Progress in Nuclear Energy最新文献_第6页

Neutronics evaluation for coating layers of the blanket system in a hybrid fusion-fission reactor 混合聚变裂变反应堆包层系统包层的中子学评价

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-09 DOI: 10.1016/j.pnucene.2025.106010

Natália G.P. L. Oliveira, Claubia Pereira

{"title":"Neutronics evaluation for coating layers of the blanket system in a hybrid fusion-fission reactor","authors":"Natália G.P. L. Oliveira, Claubia Pereira","doi":"10.1016/j.pnucene.2025.106010","DOIUrl":"10.1016/j.pnucene.2025.106010","url":null,"abstract":"<div><div>A hybrid fusion-fission reactor (FFH) can be understood as a significant source of fusion neutrons combined with a layer of fissile fuel, which can be used both for the breeding of fissile material and for the transmutation of high-level radioactive waste (HLW), such as the long half-life actinide elements. To evaluate an FFH reactor for the transmutation of reprocessed fuel, two models of an FFH are analyzed: a simpler model for the plasma chamber without the representation of the divertor component (Model 1) and a model with the divertor component represented in a simplified form (Model 2). This work aims to analyze changes in the spectrum of fusion neutrons that reach the transmutation layers (TL) position in the two simulated FFH reactor models, investigating the albedo coefficients calculated through the input and output currents in the beryllium coating layers, heat sink, and tritium production. Differences in the interactions of neutrons with these three layers are observed between the models, initially caused by the scattering of fusion neutrons with the W nuclei of the diverter's plasma facing components (PFC), which can ultimately impact the transmutation rate and energy multiplication between models.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106010"},"PeriodicalIF":3.2,"publicationDate":"2025-09-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145020055","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 nuclear emergency response through wind data assimilation: a particle filter-based approach combined with terrain-modified Gaussian plume model 通过风数据同化增强核应急响应：基于粒子滤波的方法与地形修正高斯羽流模型相结合

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-09 DOI: 10.1016/j.pnucene.2025.106024

Maryna Batur , Reha Metin Alkan , Himmet Karaman

引用次数: 0

Random media criticality analysis using randomized Fourier series and incomplete randomized Weierstrass function 随机傅立叶级数和不完全随机Weierstrass函数的随机媒介临界性分析

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-08 DOI: 10.1016/j.pnucene.2025.106007

Taro Ueki

{"title":"Random media criticality analysis using randomized Fourier series and incomplete randomized Weierstrass function","authors":"Taro Ueki","doi":"10.1016/j.pnucene.2025.106007","DOIUrl":"10.1016/j.pnucene.2025.106007","url":null,"abstract":"<div><div>Criticality analysis of continuously-mixed random media is essential for the safe retrieval of fuel debris. A key first approach to it is to establish some Monte Carlo (MC) method for the random media characterized by a single-mode inverse power law power spectrum, modelled using the Incomplete Randomized Weierstrass Function (IRWF). However, image analysis reveals that the power spectrum of an oxide debris mock-up cannot be fully explained by a single contributing factor. This has led to the search for a new randomized function with a power spectrum capable of capturing more complexity than a single-mode law. To this end, a function called a Randomized Fourier Series (RFS) has been developed to represent a power spectrum of arbitrary shape. Here, the repertoire of RFS is so broad that it is capable of representing power spectra obtained from measurements, includes a phase-randomized form of the Karhunen-Loève expansion of Brownian motion, and allows reactor physicists and criticality safety engineers to analyse various scenarios. Numerical results are presented for the fluctuation of neutron effective multiplication factor (k<sub>eff</sub>) over the random media replicas independently generated via RFS. The scale of RFS is linear, while that of IRWF is logarithmic, therefore numerical results are also presented for IRWF to identify a spectral range most influential on the k<sub>eff</sub> fluctuation.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106007"},"PeriodicalIF":3.2,"publicationDate":"2025-09-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145011176","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

Numerical simulation of the effect of micro-layer slopes on bubble growth and heat transfer during nucleate pool boiling 微层斜率对核池沸腾过程中气泡生长和传热影响的数值模拟

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-08 DOI: 10.1016/j.pnucene.2025.106017

Hongkang Tian , Botao Zhang , Tenglong Cong , Xiaowen Wang , Mengke Cai , Hanyang Gu

{"title":"Numerical simulation of the effect of micro-layer slopes on bubble growth and heat transfer during nucleate pool boiling","authors":"Hongkang Tian , Botao Zhang , Tenglong Cong , Xiaowen Wang , Mengke Cai , Hanyang Gu","doi":"10.1016/j.pnucene.2025.106017","DOIUrl":"10.1016/j.pnucene.2025.106017","url":null,"abstract":"<div><div>In conducted water nucleate pool boiling experiments, the initial micro-layer slopes exhibited fluctuations ranging from 0.04 to 0.05. Considering that the mechanisms by which the micro-layer slopes affect bubble growth have not been well elucidated, numerical simulations of the bubble growth process under different initial micro-layer slopes were performed in this study. The interface dynamics were accurately captured by the coupled LS and VOF methods (CLSVOF). The phase-change model, coupled with smear methods, was developed to simulate bubble growth. Furthermore, the models of initial micro-layer thickness and thermal resistance were developed to investigate the heat-transfer mechanisms within the micro-layer. The coupling methods and proposed models were then validated against measurements from pool boiling experiments. The results demonstrate that the micro-layer slopes (<em>C</em><sub><em>slope</em></sub>) increase in a linear relationship with the time after nucleation since the extension of the dry-spot. In addition, the thermal conductivity resistance and the evaporation resistance are found to be of the same order of magnitude, but show opposite trends with respect to the radius. As <em>C</em><sub><em>slope</em></sub> increases from 3.79e-3 to 5.13e-3, the bubble equivalent radius and height increase by 7.8 % and 5.3 % with bubble departure, respectively. When the initial <em>C</em><sub><em>slope</em></sub> is 4.46e-3, the micro-layer contributes 21.6 % to the bubble growth, and its evaporation time fraction in the bubble growth time increases from 0.56 to 0.68 with <em>C</em><sub><em>slope</em></sub> increasing from 3.79e-3 to 5.13e-3. This study contributes to a deeper understanding of the role of the micro-layer in bubble growth dynamics.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106017"},"PeriodicalIF":3.2,"publicationDate":"2025-09-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145020056","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

Regenerating and estimating missing parameters in critical benchmark experiments: A framework for inverse uncertainty quantification using information-theoretic experiment design 关键基准实验中缺失参数的再生与估计：基于信息论实验设计的逆不确定性量化框架

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-08 DOI: 10.1016/j.pnucene.2025.106016

Xiangchun Tian , Qian Zhang , Geng Zhang

{"title":"Regenerating and estimating missing parameters in critical benchmark experiments: A framework for inverse uncertainty quantification using information-theoretic experiment design","authors":"Xiangchun Tian , Qian Zhang , Geng Zhang","doi":"10.1016/j.pnucene.2025.106016","DOIUrl":"10.1016/j.pnucene.2025.106016","url":null,"abstract":"<div><div>The verified benchmark data are integral validation components of contemporary neutronics calculation, which plays a crucial role in advanced modeling and simulation, criticality and reactor safety analysis, and nuclear data testing. Nevertheless, the phenomenon of retained experiment data loss has occurred occasionally in recent years, causing great difficulty and influence on the formulation and compilation of benchmark in international evaluation projects. Therefore, we proposed a comprehensive approach to address the issue of data missing in benchmark experiments. In this paper, we use the Bayesian inference framework, combined with the information theory method, to give a general process framework for dealing with missing data estimation. This framework spans from experimental strategies design to experimental data acquisition, and further to Bayesian inverse uncertainty quantification (IUQ) based on the obtained data. It indicates that this approach can effectively reduce the uncertainty of unknown parameters with fewer IUQ evaluation times, and provide the effective estimation of missing data. The results obtained her e not only provide a theoretical basis for regeneration and estimation methods of missing parameters in critical benchmark experiments, but also have great engineering application prospects in parameter estimation and model calibration.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106016"},"PeriodicalIF":3.2,"publicationDate":"2025-09-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145020057","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

Temperature forecast for spent nuclear fuels (SNFs) in dry storage using time series decomposition and machine learning 使用时间序列分解和机器学习的乏核燃料干贮存温度预测

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-07 DOI: 10.1016/j.pnucene.2025.106006

Yingxiao Kong , Bozhou Zhuang , Danny Smyl

{"title":"Temperature forecast for spent nuclear fuels (SNFs) in dry storage using time series decomposition and machine learning","authors":"Yingxiao Kong , Bozhou Zhuang , Danny Smyl","doi":"10.1016/j.pnucene.2025.106006","DOIUrl":"10.1016/j.pnucene.2025.106006","url":null,"abstract":"<div><div>The spent nuclear fuel (SNF) is a high-level radioactive nuclear waste disposed from the nuclear power plants. Currently, SNF is stored in dry cask storage systems (DCSSs) for extended interim dry storage. The thermal profile of DCSSs during their dry storage has been identified as the top research priority. This study developed a temperature forecast framework for SNF in dry cask to predict their temperature variation over time. A framework was developed with six steps: data collection, data cleaning, sensor aggregation, time series decomposition, model training and evaluation, and long-term forecast with spatial temperature variability. The proposed framework was validated using real thermal data collected from M5 and Zirlo cladding materials. Research results found that the time series decomposition plays a key role by extracting the trend component from the original time series. Machine learning (ML) models trained on decomposed data achieve smaller errors compared to models trained on the original data. Among the four models evaluated, autoregressive integrated moving average (SARIMA) outperforms other models and has the best robustness across different training-testing split windows. Long-term temperature forecast demonstrates a gradual cooling trend and reduced temperature variability across fuel locations to the year of 2050. Conclusions and methodologies from this study are promising to support the decision-making for extended dry storage for high-level radioactive wastes.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106006"},"PeriodicalIF":3.2,"publicationDate":"2025-09-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145011177","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

Uncertainty and sensitivity analysis of containment aerosol removal under severe accident 严重事故下安全壳气溶胶去除的不确定性和敏感性分析

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-07 DOI: 10.1016/j.pnucene.2025.106004

Pingwen Ou , Yongzheng Chen , Peng Chen , Yong Ouyang , Chao Guo , Guanghui Su

{"title":"Uncertainty and sensitivity analysis of containment aerosol removal under severe accident","authors":"Pingwen Ou , Yongzheng Chen , Peng Chen , Yong Ouyang , Chao Guo , Guanghui Su","doi":"10.1016/j.pnucene.2025.106004","DOIUrl":"10.1016/j.pnucene.2025.106004","url":null,"abstract":"<div><div>This study focuses on the uncertainty and sensitivity analysis of containment aerosol removal under severe accident conditions using the severe accident integral code ASTEC, validated by experiments carried by CNPRI, and the coupled uncertainty and sensitivity tool SUNSET. A \"separated\" methodology is introduced, which distinguishes between thermal-hydraulic and aerosol boundary conditions to highlight the impact of containment aerosol mechanisms. Eleven uncertainty input parameters related are selected for uncertainty propagation and the Spearman correlation coefficient is utilized to describe sensitivity. The removal factor exhibits significant variation, with peaks due to temporary enhancement of diffusiophoresis deposition caused by corium relocation and subsequent steam generation. Uncertainty in the removal factor is substantial before aerosol release termination and narrows afterward. The gravitational settling and the diffusiophoresis deposition are the most important contributors with approximately 70 % and 20 % deposited aerosol mass, respectively. The initial mass medium diameter, the gravitational shape factor and the agglomeration shape factor are the most influential input parameters in aerosol removal, including in-containment deposition and environmental release, and they should be considered discreetly with conservatism in source term estimation and radioactive consequence evaluation in nuclear engineering.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106004"},"PeriodicalIF":3.2,"publicationDate":"2025-09-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145011174","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

Theoretical study of the stability in transient neutronics/thermal-hydraulics coupling problems using Fourier analysis 瞬态中子/热工-水力学耦合稳定性的傅立叶分析理论研究

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-07 DOI: 10.1016/j.pnucene.2025.106015

Xingyu Zhao , Kaiwen Li , Shanfang Huang , Qiaoyan Chen , Kan Wang , Yaru Li

{"title":"Theoretical study of the stability in transient neutronics/thermal-hydraulics coupling problems using Fourier analysis","authors":"Xingyu Zhao , Kaiwen Li , Shanfang Huang , Qiaoyan Chen , Kan Wang , Yaru Li","doi":"10.1016/j.pnucene.2025.106015","DOIUrl":"10.1016/j.pnucene.2025.106015","url":null,"abstract":"<div><div>This paper theoretically studies the stability of Picard iteration in transient neutronics and thermal-hydraulics coupling problems using Fourier analysis. Various iteration schemes of a simplified transient coupling problem were mathematically described in one-dimensional Cartesian coordinates. Fourier analysis was then applied to the iteration schemes and expressions of iterative spectral radius were obtained. The results show that the spectral radius of the deterministic iteration is identical to that of a particular case of the Monte Carlo-based iteration, indicating their mathematical equivalence. Verifications confirm the validity of the methodology and show that the theoretical model agrees well with numerical results. Analytical results show that the iterative stability is primarily affected by the system size, feedback strength, scattering ratio, and time step. The stability is improved for systems with small sizes, and unconditional stability is achieved for systems with relatively weak feedback. The time step effect is highly coupled with multiple factors including the system sizes, initial state, and reactivity. The selection of the time step becomes more stringent as the reactivity is more positive for supercritical systems, or less negative for subcritical systems. For subcritical systems, reducing the time step does not necessarily improve the stability. Further discussions show the relations of the iterative stability to the thermal-hydraulics properties, under-relaxation treatment, and Monte Carlo cycles, quantitatively showing that the under-relaxation treatment improves the stability, while using excessive Monte Carlo cycles worsens the stability and may even lead to severe divergence.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106015"},"PeriodicalIF":3.2,"publicationDate":"2025-09-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145011100","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

Experimental study on heat transfer and flow characteristics inside helically corrugated tubes in intermediate heat exchangers 中间换热器螺旋波纹管内换热及流动特性实验研究

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-07 DOI: 10.1016/j.pnucene.2025.106019

Haifeng Liu , Qingxiang Hu , Wei Peng , Ekaterina Sokolova , Khashayar Sadeghi , Qi Sun , Jie Wang

{"title":"Experimental study on heat transfer and flow characteristics inside helically corrugated tubes in intermediate heat exchangers","authors":"Haifeng Liu , Qingxiang Hu , Wei Peng , Ekaterina Sokolova , Khashayar Sadeghi , Qi Sun , Jie Wang","doi":"10.1016/j.pnucene.2025.106019","DOIUrl":"10.1016/j.pnucene.2025.106019","url":null,"abstract":"<div><div>The intermediate heat exchanger (IHX) in very-high-temperature gas-cooled reactors (VHTRs) is essential for process heat applications, serving as the primary component for thermal energy transfer in the intermediate loop. This study experimentally investigated the heat transfer and flow characteristics of a smooth circular tube and eight helically corrugated tubes (HCTs) with varying structural parameters, using air as working fluid, under turbulent conditions spanning Reynolds number from 7000 to 22000. The results indicate that HCTs significantly enhance convection heat transfer within the tube but also lead to increased flow resistance. The <em>Nu</em> and <em>f</em> of the HCTs increase with higher dimensionless corrugation height <em>e</em>/<em>d</em>, and decrease with larger dimensionless corrugation pitch <em>p</em>/<em>d</em>. Based on the experimental data, empirical correlations were developed in the form of power and dimensionless roughness functions, both demonstrating good agreement with the measurements. The maximum errors of the power correlations for <em>Nu</em> and <em>f</em> were ±11.24 % and ±15.89 %, respectively, while the maximum errors for the dimensionless roughness function correlations for resistance and heat transfer were ±15.67 % and ±15.17 %.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106019"},"PeriodicalIF":3.2,"publicationDate":"2025-09-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145011101","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 flow characteristics of gas-liquid two-phase flow in reactor coolant pump 反应堆冷却剂泵内气液两相流内部流动特性研究

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-07 DOI: 10.1016/j.pnucene.2025.106018

Chenbiao Tian, Yun Long, Mingyu Zhang

{"title":"Research on internal flow characteristics of gas-liquid two-phase flow in reactor coolant pump","authors":"Chenbiao Tian, Yun Long, Mingyu Zhang","doi":"10.1016/j.pnucene.2025.106018","DOIUrl":"10.1016/j.pnucene.2025.106018","url":null,"abstract":"<div><div>The operational performance of the Reactor coolant pump (RCP) is crucial to the safety and reliability of nuclear power plants. During a Loss of Coolant Accident (LOCA), the RCP is subjected to complex gas–liquid two-phase flow conditions, which significantly affect its head, torque, and operational efficiency. In this study, a scaled CAP1400 model is analyzed using a high-fidelity MUSIG model with ten bubble size groups to capture bubble coalescence and breakup. Numerical simulations show that as the inlet gas volume fractions (IGVF) increases from 1 % to 30 %, pump head and efficiency decline continuously, with a sharp performance drop of up to 40 % occurring at IGVF = 5 %–15 %. When IGVF exceeds 10 %, gas accumulation near the impeller suction surface leads to flow separation and channel blockage. The Ω-vortex method is applied to identify distinct flow regimes evolving from bubbly flow to coalescing bubble flow, gas pocket flow, and finally separating flow. This study reveals the changing law of the internal flow in the nuclear reactor coolant pump under the inlet gas-containing condition, analyzes the mechanism of the gas-liquid two-phase flow on the performance of the nuclear reactor coolant pump, and aims to gain a deeper understanding of the specific impact of the gas-liquid two-phase flow on the performance of the nuclear reactor coolant pump.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106018"},"PeriodicalIF":3.2,"publicationDate":"2025-09-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145011175","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