Progress in Nuclear Energy最新文献_第4页

Cross-domain fault diagnosis method for nuclear power plant bearings based on deep transfer learning under small sample conditions 小样本条件下基于深度迁移学习的核电厂轴承跨域故障诊断方法

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-04-30 DOI: 10.1016/j.pnucene.2025.105792

Wenzhe Yin , Hong Xia , Enrico Zio , Xueying Huang

{"title":"Cross-domain fault diagnosis method for nuclear power plant bearings based on deep transfer learning under small sample conditions","authors":"Wenzhe Yin , Hong Xia , Enrico Zio , Xueying Huang","doi":"10.1016/j.pnucene.2025.105792","DOIUrl":"10.1016/j.pnucene.2025.105792","url":null,"abstract":"<div><div>In recent years, methods based on deep learning have attracted attention in the fault diagnosis of rotating machinery in nuclear power plants (NPPs). However, these methods are typically developed under the assumption that sufficient fault samples are available. In practice, rotating machinery in NPPs operate in healthy state most of the time and faults occur rarely and last a relatively short period of time. This work proposes a fault diagnosis method based on deep transfer learning to overcome the issue of small sample conditions in the bearing fault diagnosis task of NPPs. The bearing vibration signals collected by the sensor are converted into a time-frequency map by synchrosqueezed wavelet transforms, they are used as input of the deep convolutional neural network. In the learning phase, the deep learning model first learns domain-related knowledge from real devices, then the model parameters are transferred to the target task, and the model is fine-tuned based on the target domain knowledge. The proposed method was applied to two case studies: bearing fault localization and fault severity assessment. Experimental results demonstrated that, for the fault localization case, the method achieved average accuracy, precision, and F1 score of 95.21 %, 95.35 %, and 95.17 %, respectively, under four small sample conditions (with 10, 20, 30, and 40 samples per category in the training dataset). For the fault severity assessment case, the method attained average accuracy, precision, and F1 score of 95.03 %, 95.45 %, and 94.94 %, respectively, under three small sample conditions (with 3, 5, and 8 samples per category in the training dataset), demonstrating its potential value for NPPs bearing fault diagnosis.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"186 ","pages":"Article 105792"},"PeriodicalIF":3.3,"publicationDate":"2025-04-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143887814","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

Economic competitiveness of a nuclear-renewable hybrid energy system with water desalination: case of study 带海水淡化的核可再生混合能源系统的经济竞争力：案例研究

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-04-30 DOI: 10.1016/j.pnucene.2025.105819

Gustavo Alonso , Jeanette Montaño

{"title":"Economic competitiveness of a nuclear-renewable hybrid energy system with water desalination: case of study","authors":"Gustavo Alonso , Jeanette Montaño","doi":"10.1016/j.pnucene.2025.105819","DOIUrl":"10.1016/j.pnucene.2025.105819","url":null,"abstract":"<div><div>Nuclear-renewable hybrid systems could be an option for electricity systems composed of 100 % clean sources (non-GHG emitting sources). The proposed hybrid systems in the literature show reactors working at 100 % capacity where associated industrial processes and energy storage units are using energy not required for electricity generation. The current case study proposes a 100 % hybrid energy system composed of renewable variable sources (wind and photovoltaic), small modular reactors, and an associated reverse osmosis desalination process, where the reactors will work in a load-following electricity demand mode. An actual isolated electricity system in Mexico composed of aging fossil fuels, wind, and photovoltaic power plants comprises the proposed case study. This region is suffering from water stress. The aging fossil plants are replaced with small modular reactors with an associated reverse osmosis plant system to alleviate water scarcity. The case study considers actual changes in electricity demand on the region's seasonal and daily basis. Results are promissory, having a variable renewable installed capacity penetration of 22.48 %; the hybrid system can follow electricity demand. The proposed hybrid system is economically competitive for investment discount rates up to 7 %, assuming an electricity selling price of 100 US$/MWh and a potable water price, in the region, of 1.70 US$/m3. The study shows that the load-following procedure, in the worst-case scenario, does not compromise the lifetime of nuclear components and ensures normal nuclear operation conditions in the whole fleet of small modular reactors. The results obtained set some guidance conditions for these types of hybrid systems.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"186 ","pages":"Article 105819"},"PeriodicalIF":3.3,"publicationDate":"2025-04-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143887813","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

Derivation of specific clearance levels for landfill disposed of waste at Ignalina NPP 依纳利纳核电厂堆填区弃置废物的特定清理水平的厘定

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-04-30 DOI: 10.1016/j.pnucene.2025.105816

Valdas Ragaišis, Povilas Poškas, Audrius Šimonis

引用次数: 0

A control valve for fluid-load oscillation inhibiting and energy harvesting 一种用于抑制流体负载振荡和能量收集的控制阀

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-04-29 DOI: 10.1016/j.pnucene.2025.105820

Shinong Wang , Zilei Ji , Feiyang Han , Yudong Xie , Jiazhen Han , Yong Wang , Chuandong Li

{"title":"A control valve for fluid-load oscillation inhibiting and energy harvesting","authors":"Shinong Wang , Zilei Ji , Feiyang Han , Yudong Xie , Jiazhen Han , Yong Wang , Chuandong Li","doi":"10.1016/j.pnucene.2025.105820","DOIUrl":"10.1016/j.pnucene.2025.105820","url":null,"abstract":"<div><div>Control valves are extensively utilized in the equipment of nuclear power plants. Under specific operational conditions, fluid oscillation occurs within the valve, resulting in sudden fluid loads on the valve core, which may lead to valve jamming and even stem breakage. To address this problem, an innovative control valve is designed to inhibit the fluid oscillation and harvest the energy typically dissipated during the fluid oscillation process. A piston component is situated within the valve body to mitigate inlet fluid oscillation of the valve and harness a portion of the oscillation energy that would otherwise be dissipated, and a systematic analysis of the factors affecting the valve's suppression of fluid oscillation and capturing energy in this valve is presented. The results show that the innovative control valve can inhibit fluid oscillation and harvest energy from the fluid oscillation process in the control valve. The proposed method does not affect the regulating ability of the control valve, and it can obviously eliminate or reduce the fluid load of the oscillation on the plug of the control valve, reduces the occurrence of vortices inside the valve. which helps to address the problem that the actuator of the valve is prone to abnormal shutdown when the fluid controlled by the control valve is unstable and violent oscillation.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"186 ","pages":"Article 105820"},"PeriodicalIF":3.3,"publicationDate":"2025-04-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143882102","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

Computational model for prediction of water level inside Vertical U-tube Steam Generators (UTSGs) of typical PWR 典型压水堆立式u管蒸汽发生器（UTSGs）内水位预测计算模型

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-04-29 DOI: 10.1016/j.pnucene.2025.105823

Ihtisham Ul Haq , Abdul Manan , Ajmal Shah

{"title":"Computational model for prediction of water level inside Vertical U-tube Steam Generators (UTSGs) of typical PWR","authors":"Ihtisham Ul Haq , Abdul Manan , Ajmal Shah","doi":"10.1016/j.pnucene.2025.105823","DOIUrl":"10.1016/j.pnucene.2025.105823","url":null,"abstract":"<div><div>Maintaining water level inside steam generators in a typical Pressurized Water Reactor (PWR) particularly during low power has always been a significant challenge in the operation of Nuclear Power Plants (NPPs). Variation in power leads to fluctuations in the water level and stabilizing the water level in the steam generator prevent damage to turbines, core and tripping of reactors. This research presents a computational model for predicting water levels in U-tube vertical steam generators (UTSGs) of PWRs during transients. The model's level predictive capability was validated through cross-calculations with actual data of <span><math><mrow><mn>998</mn><mi>M</mi><msub><mi>W</mi><mtext>th</mtext></msub><mo>/</mo><mn>340</mn><mi>M</mi><msub><mi>W</mi><mi>e</mi></msub></mrow></math></span> Nuclear Power Plant (NPP). The methodology involves developing computational frameworks from the Irving model and collecting extensive data from existing PWR systems of <span><math><mrow><mn>998</mn><mi>M</mi><msub><mi>W</mi><mtext>th</mtext></msub><mo>/</mo><mn>340</mn><mi>M</mi><msub><mi>W</mi><mi>e</mi></msub></mrow></math></span> NPPs to assess model accuracy. The results demonstrated that the predictive control method effectively maintained optimal water levels within the steam generators, minimizing discrepancies between predicted and actual values. The ramp response consistently provided smoother and more accurate predictions that closely matched the behavior of the actual system. The cross calculations with actual data further substantiate the model's effectiveness, demonstrating its potential as a reliable tool for real time monitoring and control in steam generators. These findings contribute to the improvement of safety and efficiency in nuclear power plant operations.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"186 ","pages":"Article 105823"},"PeriodicalIF":3.3,"publicationDate":"2025-04-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143887811","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

Characterization of the Ignalina NPP RBMK-1500 reactors graphite: Review and summary of current situation and recent developments in respect to the reactor core dismantlement 格纳利纳核电站RBMK-1500反应堆石墨的特性：关于反应堆堆芯拆除的现状和最新发展的回顾和总结

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-04-28 DOI: 10.1016/j.pnucene.2025.105805

Ernestas Narkūnas, Povilas Poškas, Artūras Šmaižys, Gintautas Poškas

引用次数: 0

Design, protection, perception and planning of mobile robots in nuclear power plants 核电站移动机器人的设计、保护、感知与规划

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-04-27 DOI: 10.1016/j.pnucene.2025.105821

De Zhang , Yan Jiang , Jun Liu , Guokai Xiong , Shuliang Zou

{"title":"Design, protection, perception and planning of mobile robots in nuclear power plants","authors":"De Zhang , Yan Jiang , Jun Liu , Guokai Xiong , Shuliang Zou","doi":"10.1016/j.pnucene.2025.105821","DOIUrl":"10.1016/j.pnucene.2025.105821","url":null,"abstract":"<div><div>Mobile robots in nuclear (MRiN) has become a multidisciplinary research field that integrates numerous technologies (e.g., nuclear technology, robotic, advanced material, artificial intelligence and construction), resulting in fragmented yet extensive related literatures. In this paper, a hybrid methodology combining bibliometric analysis with qualitative discussion is proposed to explore the advancements in MRiN over the past two decades. Four research hotspots, namely design, protection, perception and planning, are identified through quantitative bibliometric analysis employing data statistics and cluster analysis. Subsequent the qualitative discussions of the four hotspots highlight recent achievements and reveal research gaps in MRiN. Furthermore, five future research directions are proposed: 1) in-depth integration of radiation information, building information modeling (BIM), with robotics; 2) novel approaches for locating radioactive sources in complex environments; 3) multi-objective optimization of shielding structures for sensitive components; 4) advanced multi-robot collaboration for concurrent operations; 5) immersive digital twin (DT) technology combined with deep reinforcement learning (DRL) for MRiN operations. By identifying current research themes and technological trends in nuclear robotics, while providing strategic insights for MRiN's future development, this research can serve both academia and industry in terms of promoting robotics technology and computer science in nuclear industry.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"186 ","pages":"Article 105821"},"PeriodicalIF":3.3,"publicationDate":"2025-04-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143877577","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 review of data-driven fault diagnosis method for nuclear power plant 核电站数据驱动故障诊断方法综述

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-04-25 DOI: 10.1016/j.pnucene.2025.105785

Zixiao Wang, Hongyang Wei, Ruifeng Tian, Sichao Tan

{"title":"A review of data-driven fault diagnosis method for nuclear power plant","authors":"Zixiao Wang, Hongyang Wei, Ruifeng Tian, Sichao Tan","doi":"10.1016/j.pnucene.2025.105785","DOIUrl":"10.1016/j.pnucene.2025.105785","url":null,"abstract":"<div><div>Fault diagnosis plays a pivotal role in the operation and maintenance of nuclear power plants, serving as a cornerstone for ensuring facility safety and operational reliability. This review systematically examines state-of-the-art fault diagnosis methodologies implemented in the nuclear power industry, categorizing them into five distinct approaches: expert system, graph theory, machine learning, deep learning and reinforcement learning. Through comparative analysis of their theoretical foundations and implementation mechanisms, this study specifically evaluates their efficacy in addressing two critical challenges: the coolant circulation system and age-related equipment degradation and predictive maintenance. The synthesis of recent advancements reveals an emerging paradigm shift: the synergistic integration of data-intensive AI algorithms with physical mechanism demonstrates remarkable potential for developing high-fidelity diagnostic models. To propel this field forward, subsequent research must prioritize: validation under nuclear safety constraints, development of explainable AI frameworks and solutions balancing diagnostic accuracy with operational security.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"186 ","pages":"Article 105785"},"PeriodicalIF":3.3,"publicationDate":"2025-04-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143868335","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

Comparison between detailed and homogenous modeling methods in the TN-32B spent nuclear fuel demo cask: Part I – storage conditions n - 32b乏燃料演示桶精细建模与均匀建模方法的比较：第一部分——贮存条件

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-04-24 DOI: 10.1016/j.pnucene.2025.105796

Megan Higley , Miles Greiner , Mustafa Hadj-Nacer

{"title":"Comparison between detailed and homogenous modeling methods in the TN-32B spent nuclear fuel demo cask: Part I – storage conditions","authors":"Megan Higley , Miles Greiner , Mustafa Hadj-Nacer","doi":"10.1016/j.pnucene.2025.105796","DOIUrl":"10.1016/j.pnucene.2025.105796","url":null,"abstract":"<div><div>Due to the complexity of modeling spent nuclear fuel casks and canisters, the homogenous method (i.e., modeling the fuel regions as porous blocks with effective properties) is often utilized to conduct computational fluid dynamics simulations. This method allows for reducing the computational effort required by the detailed modeling method. However, no comprehensive comparison between the homogenous and detailed methods in a full cask has been reported in the literature. In this Part I paper, a detailed model of the TN-32 B spent nuclear fuel cask with a detailed representation of the fuel assemblies is compared to a model that uses the homogenous method under storage conditions. The same input parameters and computational mesh are used in both models. Effective thermal conductivities and porous flow coefficients in the radial and axial directions are developed and applied to the homogenous model. Temperature and axial velocities obtained from the detailed and homogenous models are compared on a point-to-point basis within the fuel regions. The results indicate that the homogenous model accurately predicts temperatures relative to the detailed model, with the most notable differences observed at lower elevations within the fuel regions. 95 % of fuel region temperature data are within 2 °C between the models. Furthermore, temperatures at 63 locations obtained from both models are compared to data from the High Burnup Demonstration project and the results showed a difference ranging from −7 °C to +10 °C.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"186 ","pages":"Article 105796"},"PeriodicalIF":3.3,"publicationDate":"2025-04-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143863698","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

AI-driven uncertainty quantification & multi-physics approach to evaluate cladding materials in a microreactor 人工智能驱动的不确定性量化&多物理场方法评估微反应堆包层材料

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-04-24 DOI: 10.1016/j.pnucene.2025.105793

Alexander Foutch , Kazuma Kobayashi , Ayodeji Alajo , Dinesh Kumar , Syed Bahauddin Alam

{"title":"AI-driven uncertainty quantification & multi-physics approach to evaluate cladding materials in a microreactor","authors":"Alexander Foutch , Kazuma Kobayashi , Ayodeji Alajo , Dinesh Kumar , Syed Bahauddin Alam","doi":"10.1016/j.pnucene.2025.105793","DOIUrl":"10.1016/j.pnucene.2025.105793","url":null,"abstract":"<div><div>The pursuit of enhanced nuclear safety has spurred the development of accident-tolerant cladding (ATC) materials for light water reactors (LWRs). This study investigates the potential of repurposing these ATCs in advanced reactor designs, aiming to expedite material development and reduce costs. The research employs a multi-physics approach, encompassing neutronics, heat transfer, thermodynamics, and structural mechanics, to evaluate four candidate materials (Haynes 230, Zircaloy-4, FeCrAl, and SiC–SiC) within the context of a high-temperature, sodium-cooled microreactor, exemplified by the Kilopower design. While neutronic simulations revealed negligible power profile variations among the materials, finite element analyses highlighted the superior thermal stability of SiC–SiC and the favorable stress resistance of Haynes 230. The high-temperature environment significantly impacted material performance, particularly for Zircaloy-4 and FeCrAl, while SiC–SiC’s inherent properties limited its ability to withstand stress loads. Additionally, AI-driven uncertainty quantification and sensitivity analysis were conducted to assess the influence of material property variations on maximum hoop stress. The findings underscore the need for further research into high-temperature material properties to facilitate broader applicability of existing materials to advanced reactors. Haynes 230 is identified as the most promising candidate based on the evaluated criteria.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"186 ","pages":"Article 105793"},"PeriodicalIF":3.3,"publicationDate":"2025-04-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143868336","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