件下的SEU敏感性。结果表明，细粒度（FG）三模冗余（TMR）电路在实现高SEU容限方面发挥了关键作用，而一般的TMR硬化电路在大多数实验中往往被证明是无效的，即使是三次触发器。FG TMR电路的开发是为了解决一般TMR电路的局限性，实现了输出保护的SEU容差提高了三个数量级。值得注意的是，在质子辐照测试中，FG TMR电路显示没有全局信号诱导故障。此外，这些系统级辐射容限设计为航天和地面加速器设施中的商用现货（COTS）设备提供了有前途的应用。

{"title":"Enhancing SEU tolerance efficacy in advanced FinFET FPGA devices using system-level fine-grained spatial redundancy techniques","authors":"Chang Cai , Hong-Jie Zeng , Ze-Qi Huang , Xue-Zhi Zheng , Yi Sun , Jing Zhang , Min-Chi Hu , Han-Tao Jing , Zhi-Xin Tan , Rui-Rui Fan , Jun Ge , Shu-Sheng Pan","doi":"10.1016/j.net.2025.104047","DOIUrl":"10.1016/j.net.2025.104047","url":null,"abstract":"<div><div>This paper investigates the Single Event Upset (SEU) sensitivity, system-level hardening effectiveness, and potential applications of high-performance 16 nm Field Programmable Gate Arrays (FPGAs) in radiation environments. Representative circuits incorporating flip-flops and configured arithmetic logic units were specifically designed using FPGA internal resources. This integration introduces extra upset errors due to the additional utilization of arithmetic logics, contributing to a better understanding of SEU sensitivity in FPGA-based circuits within actual application designs. The irradiation tests were conducted to evaluate the SEU sensitivity of D flip-flops (DFFs) and Configuration Memories (CRAMs) under various application conditions. The results indicate that Fine-Grained (FG) Triple Modular Redundancy (TMR) circuits play a critical role in achieving high SEU tolerance, whereas general TMR hardening circuits often prove ineffective in most experiments, even with triplicated flip-flops. FG TMR circuits were developed to address the limitations of general TMR circuits, achieving SEU tolerance improvements by three orders of magnitude for output protection. Notably, FG TMR circuits showed no global signal-induced failures during proton irradiation tests. Furthermore, these system-level radiation tolerance designs present promising applications for Commercial Off-The-Shelf (COTS) devices in spaceflight and ground accelerator facility.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104047"},"PeriodicalIF":2.6,"publicationDate":"2025-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145692860","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Improving hydration resistance of gadolinium-based burnable absorbers via cerium oxide additions 添加氧化铈提高钆基可燃吸收剂的抗水化性能

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

Nuclear Engineering and Technology

Pub Date : 2025-12-04 DOI: 10.1016/j.net.2025.104067

Hyeong Jin Kim, Hyeongju Bae, Ho Jin Ryu

The hydration behavior of gadolinium oxide (Gd₂O₃) under high-temperature water conditions presents a significant challenge for the development of soluble-boron-free small modular reactor (SMR) fuels. To overcome this issue, we investigated cerium oxide (CeO₂) additions to improve the hydration resistance of Gd₂O₃. Pellets containing 0–25 at.% Ce were exposed to pressurized water at 200 °C, 1.5 MPa, for 48 h. Gd₂O₃ pellets are originally monoclinic under 1600 °C sintering temperature, whereas CeO₂ additions progressively suppress the phase transformation; at 15 at.% or higher Ce doping, a single cubic phase forms. XRD showed that undoped Gd₂O₃ fully hydrates, whereas specimens with 15 at.% or higher Ce doping retain the cubic structure with no detectable hydroxides. FT-IR results also provide evidence of hydration resistance of Ce-doped Gd₂O₃, by vanishing Gd-O-H bands with the Ce addition. XPS indicated that Ce ions are predominantly Ce⁴⁺ in 15 at.% or higher Ce-doped Gd₂O₃, suggesting that Ce⁴⁺ substitution on Gd³⁺ sites prevents oxygen-vacancy-assisted hydroxylation. Conversely, a lower Ce⁴⁺ fraction in pellets sintered in an Ar atmosphere correlated with an increased hydration tendency. These results indicate that 15 at.% or higher Ce doping stabilizes the cubic phase of Gd₂O₃ and completely suppresses hydration under the tested conditions, as a result of a reduced oxygen vacancy concentration.

高温水条件下氧化钆（Gd2O3）的水化行为是开发可溶无硼小型模块化反应堆（SMR）燃料的一个重大挑战。为了克服这一问题，我们研究了添加氧化铈（CeO2）来提高Gd2O3的抗水化性能。含有0-25 at的弹丸。% Ce在200℃，1.5 MPa的高压水中暴露48 h。在1600℃烧结温度下，Gd2O3球团最初是单斜的，而CeO2的加入逐渐抑制了相变；15点。%或更高的Ce掺杂，形成单立方相。XRD结果表明，未掺杂的Gd2O3完全水化；%或更高的Ce掺杂保留了立方结构，没有检测到氢氧化物。FT-IR结果还通过Ce的加入使Gd-O-H带消失，提供了Ce掺杂Gd2O3的水化阻力的证据。XPS表明，15at中Ce离子以Ce4+为主。%或更高的ce掺杂Gd2O3，表明在Gd3+位点上的Ce4+取代阻止了氧空位辅助羟基化。相反，在Ar气氛中烧结的球团中Ce4+分数越低，其水化倾向越强。这些结果表明15 at。%或更高的Ce掺杂稳定了Gd2O3的立方相，在测试条件下，由于氧空位浓度降低，完全抑制了水化作用。

{"title":"Improving hydration resistance of gadolinium-based burnable absorbers via cerium oxide additions","authors":"Hyeong Jin Kim, Hyeongju Bae, Ho Jin Ryu","doi":"10.1016/j.net.2025.104067","DOIUrl":"10.1016/j.net.2025.104067","url":null,"abstract":"<div><div>The hydration behavior of gadolinium oxide (Gd<sub>2</sub>O<sub>3</sub>) under high-temperature water conditions presents a significant challenge for the development of soluble-boron-free small modular reactor (SMR) fuels. To overcome this issue, we investigated cerium oxide (CeO<sub>2</sub>) additions to improve the hydration resistance of Gd<sub>2</sub>O<sub>3</sub>. Pellets containing 0–25 at.% Ce were exposed to pressurized water at 200 °C, 1.5 MPa, for 48 h. Gd<sub>2</sub>O<sub>3</sub> pellets are originally monoclinic under 1600 °C sintering temperature, whereas CeO<sub>2</sub> additions progressively suppress the phase transformation; at 15 at.% or higher Ce doping, a single cubic phase forms. XRD showed that undoped Gd<sub>2</sub>O<sub>3</sub> fully hydrates, whereas specimens with 15 at.% or higher Ce doping retain the cubic structure with no detectable hydroxides. FT-IR results also provide evidence of hydration resistance of Ce-doped Gd<sub>2</sub>O<sub>3</sub>, by vanishing Gd-O-H bands with the Ce addition. XPS indicated that Ce ions are predominantly Ce<sup>4+</sup> in 15 at.% or higher Ce-doped Gd<sub>2</sub>O<sub>3</sub>, suggesting that Ce<sup>4+</sup> substitution on Gd<sup>3+</sup> sites prevents oxygen-vacancy-assisted hydroxylation. Conversely, a lower Ce<sup>4+</sup> fraction in pellets sintered in an Ar atmosphere correlated with an increased hydration tendency. These results indicate that 15 at.% or higher Ce doping stabilizes the cubic phase of Gd<sub>2</sub>O<sub>3</sub> and completely suppresses hydration under the tested conditions, as a result of a reduced oxygen vacancy concentration.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104067"},"PeriodicalIF":2.6,"publicationDate":"2025-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145734677","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Extension of the formula between reactivity and concentrations of fissile and non-fissile nuclide in the fuel salt for thermal neutron spectrum molten salt reactors 热中子谱熔盐堆燃料盐中可裂变和不可裂变核素浓度与反应性关系式的推广

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

Nuclear Engineering and Technology

Pub Date : 2025-12-04 DOI: 10.1016/j.net.2025.104068

Changqing Yu , Guifeng Zhu , Jintong Cao , Yang Zou , Rui Yan , Xiaohan Yu

Due to the unique properties of liquid fuel in molten salt reactors (MSRs), reactor reactivity is directly correlated with the fuel salt composition. Previous studies have established and verified a linear relationship between reactivity and the inverse of fissile nuclide concentration in thermal spectrum MSRs. This paper aims to expand the relationship to non-fissile nuclides. Non-fissile nuclides, including carrier salts, and fission products, are widely distributed within MSRs. Unlike fissile nuclides, increasing the concentration of these non-fissile isotopes reduces reactivity. By applying the "1/v law" for neutron absorption cross-sections in the thermal neutron energy range, we demonstrate that reactivity is linearly related to the concentration of these non-fissile isotopes, in contrast to fissile ones. Furthermore, a generalized relationship expressing reactivity as a function of both fissile and non-fissile nuclide concentrations is developed and validated. This formula enables the calculation of reactor reactivity for any fuel salt composition without requiring repeated neutron transport calculations, offering significant potential for criticality and burnup calculations in MSRs.

由于熔盐堆中液体燃料的独特性质，反应堆的反应性与燃料盐组成直接相关。以往的研究已经在热谱MSRs中建立并验证了反应性与可裂变核素浓度反比之间的线性关系。本文的目的是将这种关系扩展到不可裂变的核素。非裂变核素，包括载体盐和裂变产物，广泛分布在msr内。与易裂变核素不同，增加这些非易裂变同位素的浓度会降低反应性。通过对热中子能量范围内的中子吸收截面应用“1/v定律”，我们证明了反应性与这些不可裂变同位素的浓度呈线性关系，而与可裂变同位素的浓度相反。此外，一个广义的关系表示反应性作为一个函数的可裂变和不可裂变核素浓度被开发和验证。该公式可以计算任何燃料盐成分的反应堆反应性，而不需要重复的中子输运计算，为msr中的临界和燃耗计算提供了重要的潜力。

{"title":"Extension of the formula between reactivity and concentrations of fissile and non-fissile nuclide in the fuel salt for thermal neutron spectrum molten salt reactors","authors":"Changqing Yu , Guifeng Zhu , Jintong Cao , Yang Zou , Rui Yan , Xiaohan Yu","doi":"10.1016/j.net.2025.104068","DOIUrl":"10.1016/j.net.2025.104068","url":null,"abstract":"<div><div>Due to the unique properties of liquid fuel in molten salt reactors (MSRs), reactor reactivity is directly correlated with the fuel salt composition. Previous studies have established and verified a linear relationship between reactivity and the inverse of fissile nuclide concentration in thermal spectrum MSRs. This paper aims to expand the relationship to non-fissile nuclides. Non-fissile nuclides, including carrier salts, and fission products, are widely distributed within MSRs. Unlike fissile nuclides, increasing the concentration of these non-fissile isotopes reduces reactivity. By applying the \"1/v law\" for neutron absorption cross-sections in the thermal neutron energy range, we demonstrate that reactivity is linearly related to the concentration of these non-fissile isotopes, in contrast to fissile ones. Furthermore, a generalized relationship expressing reactivity as a function of both fissile and non-fissile nuclide concentrations is developed and validated. This formula enables the calculation of reactor reactivity for any fuel salt composition without requiring repeated neutron transport calculations, offering significant potential for criticality and burnup calculations in MSRs.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 4","pages":"Article 104068"},"PeriodicalIF":2.6,"publicationDate":"2025-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145734728","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0