Annals of Nuclear Energy最新文献_第6页

Utilization of thorium in accelerator driven subcritical system 钍在加速器驱动亚临界系统中的应用

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-07-08 DOI: 10.1016/j.anucene.2025.111728

Shijie Du , Xiang Wu , Peng Fang , Qiuying Liang , Yongwei Yang , Feng Zhou , Yanling Zhu , Lei Yang

引用次数: 0

A comprehensive depletion code MACT for molten salt reactors 熔盐反应堆的综合耗尽代码MACT

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-07-08 DOI: 10.1016/j.anucene.2025.111709

Yunfei Zhang , Yang Zou , Rui Yan , Guifeng Zhu , Qian Zhang

{"title":"A comprehensive depletion code MACT for molten salt reactors","authors":"Yunfei Zhang , Yang Zou , Rui Yan , Guifeng Zhu , Qian Zhang","doi":"10.1016/j.anucene.2025.111709","DOIUrl":"10.1016/j.anucene.2025.111709","url":null,"abstract":"<div><div>In the realm of reactor design and analysis, the computation of nuclide depletion and the quantification of radioactive source terms are indispensable. These processes are underpinned by the rigorous solution of the depletion equation, which are essential for obtaining accurate determinations of nuclide inventories. To address the characteristics of online reprocessing, continuous fuel feeding, and nuclide migration in liquid fuel molten salt reactors (MSRs), a radioactive source term calculation code named MACT has been developed specifically for MSRs. The depletion solution algorithms in MACT employ the widely used Transmutation Trajectory Analysis (TTA) method and the Chebyshev Rational Approximation Method (CRAM). Pseudo-decay constant, pseudo nuclide method, and augmented matrix method are utilized to handle the reprocessing and feeding issues of MSRs. Additionally, a depletion model under multi-node isotopic migration conditions has been established, along with the development of corresponding calculation module. Finally, MACT has been validated through various tests, including the decay of Ra-228, activation of Cr-50, testing of extremely short-lived fission products, decay heat testing of U-235 thermal neutron fission, fuel salt irradiation and feeding, and multi-node nuclide migration tests. Numerical results demonstrate that MACT possesses high precision in nuclide inventory calculations and can easily handle the characteristics of MSR reprocessing, feeding, and nuclide migration, making it a potent engineering calculation tool for depletion calculations and source term analysis in MSRs.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111709"},"PeriodicalIF":1.9,"publicationDate":"2025-07-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144571666","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

Reliability assessment of passive EHRS of IRIS based on the AM-SIS-ANN method 基于AM-SIS-ANN方法的IRIS被动EHRS可靠性评估

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-07-07 DOI: 10.1016/j.anucene.2025.111707

Hong Jiang , Haiying Li , Shuwen Yu , Changhong Peng

{"title":"Reliability assessment of passive EHRS of IRIS based on the AM-SIS-ANN method","authors":"Hong Jiang , Haiying Li , Shuwen Yu , Changhong Peng","doi":"10.1016/j.anucene.2025.111707","DOIUrl":"10.1016/j.anucene.2025.111707","url":null,"abstract":"<div><div>Research on the reliability estimation of passive systems in nuclear power plants has been pivotal to ensuring nuclear power generation safety. Numerous analytical methods have been proposed to calculate the failure probability of passive systems, with the most notable ones combining fast computational surrogate models with efficient variance reduction sampling techniques. Nevertheless, these methods are predominantly based on deterministic failure criteria, posing a significant challenge in managing the uncertainty of such criteria. To address this problem and enhance the accuracy and efficiency of passive system reliability estimation, this paper introduces a segmented method that integrates Adaptive Metamodel Subset Simulation Importance Sampling (AM-SIS) with neural networks, abbreviated as AM-SIS-ANN. This method harnesses the strengths of both techniques: employing the AM-SIS method to calculate failure probabilities in low-probability regions to mitigate high prediction errors from neural networks in sparse data areas, and using neural networks to compute output distributions in other regions, thereby eliminating the need for additional AM-SIS executions and substantially reducing computation time. The proposed method’s effectiveness is illustrated and validated through two numerical examples. Finally, this method is applied to calculate the failure probability of the Emergency Heat Removal System (EHRS) of the IRIS reactor. For the natural circulation loop example, considering four failure criteria, the AM-SIS-ANN method achieved the shortest computation time, reducing it by approximately 23.4% compared to the AM-SIS method and by about 57.5% compared to the neural network method. These results demonstrate that the AM-SIS-ANN method, under uncertain failure criteria, can significantly reduce computational time while ensuring high accuracy.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111707"},"PeriodicalIF":1.9,"publicationDate":"2025-07-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144570802","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

Precise implementation of the Goldstein current model for self-powered neutron detectors and comparative analysis of its approximate approaches 自供电中子探测器Goldstein电流模型的精确实现及其近似方法的比较分析

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-07-07 DOI: 10.1016/j.anucene.2025.111700

Jun Chen , Shijie Luo , Tingyu Wu , Li Cai , Haoliang Lu , Bite Qiu , Shiyu Liu , Qingmin Zhang

{"title":"Precise implementation of the Goldstein current model for self-powered neutron detectors and comparative analysis of its approximate approaches","authors":"Jun Chen , Shijie Luo , Tingyu Wu , Li Cai , Haoliang Lu , Bite Qiu , Shiyu Liu , Qingmin Zhang","doi":"10.1016/j.anucene.2025.111700","DOIUrl":"10.1016/j.anucene.2025.111700","url":null,"abstract":"<div><div>Self-powered neutron detectors (SPND) have been commonly used in reactors to monitor neutron flux density based on their response current. The Goldstein model is a typical Monte-Carlo model used to calculate steady-state SPND current. Compared with other models, the conductive current at steady state due to the space charge effect was included and calculated in the Goldstein model, and some approximate approaches were introduced due to the limitations of the used Monte Carlo software or for the sake of fast calculations. Hence, considering that Geant4 can trace the trajectories of charged particles in electric field, a more precise implementation of the Goldstein current model—accounting for charge transport under the actual electric field—has been carried out based on Geant4 in this work. In the precise implementation, the response current is accurately calculated by simulating the electron transported under the actual electric field, and actual charge density distribution is also obtained. Compared with the experimental result, the relative deviation of the response current calculated by the precise implementation is 8.99 %, while for the three approximation approaches, the deviations are 9.49 %, 10.15 %, and 11.39 %, respectively. In addition, six parameters affecting the detector response were scanned within the conventional variation range for comparative analysis of the three approximate approaches. The results show that the approximate approach #1 always gives the most precise result and that considering the practical application situations the insulator resistivity is the most key parameter affecting the space charge effect. It is worth mentioning that when the peak electric potential in insulator is a few kV or even less, the approximate approaches are acceptable, especially for the situation of quick calculation.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111700"},"PeriodicalIF":1.9,"publicationDate":"2025-07-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144570817","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

Investigating constituent redistribution in U-Zr metallic fuels: A phase-field approach incorporating porosity and sodium infiltration 研究铀锆金属燃料中的成分再分布：结合孔隙度和钠渗透的相场方法

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-07-07 DOI: 10.1016/j.anucene.2025.111679

Woojin Jung , Ju-Seong Kim , Kunok Chang

{"title":"Investigating constituent redistribution in U-Zr metallic fuels: A phase-field approach incorporating porosity and sodium infiltration","authors":"Woojin Jung , Ju-Seong Kim , Kunok Chang","doi":"10.1016/j.anucene.2025.111679","DOIUrl":"10.1016/j.anucene.2025.111679","url":null,"abstract":"<div><div>U-Zr metallic fuel, known for its superior thermal conductivity compared to <span><math><msub><mrow><mtext>UO</mtext></mrow><mrow><mn>2</mn></mrow></msub></math></span> fuel, is a promising candidate for advanced nuclear reactors. However, redistribution of constituents during operation affects the integrity of the fuel and phase stability, necessitating detailed investigation. In this study, a phase-field model was developed using the Multiphysics Object-Oriented Simulation Environment (MOOSE) to analyze the effects of porosity and sodium infiltration on redistribution behavior. A Baseline model incorporating a phase dependent porosity model was established, enabling comparative analyses. For instance, without considering porosity, our simulation resulted in an approximate 0.17at% decrease in the central Zr concentration and a 36K decrease in centerline temperature. Considering 50% sodium infiltration lead to a 0.7at% lower central Zr concentration and an approximately 20K decrease at centerline temperature. The findings demonstrate the importance of accurately modeling thermal conductivity to predict fuel behavior, providing a basis for optimizing U-Zr fuel performance in advanced reactor applications.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111679"},"PeriodicalIF":1.9,"publicationDate":"2025-07-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144570816","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

Prediction of secondary circuit power generation for nuclear units based on WSA-VMD-BP approach 基于WSA-VMD-BP方法的核电机组二次回路发电量预测

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-07-07 DOI: 10.1016/j.anucene.2025.111721

Desheng Dan , Maobin Hu , Haiyan Liu , Yuanhao Xu , Jie Yu , Gang Pei

{"title":"Prediction of secondary circuit power generation for nuclear units based on WSA-VMD-BP approach","authors":"Desheng Dan , Maobin Hu , Haiyan Liu , Yuanhao Xu , Jie Yu , Gang Pei","doi":"10.1016/j.anucene.2025.111721","DOIUrl":"10.1016/j.anucene.2025.111721","url":null,"abstract":"<div><div>Nuclear energy has been regarded as an environmentally superior and reliable form of energy due to its inherent stability and lengthy operational lifetime. Small modular reactors (SMR) have been positioned as a prominent research focus in recent years, while artificial intelligence has also opened new avenues for exploration the performance of nuclear units. This paper proposes to predict the power generation of nuclear power plants integrating variational modal decomposition (VMD) and back propagation (BP) neural networks to optimize the hyperparameters through the utilization of the wave search algorithm (WSA). The efficacy of the proposed method is validated through the construction of a secondary circuit mathematical model of a nuclear power facility and an in-depth analysis of the thermal parameter relationships. The proposed method demonstrated an MAE of 0.6964 and a WIA of up to 0.99 in the noiseless case, exhibiting a low prediction error. In the context of environmental noise, the prediction accuracy can be maintained at approximately WIA ∼ 0.97. These results demonstrate the high prediction accuracy and strong robustness of the algorithm.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111721"},"PeriodicalIF":1.9,"publicationDate":"2025-07-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144570803","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

Digital twin model generation for crack propagation in steam generator tubes: Methods and implementation 蒸汽发生器管裂纹扩展的数字孪生模型生成：方法与实现

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-07-05 DOI: 10.1016/j.anucene.2025.111697

Yingying Jiang , Hong Xia , Jinming Zhang , Yihu Zhu , Kaige Zhang , Xueying Huang , Wenzhe Yin , Peiqi Jiang

{"title":"Digital twin model generation for crack propagation in steam generator tubes: Methods and implementation","authors":"Yingying Jiang , Hong Xia , Jinming Zhang , Yihu Zhu , Kaige Zhang , Xueying Huang , Wenzhe Yin , Peiqi Jiang","doi":"10.1016/j.anucene.2025.111697","DOIUrl":"10.1016/j.anucene.2025.111697","url":null,"abstract":"<div><div>Crack propagation in the steam generator tubes are critical factor influencing the safe operation of nuclear power plants. Accurate prediction of crack growth behavior is vital for effective equipment health monitoring and maintenance. A fundamental framework and key technologies for the implementation of digital twin technology in nuclear power plants were presented in this study. And a novel crack propagation digital twin model generation technique for steam generator tubes was introduced, which integrates experimental data with extended finite element simulation results. Particle Filter method and reinforcement learning were conducted to evaluate respective strengths and limitations in crack propagation prediction. Both experimental data and extended finite element simulation data were incorporated into the model training process. The results demonstrated that both digital twin model generation techniques have distinct applicability conditions and high accuracy. This study could provide new insights and technological approaches for the health monitoring of steam generator tubes.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111697"},"PeriodicalIF":1.9,"publicationDate":"2025-07-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144563722","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

Machine learning prediction for thermal–hydraulic parameters of semicircular-fin fuel bundle in lead–bismuth fast reactor 铅铋快堆半圆翅片燃料束热水力参数的机器学习预测

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-07-04 DOI: 10.1016/j.anucene.2025.111696

Qian Li , Siwei Cai , Shengcai Zhang , XueChen Liu , Nianmei Zhang , Chen Hu , Xian Zeng , Yulong Mao , Weihua Cai

{"title":"Machine learning prediction for thermal–hydraulic parameters of semicircular-fin fuel bundle in lead–bismuth fast reactor","authors":"Qian Li , Siwei Cai , Shengcai Zhang , XueChen Liu , Nianmei Zhang , Chen Hu , Xian Zeng , Yulong Mao , Weihua Cai","doi":"10.1016/j.anucene.2025.111696","DOIUrl":"10.1016/j.anucene.2025.111696","url":null,"abstract":"<div><div>In this study, a machine learning approach is used to predict the thermal–hydraulic parameters of lead–bismuth eutectic flow in a new-style semicircular-fin rod bundles. With numerical simulation data, a novel micro segment method was used to extract data from 42 sub-channels and 19 fuel rods in the fluid domain and establish a database with 23,313 data points. Four machine learning models are used to predict the <em>h</em> and Δ<em>P</em> by normalizing the input parameters with model hyperparameter optimization. The results show that all of the four machine learning models have good prediction accuracy, with the error of less than 5% and MAPE were all within 1%. The performance of ANN model is better than that of the other three models in predicting new cases. It indicates that ANN model has a high accuracy in predicting thermal parameters under new cases, which verifies the applicability of the machine learning prediction method for multiple cases. This study confirmed the advantages of machine learning in predicting complex regular parameters, and proposed a new method for flow and heat transfer parameters prediction in the development of a subchannel analysis program for semicircular-fin rod bundles.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111696"},"PeriodicalIF":1.9,"publicationDate":"2025-07-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144557041","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

Evaluation of Aluminum Hexacyanoferrate utilization for PGM and Mo removal from simulated high-level-raffinates in reprocessing for repository area minimization 评价六氰高铁酸铝对PGM的利用和对模拟高水平后萃物中Mo的去除，以减少储存库面积

IF 2.3 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-07-04 DOI: 10.1016/j.anucene.2025.111569

Masahiko Nakase , Ria Mishima , Takumi Abe , Tomohiro Okamura , Hidekazu Asano

{"title":"Evaluation of Aluminum Hexacyanoferrate utilization for PGM and Mo removal from simulated high-level-raffinates in reprocessing for repository area minimization","authors":"Masahiko Nakase , Ria Mishima , Takumi Abe , Tomohiro Okamura , Hidekazu Asano","doi":"10.1016/j.anucene.2025.111569","DOIUrl":"10.1016/j.anucene.2025.111569","url":null,"abstract":"<div><div>Higher burnup LWR and MOX spent fuels contain increased levels of Platinum Group Metals (PGMs; Pd, Ru, Rh) and Mo, necessitating their control to ensure stable glass melter operations and prevent yellow phase formation, thereby maintaining vitrified glass quality. Separating PGMs and Mo during reprocessing can significantly reduce the repository space required for vitrified high-level wastes (HLWs). This study explores the use of Aluminum Hexacyanoferrate (AlHCF) for simultaneous separation of PGMs and Mo, which involves the elution of structural Al during sorption. A fundamental methodology was developed for analyzing the back-end processes of the nuclear fuel cycle (NFC), focusing on the quantitative impact of AlHCF. By integrating adsorption experiments of simulated high-level liquid waste (sHLLW) with mass balance calculations and thermal conductive calculation via NMB 4.0, the study identified practical AlHCF utilization conditions (11 to 40 wt% waste loading and 100 to 200 kg/tHM of AlHCF). It also established the relationship between AlHCF amount, waste loading, and reductions in both vitrified waste and repository size, highlighting optimal conditions for minimizing repository footprint.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111569"},"PeriodicalIF":2.3,"publicationDate":"2025-07-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144724318","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

Mathematical modeling and connectivity-enhanced segmentation of void fraction in two-phase flow CT images 两相流CT图像中空隙率的数学建模与连通性增强分割

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-07-04 DOI: 10.1016/j.anucene.2025.111693

Zirou Jiang , Shuo Xu , Jiahao Chang , Jichen Miao , Yuewen Sun

引用次数: 0