Nuclear Engineering and Technology最新文献_第7页

Optimal passivation process for improved spectroscopic grade CdMnTeSe single crystals based on chromic acid 基于铬酸的改进光谱级CdMnTeSe单晶的最佳钝化工艺

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-03-17 DOI: 10.1016/j.net.2025.103577

Jiwon Seo , Seungho Song , Jangwon Byun , Chaewon Yoon , Taejoon Mo , Younghak Kim , Hansoo Kim , Jung-Yeol Yeom , Beomjun Park

引用次数: 0

The application of Kriging model for three-dimensional core power distribution calibration Kriging模型在三维堆芯功率分配标定中的应用

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-03-17 DOI: 10.1016/j.net.2025.103591

Tien-Tso Lee, Wu-Hsiung Tung

{"title":"The application of Kriging model for three-dimensional core power distribution calibration","authors":"Tien-Tso Lee, Wu-Hsiung Tung","doi":"10.1016/j.net.2025.103591","DOIUrl":"10.1016/j.net.2025.103591","url":null,"abstract":"<div><div>The safety operation of a nuclear reactor relies on knowing the core power distributions as accurately as possible. PWR adapt the calculated power distributions to obtain accurate power distributions, which requires knowing the calibration factors for the calculated powers of each fuel bundle in the core. The calibration factors are obtained by comparing the measured reaction rates and the calculated reaction rates at the instrumented locations in the core. For the fuel bundles position that do not have measurement data, their calibration factors shall be inferred by using the calibration factor of the instrumented bundles nearby. In this study, we propose using Kriging model to fit the calibration factors of the instrumented bundles and then predict the calibration factors for the un-instrumented bundles. To verify the correctness of the model, we employed a method of repeated random sampling from the dataset to validate the model. After expanding the samples in each group, which originally contained only one plane, to include two or three planes, it was observed that the average RMSE value, as defined by cross-validation, not only significantly decreased but also showed a marked improvement in the predicted calibration factor for most of the validated samples.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 8","pages":"Article 103591"},"PeriodicalIF":2.6,"publicationDate":"2025-03-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143681682","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Simulating nuclear fuel inspections: Enhancing reliability through synthetic data 模拟核燃料检验：通过合成数据提高可靠性

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-03-15 DOI: 10.1016/j.net.2025.103571

J. Knotek , J. Blažek , M. Kopeć

{"title":"Simulating nuclear fuel inspections: Enhancing reliability through synthetic data","authors":"J. Knotek , J. Blažek , M. Kopeć","doi":"10.1016/j.net.2025.103571","DOIUrl":"10.1016/j.net.2025.103571","url":null,"abstract":"<div><div>Visual inspection of nuclear fuel assemblies is critical for assessing fuel reliability and ensuring safe operation. However, the sensitivity of real inspection data, along with its inflexibility and high collection costs, limits its use for research and development (R&D) tasks. These challenges hinder the ability to test and validate new inspection methodologies, making innovation slow and expensive. To address these limitations, we propose the development of synthetic nuclear fuel datasets that simulate fuel assembly inspections. These data sets replicate various defects and degradations in fuel assemblies, providing a controlled environment for hypothesis testing, operator training, and the evaluation of automated inspection techniques. Unlike real-world data, synthetic data offers the advantage of known ground-truth parameters, allowing for rigorous testing and validation. This approach enables the continuous development of inspection technologies, regardless of hardware availability and operational outages in nuclear facilities. By reducing the reliance on costly real-world experiments, synthetic data offers a scalable and flexible solution for the advancement of nuclear fuel inspection methods.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 8","pages":"Article 103571"},"PeriodicalIF":2.6,"publicationDate":"2025-03-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143682204","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

RUCAS: Software for assessing radiological risk to the public in metallic radioactive waste recycling from decommissioning nuclear facilities RUCAS：用于评估从退役核设施回收金属放射性废物对公众的辐射风险的软件

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-03-14 DOI: 10.1016/j.net.2025.103585

Ugyu Jeong , Hyeongjin Byeon , Jaeyeong Park

引用次数: 0

Adaptive probabilistic estimation of chromium coating thickness for nuclear fuel cladding using non-parametric regression with ECT sensors 基于非参数回归和ECT传感器的核燃料包层铬涂层厚度自适应概率估计

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-03-14 DOI: 10.1016/j.net.2025.103586

Jaebeom Lee , Hoyoung Kim , Jeong Won Park , Daegyun Ko , Hun Jang , Wonjae Choi

{"title":"Adaptive probabilistic estimation of chromium coating thickness for nuclear fuel cladding using non-parametric regression with ECT sensors","authors":"Jaebeom Lee , Hoyoung Kim , Jeong Won Park , Daegyun Ko , Hun Jang , Wonjae Choi","doi":"10.1016/j.net.2025.103586","DOIUrl":"10.1016/j.net.2025.103586","url":null,"abstract":"<div><div>To prevent the catastrophic failure of nuclear power plants following unexpected massive earthquakes and subsequent cooling system collapses, various studies have been conducted on nuclear fuel cladding coating. Consequently, measuring the coating thickness has become crucial, leading to the development of eddy current testing (ECT) sensor-based measurement technologies. These technologies typically extract meaningful features from measured signals and employ pre-built functions to correlate these features with the coating thickness, often using linear or polynomial regressions. However, these regressions can be overly simplistic, yielding inaccurate results. Recently, artificial intelligence has been explored to better model the relationship between the features and thickness. However, many studies on sensor development have not gathered sufficient data to construct deep-learning-based models. In this paper, a non-parametric regression-based regression technique is proposed, which outperforms traditional methods, even with limited data. Unlike traditional regression, which requires manually determining the best-fit order, the proposed method adapts automatically to data characteristics, eliminating the need for expert intervention. Furthermore, a probabilistic regression concept is introduced to account for various uncertainties that have not been addressed in previous related research. The effectiveness and adaptability of the proposed method were validated by applying it to real ECT data for thickness estimation.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 8","pages":"Article 103586"},"PeriodicalIF":2.6,"publicationDate":"2025-03-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143682205","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Experimental study and sub-channel analysis on the transverse mixing of the helical cruciform fuel assembly 螺旋十字形燃料组件横向混合的实验研究及子通道分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-03-14 DOI: 10.1016/j.net.2025.103587

Qi Zhang , Zhenhai Liu , Yile Zhang , Hua Pang , Mengke Cai , Zhenhan Hong , Guangliang Yang , Haoyu Wang , Li Liu , Yao Xiao , Hanyang Gu

{"title":"Experimental study and sub-channel analysis on the transverse mixing of the helical cruciform fuel assembly","authors":"Qi Zhang , Zhenhai Liu , Yile Zhang , Hua Pang , Mengke Cai , Zhenhan Hong , Guangliang Yang , Haoyu Wang , Li Liu , Yao Xiao , Hanyang Gu","doi":"10.1016/j.net.2025.103587","DOIUrl":"10.1016/j.net.2025.103587","url":null,"abstract":"<div><div>The helical cruciform fuel (HCF) is characterized as self-mixing and self-supporting, which has promising applications in advanced nuclear power devices. In the presented work, the transverse mixing behaviors of the 4 × 4 HCF assembly with the Reynolds number scope of 5.90 × 10<sup>2</sup> to 1.13 × 10<sup>4</sup> were investigated by mixing experiment and sub-channel analysis. The wire-mesh sensor (WMS) device for the complex-structured rod bundle channel was designed, which was utilized for the concentration measurement in the range of 0.01352 mol/L to 0.02916 mol/L. The one-way mixing at rod gap type Ⅰ and two-way mixing at rod gap type ⅠⅠ were revealed by the evolution of sub-channel concentration profile along the axial height of HCF assembly. The mixing coefficient of the HCF assembly was found to be a geometry depended constant, which was 0.022 for the 4 × 4 HCF assembly. It is confirmed that the transverse mixing of HCF assembly is dominant by flow sweeping effect rather than the turbulent mixing. The flow sweeping mixing model for the HCF assembly was developed, which involves two sets of momentum equations. In general, the presented work provides the fundamental experimental data and applicable mixing model for the development of sub-channel code for HCF assembly.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103587"},"PeriodicalIF":2.6,"publicationDate":"2025-03-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143776931","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Research on key technologies for early warning-position-angle monitoring and diagnosis of nuclear-grade pipeline leaks 核级管道泄漏预警位角监测与诊断关键技术研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-03-12 DOI: 10.1016/j.net.2025.103583

Guohua Wu , Jun Ling , Yuan Diping , Sheng Fang , Wenlin Wang , Yi Zhang

{"title":"Research on key technologies for early warning-position-angle monitoring and diagnosis of nuclear-grade pipeline leaks","authors":"Guohua Wu , Jun Ling , Yuan Diping , Sheng Fang , Wenlin Wang , Yi Zhang","doi":"10.1016/j.net.2025.103583","DOIUrl":"10.1016/j.net.2025.103583","url":null,"abstract":"<div><div>Nuclear power plants (NPPs) are complex systems where most accidents stem from equipment failures. When such failures occur, personnel often struggle to identify the root cause accurately, promptly, and effectively, which can lead to worsening conditions and potential radioactive leaks. To reduce the risk of coolant loss accidents, it is crucial for NPPs to develop robust leakage monitoring systems that can control the spread of harmful consequences and improve overall safety. Although researchers have made significant strides in developing online pipeline leak detection systems, challenges remain, particularly in providing sufficient early warning information and accurately diagnosing the exact location of pipeline ruptures. To address these issues, this paper introduces an advanced monitoring and diagnostic method that combines threshold techniques with qualitative trend analysis to offer early warnings of nuclear-grade pipeline leaks. This method establishes a comprehensive \"early warning - location - angle\" monitoring and diagnostic framework. Specifically, the combined use of threshold methods and qualitative trend analysis enhances monitoring sensitivity, while a novel sensor positioning technique improves the accuracy of detecting abnormal locations, achieving precise localization within 0.275 m. Additionally, a machine learning-based technique is proposed for diagnosing breach angles, achieving a 95 % accuracy rate in monitoring breach angles.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 8","pages":"Article 103583"},"PeriodicalIF":2.6,"publicationDate":"2025-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143725235","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Radioactivity evaluation induced by beamline components in the ocular proton treatment 眼质子治疗中束线成分诱导的放射性评价

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-03-12 DOI: 10.1016/j.net.2025.103582

Dong-san Kang , Yeseul Kim , Sangseok Ha , Sangrok Kim , Wonmo Sung

{"title":"Radioactivity evaluation induced by beamline components in the ocular proton treatment","authors":"Dong-san Kang , Yeseul Kim , Sangseok Ha , Sangrok Kim , Wonmo Sung","doi":"10.1016/j.net.2025.103582","DOIUrl":"10.1016/j.net.2025.103582","url":null,"abstract":"<div><div>Using Geant4/TOPAS and FISPACT-II simulations, we built an ocular proton treatment system and performed activation analysis. We evaluated two scenarios: a simple one assuming 15 years of operation and a detailed one based on 10 patients per day, each receiving a 1-min beam irradiation with a 30-min cooling period. To assess if the radionuclide mixture was below the clearance level, we calculated the relative activity ratio as the sum of <em>C</em><sub><em>i</em></sub><em>/C</em><sub><em>L,i</em></sub>, where <em>C</em><sub><em>i</em></sub> is the concentration and <em>C</em><sub><em>L,i</em></sub> is the clearance concentration level of radionuclide <em>i</em>, based on two national reports. In the simple scenario, the inner ring of ion chamber, the metallic component closest to the proton source, showed a relative activity ratio exceeding 7.8 × 10<sup>4</sup> at the end of the treatment. The detailed scenario resulted in a relative activity ratio of 5.6 × 10<sup>3</sup> at the end of the treatment, which is about 10 times lower than the simple scenario. Main long-lived radionuclides, such as <sup>195</sup>Au (1.07 × 10<sup>2</sup> Bq/g), <sup>194</sup>Hg (0.73 Bq/g), and <sup>193</sup>Pt (1.66 × 10 Bq/g), were identified as crucial in long-term disposal planning. This study shows that the simulations can identify activation-sensitive components, aiding in disposal planning.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 8","pages":"Article 103582"},"PeriodicalIF":2.6,"publicationDate":"2025-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143682574","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

SAMG-based human reliability analysis method in support of level 2 PSA. Part II: Methodology and application 基于samg的二级PSA人的可靠性分析方法。第二部分：方法和应用

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-03-09 DOI: 10.1016/j.net.2025.103578

Jaewhan Kim , Jaehyun Cho , Sooyong Park , Jinkyun Park

{"title":"SAMG-based human reliability analysis method in support of level 2 PSA. Part II: Methodology and application","authors":"Jaewhan Kim , Jaehyun Cho , Sooyong Park , Jinkyun Park","doi":"10.1016/j.net.2025.103578","DOIUrl":"10.1016/j.net.2025.103578","url":null,"abstract":"<div><div>The second part of this series provides the methodological framework of the developed SAM-L2HRA method for evaluating severe accident management (SAM) strategies utilizing portable equipment for preventing and mitigating severe accidents. SAM-L2HRA uses two fundamental approaches for the evaluation of SAM strategies: a time-based approach and a task-based approach. In the time-based approach, a time uncertainty analysis is performed based on the convolution of two distributions of time available and time required for detailed quantification. Time elements in the time uncertainty analysis include the distribution of time available with consideration of phenomenological uncertainty, the time elapsed (or required), and its distribution for an individual SAM strategy. In the task-based analysis, the human error potential or decision-making likelihood associated with a SAM strategy is assessed. The task-based approach deals with the availability of essential information, evaluation of potential negative impacts associated with the strategy and their effects on decision-making likelihood, and the reliability of implementation activities between distributed organizations. The SAM-L2HRA method can be used to identify the major task characteristics and vulnerabilities associated with a SAM strategy that impede high reliability of strategy implementation, as well as to quantify the probability of failure to perform and complete the strategy.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 8","pages":"Article 103578"},"PeriodicalIF":2.6,"publicationDate":"2025-03-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143839580","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

Detachable and robust three-dimensionally printed support structures for optical coupling of lightguide to photomultiplier tube 光导管与光电倍增管光学耦合的可拆卸和坚固的三维印刷支撑结构

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-03-08 DOI: 10.1016/j.net.2025.103579

Sang Yong Kim, Ji Young Choi, Kyung Kwang Joo

{"title":"Detachable and robust three-dimensionally printed support structures for optical coupling of lightguide to photomultiplier tube","authors":"Sang Yong Kim, Ji Young Choi, Kyung Kwang Joo","doi":"10.1016/j.net.2025.103579","DOIUrl":"10.1016/j.net.2025.103579","url":null,"abstract":"<div><div>This study introduces a novel optical coupling structure for scintillation detectors, which are critical tools in high-energy physics, nuclear engineering, medical physics, and radiation applications. The proposed design focuses on optimizing optical coupling efficiency, mechanical strength, stability, and maintainability between a light guide and a photomultiplier tube (PMT), particularly for large-area scintillators. Accordingly, a customized support structure was fabricated using fused deposition modeling to precisely align and secure the light guide and PMT. A fabricated structure using carbon-fiber-reinforced polyethylene terephthalate glycol filament was equipped with an interlocking mechanism enabling easy assembly and disassembly. To assess the long-term performance and stability of different optical coupling techniques, we evaluated the effects of reactor neutrino exposure and environmental conditions on optical transmittance. Specifically, ultraviolet–visible spectroscopy was performed on optical cement exposed to a reactor neutrino exposure environment for 12 years, revealing a decline in optical performance likely due to oxidation, decomposition, and the formation of color centers or defects. Additionally, the transmittance spectra of optical grease and cement cured under controlled temperature and humidity were compared. Finally, the impact of an air gap between the light guide and PMT, caused by insufficient optical grease application, on the cosmic ray background charge distribution was analyzed. In the future, this study could contribute to improving the better optical coupling structure between light guide and PMT for the development of radiation measurement technology.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 8","pages":"Article 103579"},"PeriodicalIF":2.6,"publicationDate":"2025-03-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143839578","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