Annals of Nuclear Energy最新文献_第6页

A comparative study on the neutronic characteristics of the new four-petal and three-petal helix fuel assemblies 新型四瓣和三瓣螺旋燃料组件中子特性的比较研究

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-16 DOI: 10.1016/j.anucene.2025.111637

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

{"title":"A comparative study on the neutronic characteristics of the new four-petal and three-petal helix fuel assemblies","authors":"Deping Du, Jincheng Wang, Xunjian Che, Jianchuang Sun, Weihua Cai","doi":"10.1016/j.anucene.2025.111637","DOIUrl":"10.1016/j.anucene.2025.111637","url":null,"abstract":"<div><div>Petal-shaped helix fuel (PHF) enhances the reactor power and economic efficiency owing to its large heat transfer area, improved flow and heat transfer, and self-supporting structure. In this study, the neutronics characteristics of four petal-shaped fuel rods (FPF) and three petal-shaped fuel rods (TPF) are compared by analyzing the concave-convex ratio(also called the geometric factor for PHF, <em>R</em>/<em>r</em>), water-uranium ratio, and helix angle of the fuel rod. The results show that the difference in <em>R/r</em> values lead to different <em>k</em><sub>∞</sub> for FPF-FA and TPF-FA, and the <em>k</em><sub>∞</sub> of TPF-FA performs more excellently. For example, When <em>R/r</em> is equal to 2, the <em>k</em><sub>∞</sub> of TPF-FA is 1.13650, while that of FPF-FA is 1.12451. When the water-uranium ratio decreases from 2.3 to 1.5, the effective full power days of the FPF assembly increases from 420 to 750, and those of the TPF assembly increases from 480 to 810. At a helix angle of 720°, the maximum effective full power values for the FPF and TPF assemblies are 540d and 600d days, respectively. The non-uniformity coefficients of the FPF assembly are 0.02 % ∼ 1.80 % higher than those of TPF-FA. Finally, the FPF assembly exhibits better proliferation ability. Specifically, the resonance absorption of FPF-FA is always higher than that of TPF-FA, which improves the utilization of <sup>238</sup>U.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111637"},"PeriodicalIF":1.9,"publicationDate":"2025-06-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144290960","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 study of flow evolution and secondary flow dynamics in helical coils with periodically varying curvature 周期变曲率螺旋盘管内流动演化及二次流动力学的数值研究

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-14 DOI: 10.1016/j.anucene.2025.111651

Yangyang Li , Zhiling Guan , Hangbin Zhao , Nailiang Zhuang

{"title":"Numerical study of flow evolution and secondary flow dynamics in helical coils with periodically varying curvature","authors":"Yangyang Li , Zhiling Guan , Hangbin Zhao , Nailiang Zhuang","doi":"10.1016/j.anucene.2025.111651","DOIUrl":"10.1016/j.anucene.2025.111651","url":null,"abstract":"<div><div>Helical coil steam generators (HCSGs) are recognized as advanced high-efficiency heat exchangers for the nuclear industry. To further enhance heat and mass transfer both inside the coil tube and within coil bundles, the present study introduces an innovative concept: a variable-curvature helical coil tube combined with a longitudinal cross-arrangement helical coil bundle. This paper numerically investigates the evolution characteristics of the flow structure within the proposed variable-curvature helical coil. Using Reynolds-averaged Navier-Stokes (RANS) turbulence models, we analyzed the evolution of velocity fields, vorticity, Q-criterion, and turbulent kinetic energy (TKE). The simulation results reveal a transient flow structure where the secondary flow, vortex morphology, and TKE distribution dynamically adapt to the periodically varying curvature. Specifically, the size and distribution of secondary flow vortices are found to be strongly dependent on the axial position, directly correlating with the local curvature. Furthermore, the mixing efficiency is significantly enhanced in the regions away from the coil center compared to the central region, highlighting the crucial role of secondary flow in promoting transverse mass transfer. These findings provide valuable theoretical insights for the design and optimization of high-performance helical coil steam generators and heat exchangers.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111651"},"PeriodicalIF":1.9,"publicationDate":"2025-06-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144279726","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

Effect of thermal-hydraulic parameters and pH on the corrosion product deposition in steam generator based on CFD 基于CFD的热工水力参数和pH对蒸汽发生器腐蚀产物沉积的影响

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-14 DOI: 10.1016/j.anucene.2025.111633

Yunchen Lai , Haiyan Xie , Shiyu Tan , Ke Wang , Dongyun Li , Xuesong Li , Yang Gao , Hongguo Hou , Nan Chao , Caishan Jiao , Yu Zhou

{"title":"Effect of thermal-hydraulic parameters and pH on the corrosion product deposition in steam generator based on CFD","authors":"Yunchen Lai , Haiyan Xie , Shiyu Tan , Ke Wang , Dongyun Li , Xuesong Li , Yang Gao , Hongguo Hou , Nan Chao , Caishan Jiao , Yu Zhou","doi":"10.1016/j.anucene.2025.111633","DOIUrl":"10.1016/j.anucene.2025.111633","url":null,"abstract":"<div><div>The deposition of corrosion products in the primary circuit of a pressurized water reactors is known to have an adverse impact on reactor system’s performance, which can cause localized corrosion. They can also impede the flow of coolant, or in severe cases block the tube channels. Besides, the deposits have a lower thermal conductivity than the structural materials, which may increase the thermal resistance, thus reducing heat transfer efficiency. Despite the presence of a considerable amount of corrosion products in steam generators, research on the deposition of corrosion products within is still insufficient. A comprehensive 3-D model of thermal–hydraulic and chemical processes was used to investigate the factors affecting the deposition of corrosion products in a steam generator. For the purpose of determine the deposition distribution along the heat transfer tube, the tube was separated into 11 main nodes based on the equal temperature differences according to the thermal–hydraulic data calculated. The simulation results indicate that the deposition thickness is sensitive to coolant temperature, flow velocity and pH value, and it was shown that higher temperature(from 560 K to 600 K decreasing 9.31 %), pH value (from 6.5 to 8.0 decreasing 9.92 %) and lower flow velocity (from 5 m/s to 20 m/s increasing 8.13 %)was effective for reducing the corrosion product deposition due to the physicochemical properties of the coolant and the turbulent flow, while working pressure has less influence on it(from 6 MPa to 15 MPa increasing only 1.03 %).</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111633"},"PeriodicalIF":1.9,"publicationDate":"2025-06-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144279729","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}

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Investigation of environmental effects from the operation of a nuclear power plant 核电站运行对环境影响的调查

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-14 DOI: 10.1016/j.anucene.2025.111620

I. Souza, S. Pennafirme, N. Santos, A. Domingues, A. Silva, I. Lima

{"title":"Investigation of environmental effects from the operation of a nuclear power plant","authors":"I. Souza, S. Pennafirme, N. Santos, A. Domingues, A. Silva, I. Lima","doi":"10.1016/j.anucene.2025.111620","DOIUrl":"10.1016/j.anucene.2025.111620","url":null,"abstract":"<div><div>This study presents a comparative analysis of pre-operational data report (July 1979–October 1980), operational data report (2010 and 2021), and sediment samples collected in September 2022, to monitor the area designated for the disposal of cooling effluents from the Angra I and II reactors, known as Piraquara de Fora, and to assess its potential environmental impacts. The activity concentrations of <sup>134</sup>Cs, <sup>137</sup>Cs, <sup>58</sup>Co, <sup>60</sup>Co, <sup>54</sup>Mn, <sup>7</sup>Be, <sup>214</sup>Pb, <sup>228</sup>Ac, and <sup>40</sup>K were analyzed by gamma spectrometry in dry sediment samples obtained from eight distinct sampling points within the Piraquara de Fora impact area. The results of comparisons with pre-operational (1979/1980), operational (2010 and 2021), and current experimental data from 2022 indicated an increase in <sup>40</sup>K concentrations, which can be attributed to the high background radiation levels of the region, posing no discernible threat to human or environmental well-being. These findings provide a foundation for future investigations and offer valuable insights for radiological mapping purposes.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111620"},"PeriodicalIF":1.9,"publicationDate":"2025-06-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144289197","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 investigation of the screen mesh effects on the heat transfer performance of wick structured heat pipe 筛网对灯芯结构热管传热性能影响的数值研究

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-14 DOI: 10.1016/j.anucene.2025.111655

Youyuan Fu , Da Chen , Yuxuan Cui , Shang Mao , Zilong Deng

{"title":"Numerical investigation of the screen mesh effects on the heat transfer performance of wick structured heat pipe","authors":"Youyuan Fu , Da Chen , Yuxuan Cui , Shang Mao , Zilong Deng","doi":"10.1016/j.anucene.2025.111655","DOIUrl":"10.1016/j.anucene.2025.111655","url":null,"abstract":"<div><div>The wick structure is the key component of heat pipe, which drives the working fluid circulation and greatly influences the heat transfer performance. This study investigated the steady state operation of heat pipes with seven different screen mesh numbers and four input powers through numerical simulation methods. A capillary force model was established to formulate the relationship between the driving force of wick structure and the effective pore size of screen mesh. The Lee model and Volume of Fluid (VOF) model were employed to simulate the phase changes and two-phase flow within the heat pipe. The numerical model was first validated by the published experiment data. The simulation results revealed that the variation screen mesh number greatly affected the internal state of heat pipe, such as the distributions of temperature, mixed velocity, and phase fraction. The equivalent thermal resistance calculated from the temperature differences of the outer wall also showed a dependence on the screen mesh number, but its sensitivity decreased as the input power increased. The underlying mechanism was interpreted by the screen mesh effects on the circulation efficiency of working fluid, which was characterized by a net mass flow into the wick region of condenser section. Moreover, a critical power concept was proposed that the heat pipe performance was governed by the balance between evaporation and condensation rates, along with the liquid volume fraction in the wick region.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111655"},"PeriodicalIF":1.9,"publicationDate":"2025-06-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144289196","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}

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Neutronics calculation and analysis of a small lead-bismuth fast reactor core with control rods integrated within fuel assemblies 燃料组件内集成控制棒的小型铅铋快堆堆芯的中子计算与分析

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-13 DOI: 10.1016/j.anucene.2025.111653

Jiehao Gao, Haoyu Fan, Xianan Du, Wenjie Chen, Youqi Zheng

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Fault diagnosis study for nuclear power plants under imbalanced fault sample datasets based on deep learning 基于深度学习的不平衡故障样本集下核电厂故障诊断研究

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-13 DOI: 10.1016/j.anucene.2025.111634

Zhanguo Ma , Jing Cui , Jing Zhang , Liang Zhang , Wenhao Jia , Long Tian

{"title":"Fault diagnosis study for nuclear power plants under imbalanced fault sample datasets based on deep learning","authors":"Zhanguo Ma , Jing Cui , Jing Zhang , Liang Zhang , Wenhao Jia , Long Tian","doi":"10.1016/j.anucene.2025.111634","DOIUrl":"10.1016/j.anucene.2025.111634","url":null,"abstract":"<div><div>The safety of nuclear power plants is crucial, and the situation awareness of the power plant is significantly important for the plant operation during which the fault diagnosis technology plays a key role for the plant state monitoring. Operation of the nuclear power plant is predominantly in a normal state, resulting in a scarcity of fault data. This scarcity leads to imbalanced training data, posing a challenge to the accuracy of fault diagnosis models. This study proposed a fault diagnosis framework that integrates Self-Attention Time-Series Generative Adversarial Networks (SATimeGAN) to augment the training datasets and Convolutional Neural Network-Bidirectional Long Short-Term Memory networks (CNN-BiLSTM) to diagnose the faults, aimed at addressing the data imbalance issue and improving the diagnostic accuracy. Experimental results demonstrate preferable performance of the model in nuclear power plant fault diagnosis, especially in handling imbalance sample fault datasets, compared to traditional CNN, LSTM, and BiLSTM models.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111634"},"PeriodicalIF":1.9,"publicationDate":"2025-06-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144272528","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

Data-driven prediction of heat exchanger steady-state conditions based on support vector regression 基于支持向量回归的换热器稳态工况数据驱动预测

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-13 DOI: 10.1016/j.anucene.2025.111635

Xubin Wu, Wentao Hao, Wenwen Zhang, Zhenlei Liu, Weihua Li, Xingtuan Yang

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Hybrid risk evaluation and prediction method for nuclear power plant using RISMC and transformer-based surrogate model 基于RISMC和变压器代理模型的核电厂混合风险评估与预测方法

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-13 DOI: 10.1016/j.anucene.2025.111603

Linfeng Li, Anqi Xu, Yong Liu, Xiaomeng Dong, Ming Yang, Ting Wen

{"title":"Hybrid risk evaluation and prediction method for nuclear power plant using RISMC and transformer-based surrogate model","authors":"Linfeng Li, Anqi Xu, Yong Liu, Xiaomeng Dong, Ming Yang, Ting Wen","doi":"10.1016/j.anucene.2025.111603","DOIUrl":"10.1016/j.anucene.2025.111603","url":null,"abstract":"<div><div>The safe operation of nuclear power plants imposes strict requirements on the accurate prediction of key parameters and risk assessment, particularly under complex operating conditions and accident scenarios, where the dynamic evolution of key parameters directly impacts operators’ situational awareness and decision-making. This study proposes a hybrid risk evaluation and prediction method based on Risk-informed Safety Margin Characterization(RISMC) methodology, integrating high-fidelity thermal–hydraulic simulation with a Transformer-based surrogate model, significantly expanding the application of RISMC to the operation scenario of nuclear power plants. By combining time-series prediction with regression models, the proposed method enables high-accuracy prediction of the dynamic evolution of critical parameters, such as steam generator water level and pressure, while dynamically quantifying the impact of various intervention strategies on reactor shutdown risk. This approach effectively addresses the challenges of existing risk assessment methods in computational efficiency and performance during plant operation. A Partial Loss-of-Feedwater (PLOFW) scenario is used as a case study to verify the method’s effectiveness in dynamic prediction, risk quantification, and intervention strategy evaluation. The results demonstrate that the proposed method significantly outperforms prediction accuracy and computational efficiency. By precisely quantifying dynamic safety margin, the method significantly enhances operators’ situational awareness and decision-making capabilities during abnormal events and incidents, providing a basis for optimizing intervention strategies. This approach not only ensures the safe and flexible operation of nuclear power plants but also balances safety and economic efficiency.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111603"},"PeriodicalIF":1.9,"publicationDate":"2025-06-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144523360","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}

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Advancements and challenges of machine learning and deep learning in autonomous control of nuclear reactors 核反应堆自主控制中机器学习和深度学习的进展与挑战

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-06-13 DOI: 10.1016/j.anucene.2025.111643

Hui-Yu Hsieh, Pavel Tsvetkov

引用次数: 0