Progress in Nuclear Energy最新文献_第3页

Phytic acid functionalized MOF-808 for seawater uranium extraction with high capacity and selectivity 植酸功能化MOF-808高容量、高选择性海水提铀

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-20 DOI: 10.1016/j.pnucene.2025.106059

Bing Han, Zhiwei Zhao, Yijia Xu, Wencheng Yao, Yue Wen, Qi Wang, Zhuo Wang, Yuejie Ai

{"title":"Phytic acid functionalized MOF-808 for seawater uranium extraction with high capacity and selectivity","authors":"Bing Han, Zhiwei Zhao, Yijia Xu, Wencheng Yao, Yue Wen, Qi Wang, Zhuo Wang, Yuejie Ai","doi":"10.1016/j.pnucene.2025.106059","DOIUrl":"10.1016/j.pnucene.2025.106059","url":null,"abstract":"<div><div>The efficient extraction of uranium from seawater plays an important role to guarantee a sustainable nuclear energy industry. Zr-based metal-organic frameworks (MOFs) are promising uranium adsorbents due to their high stability, customizable functionality and adjustable topological structure. In this study, Zr based MOF-808 with tunable phytic acid (PA) functionalization (MOF-808-PA1 and MOF-808-PA2) were prepared. The modulation of PA modification significantly promoted the uranium extraction of MOF-808 with the saturated adsorption capacity reaching 423.89 mg/g and adsorption equilibrium achieved in 15 min in aqueous solution. Impressively, MOF-808-PA2 exhibited superior selectivity towards uranium with the distribution coefficient up to 9.2 × 10<sup>5</sup> mL/g, which overwhelms other competitive ions in simulated seawater. After adsorption in real seawater for 28 days, uranium capture capacity of MOF-808-PA2 reached 7.85 mg/g, 8 times higher than that of vanadium. DFT simulation indicated that the excellent seawater uranium extraction performance originated from the strong affinity between abundant P-O/P=O and uranyl ions. This work highlights the design of high-performance uranium adsorbents based on functional group modification in MOFs system.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106059"},"PeriodicalIF":3.2,"publicationDate":"2025-09-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145099326","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

Nuclear accident source term inversion based on explainable machine learning methods 基于可解释机器学习方法的核事故源项反演

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-19 DOI: 10.1016/j.pnucene.2025.106051

Dingping Peng , Bo Cao , Zhonghao Li , Xuewei Miao , Qingyue You

{"title":"Nuclear accident source term inversion based on explainable machine learning methods","authors":"Dingping Peng , Bo Cao , Zhonghao Li , Xuewei Miao , Qingyue You","doi":"10.1016/j.pnucene.2025.106051","DOIUrl":"10.1016/j.pnucene.2025.106051","url":null,"abstract":"<div><div>Traditional source term inversion models rely on accurate a priori information as well as atmospheric dispersion simulations, leading to time-consuming source term inversion procedures. Previous studies have used machine learning (ML) methods such as neural networks to construct source term inversion models, which exhibit excellent inversion performance but usually lack model interpretability and have complex model structure and parameter tuning. To address this problem, an interpretable nuclear accident source term inversion model using ensemble learning combined with the SHapely Additive exPlanation (SHAP) method was developed in this study to estimate the nuclide release rate and the 2D location of the release point. In the model construction, Gaussian plume model is utilized to obtain data samples. To evaluate the adaptability of the model to accident scenarios, the model was trained under two types of accidents, known and unknown at the release point. The validity and accuracy of the model were assessed using statistical metrics, including the coefficient of determination (R<sup>2</sup>), root mean square error (RMSE), mean absolute percentage error (MAPE), and mean distance error (MDE). The CatBoost model showed the best performance in both scenarios compared to the other three models. Model feature importance calculations and SHAP analyses revealed that the radioactivity concentration monitoring data had the greatest impact on the model inversion performance in both scenarios, and wind speed was an important parameter for this inversion model. Variations in meteorological parameters critically impair the reliability of source term inversion under unknown release scenarios.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106051"},"PeriodicalIF":3.2,"publicationDate":"2025-09-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145099379","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

Intelligent layout of nuclear pipeline system with mechanical constraint 带机械约束的核管道系统智能布置

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-18 DOI: 10.1016/j.pnucene.2025.106022

Yuxiang Sun , Li Chen , Yanping Wang , Shihua Liu , Kun Jia

{"title":"Intelligent layout of nuclear pipeline system with mechanical constraint","authors":"Yuxiang Sun , Li Chen , Yanping Wang , Shihua Liu , Kun Jia","doi":"10.1016/j.pnucene.2025.106022","DOIUrl":"10.1016/j.pnucene.2025.106022","url":null,"abstract":"<div><div>The layout of pipeline systems in nuclear plant including path planning and support arrangement is achieved manually. Trials and iterations are inevitable in the design process to meet mechanical constraints, such as the strength criterion. The approach suffers from heavy labor intensity, long design cycles, and high costs. In this study, we propose an intelligent layout method that combines the reinforcement learning with an optimization algorithm to satisfy both spatial and mechanical constraints in nuclear plant design. We first employ the Q-learning algorithm to solve the path planning of pipeline in a determined space with obstacles. The Q-learning algorithm makes a pipeline layout with a total length of 22,000 mm and 5 bends, overweighing the traditional Ant-colony algorithm (26,000 mm-length and 13 bends) and NSGA-II (26,000 mm-length and 12 bends). When the stress of the arranged pipeline exceeds the threshold value, the algorithm combining Particle Swarm Optimization (PSO) and Genetic Algorithm (GA) is used for the intelligent layout of supports, where the optimal number and positions of supports are automatically determined with a balance between meeting economic costs and design criteria for mechanical responses. The layout example shows the optimal arrangement of three supports. Further increasing the number of supports, the maximum stress stabilizes. Increasing the cost with additional supports becomes ineffective. The proposed intelligent method reduces the expertise dependence of pipeline layout and can be easily extended to other industrial fields.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106022"},"PeriodicalIF":3.2,"publicationDate":"2025-09-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145099378","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

Fuel optimization and transient analysis of a medium temperature heat pipe reactor 中温热管反应堆燃料优化与瞬态分析

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-18 DOI: 10.1016/j.pnucene.2025.106049

Zenghao Liu , Laishun Wang , Chen Hu , Binhuo Yan

{"title":"Fuel optimization and transient analysis of a medium temperature heat pipe reactor","authors":"Zenghao Liu , Laishun Wang , Chen Hu , Binhuo Yan","doi":"10.1016/j.pnucene.2025.106049","DOIUrl":"10.1016/j.pnucene.2025.106049","url":null,"abstract":"<div><div>Micro reactors, particularly Heat Pipe cooled Reactors (HPRs), have been recognized as leading candidates for decentralized electricity markets due to their inherent safety, compact size, and transportability. However, conventional HPRs are operated at high temperatures, posing challenges related to material corrosion, thermal stresses, and startup failures. To address these issues, Medium Temperature Heat Pipe cooled Reactors (MTRs) operating at 350 °C have been proposed. In this work, three representative fuels are systematically evaluated: uranium-zirconium hydride (U-ZrH<sub>1.6</sub>), uranium dioxide (UO<sub>2</sub>), and uranium-silicide composite (U<sub>3</sub>Si<sub>2</sub>-Al). All three fuels are indicated by steady-state calculations to be suitable for normal operation of MTR. Transient simulations are conducted to assess the behavior of fuels under single and multiple heat pipe failure situations. Results are shown to indicate that while the centerline temperatures of all fuels remain below their respective melting points, the maximum temperature of U<sub>3</sub>Si<sub>2</sub>-Al fuel is found to exceed the recommended safety threshold. Although the U-ZrH<sub>1.6</sub> fuel is considered to exhibit slightly better neutron economic performance than UO<sub>2</sub>, its safety margin is determined to be significantly lower than that of UO<sub>2</sub>. In conclusion, UO<sub>2</sub> is identified as the preferred fuel candidate for MTR.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106049"},"PeriodicalIF":3.2,"publicationDate":"2025-09-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145099377","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 hybrid Lagrangian-artificial intelligence model for predicting the 3D dispersion of radionuclides in the Persian Gulf, part I: Validation 用于预测波斯湾放射性核素三维扩散的混合拉格朗日-人工智能模型，第一部分：验证

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-17 DOI: 10.1016/j.pnucene.2025.106023

Maryam Mohammadi , Ahmad Pirouzmand , Kamal Hadad , Abdorreza Alavi Gharahbagh

{"title":"A hybrid Lagrangian-artificial intelligence model for predicting the 3D dispersion of radionuclides in the Persian Gulf, part I: Validation","authors":"Maryam Mohammadi , Ahmad Pirouzmand , Kamal Hadad , Abdorreza Alavi Gharahbagh","doi":"10.1016/j.pnucene.2025.106023","DOIUrl":"10.1016/j.pnucene.2025.106023","url":null,"abstract":"<div><div>Assessing the behavior of radionuclides in the environment following nuclear accidents is critical for maintaining and enhancing the effectiveness of emergency preparedness and response programs. The Persian Gulf (PG), a marine environment with rich oil and gas resources, is one of the world's key waterways. The proximity of several nuclear power plants (NPPs) magnifies the need to study the dispersion of radioactive materials after an accident in this region. This paper is the first part of a research that aims to develop an emergency model to predict the three-dimensional (3D) distribution of radionuclides in the PG. The first part introduces and validates a Lagrangian transport model to predict radionuclide dispersion in the PG. As a necessary step, a hydrodynamic model based on ANNs is implemented to forecast 3D current fields, including baroclinic, wind-induced, and tidal currents. These predicted currents are then used as input for the transport model. The proposed transport model incorporates advection, diffusion, decay, and water-sediment interactions. The calculated results demonstrated the importance of using real wind and tidal data in the transport model. A temporal analysis of radionuclide dispersion in the PG is also conducted.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106023"},"PeriodicalIF":3.2,"publicationDate":"2025-09-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145099376","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

Uranium diboride: Understanding and optimizing arc-melt synthesis 二硼化铀：理解和优化电弧熔体合成

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-17 DOI: 10.1016/j.pnucene.2025.106021

M. Khair , J.H. Stansby , P. Bragado , J. Stone , E.S. Sooby

{"title":"Uranium diboride: Understanding and optimizing arc-melt synthesis","authors":"M. Khair , J.H. Stansby , P. Bragado , J. Stone , E.S. Sooby","doi":"10.1016/j.pnucene.2025.106021","DOIUrl":"10.1016/j.pnucene.2025.106021","url":null,"abstract":"<div><div>Uranium diboride (UB<sub>2</sub>) is considered as a nuclear fuel candidate or burnable absorber for advanced reactors. The present study investigates the arc-melt synthesis of UB<sub>2</sub> and aims to improve understanding and reproducibility of the fabrication method. UB<sub>2</sub>-U, UB<sub>2</sub>, and UB<sub>2</sub>-UB<sub>4</sub> compounds are synthesized and characterized by X-ray diffraction and scanning electron microscopy. Direct addition of < ∼7 wt% boron excess, in a single step, results in formation of UB<sub>2</sub>-U, while addition of >∼10 wt% boron excess leads to the formation of UB<sub>2</sub>-UB<sub>4</sub>. Diffraction data shows that material loss during the melt, previously assumed to be volatilization of boron, comprises both uranium and boron in the forms of UB<sub>2</sub> and UB<sub>4</sub>. To mitigate material loss during the melt and facilitate the fabrication of pure UB<sub>2</sub>, a stoichiometric amount of boron is incrementally dissolved into uranium metal using relatively low current (<100 A for 2 g of uranium); after all the boron is incorporated, the ingot is fully melted. Alternatively, microscopy images of UB<sub>2</sub>-U composites can be analyzed to determine the amount of additional boron needed to obtain the UB<sub>2</sub> line compound. In short, this paper details the best practices for the reproducible fabrication of pure UB<sub>2</sub> using the arc-melt method. These methods can be extended to other line compounds where volatilization and high melt temperatures complicate synthesis.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106021"},"PeriodicalIF":3.2,"publicationDate":"2025-09-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145099375","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 three-dimensional space path planning method based on A∗ algorithm in radiation environment 辐射环境下基于A *算法的三维空间路径规划方法

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-17 DOI: 10.1016/j.pnucene.2025.106042

Yu-Chen Li , Zi-Hui Yang , Hao Tian , Zhong-Yang Li , Qian-Chao Huo , Guo-Min Sun , Shi-Peng Wang , Qi-sheng Chen , Juan Fu , Gui-Hua Tao

{"title":"A three-dimensional space path planning method based on A∗ algorithm in radiation environment","authors":"Yu-Chen Li , Zi-Hui Yang , Hao Tian , Zhong-Yang Li , Qian-Chao Huo , Guo-Min Sun , Shi-Peng Wang , Qi-sheng Chen , Juan Fu , Gui-Hua Tao","doi":"10.1016/j.pnucene.2025.106042","DOIUrl":"10.1016/j.pnucene.2025.106042","url":null,"abstract":"<div><div>Path planning is a critical radiation protection strategy designed to minimize radiation exposure for personnel involved in nuclear emergency response. In many practical scenarios, path planning within a radiation environment is inherently a three-dimensional (3D) problem. Existing 3D path planning methods have predominantly targeted robot navigation and UAV flight operations in non-radiation scenarios, typically overlooking radiation dose exposure. However, in nuclear emergency situations, personnel frequently need to perform operational tasks within radiation environments, necessitating strict control over their radiation exposure levels. Consequently, existing 3D path planning methods developed for robots and UAVs may be unsuitable for human operations, underscoring the need for targeted research into 3D path planning specifically for personnel operating in radiation-contaminated environments. 3D path planning in radiation environments faces two primary challenges: accurately modeling the 3D radiation field and developing a path planning approach that concurrently considers both travel distance and radiation dose exposure. To address these challenges, we propose an innovative three-dimensional A* algorithm (TDA) explicitly tailored for radiation environments. Additionally, this study utilizes the standardized Rad-HUMAN voxel model to accurately simulate human anatomy, combined with GPU-based parallel computing techniques to achieve precise and efficient radiation dose assessments during path traversal. Two simulation experiments have been conducted to validate the method’s feasibility and demonstrate the advantages of the proposed path planning method.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106042"},"PeriodicalIF":3.2,"publicationDate":"2025-09-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145099374","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 assessment of in-vessel corium retention in PHWR during severe accident 严重事故中PHWR容器内堆芯滞留的数值评价

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-17 DOI: 10.1016/j.pnucene.2025.106045

Parthkumar Rajendrabhai Patel, Nilesh Agrawal, Seik Mansoor Ali, D.K. Mohapatra

{"title":"Numerical assessment of in-vessel corium retention in PHWR during severe accident","authors":"Parthkumar Rajendrabhai Patel, Nilesh Agrawal, Seik Mansoor Ali, D.K. Mohapatra","doi":"10.1016/j.pnucene.2025.106045","DOIUrl":"10.1016/j.pnucene.2025.106045","url":null,"abstract":"<div><div>Under a hypothetical design extension condition involving core melt (also called severe accident), the PHWR calandria is expected to retain core debris/melt pool and safely terminate the event. The study presents numerical investigations on in-vessel retention (IVR) of corium within the PHWR calandria for a scenario in which the entire reactor core has disassembled, relocated, and subsequently melted upon interaction with the calandria vessel. A two-phase model capable of simulating melting and solidification within the corium region is employed. The model accounts for temperature variations along the inner surface of the calandria vessel by incorporating radiative heat transfer from the corium to the vessel wall, implemented through appropriate user-defined boundary conditions. The developed model is used to analyse corium crust formation and the resulting heat flux at the outer surface of the calandria vessel. From the assessment, it is found that for PHWRs radiation heat transfer from top surface of corium plays crucial role in IVR as it reduces heat flux from corium bottom surface. Sensitivity analyses are performed to evaluate the influence of uncertainties in key input parameters on the effectiveness of in-vessel retention in the PHWR under severe accident conditions.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106045"},"PeriodicalIF":3.2,"publicationDate":"2025-09-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145099516","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 clab decay heat measurements from 2003 to 2021 under EPRI-SKB collaboration 2003 - 2021年EPRI-SKB合作下的clab衰变热测量评估

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-15 DOI: 10.1016/j.pnucene.2025.106001

Hatice Akkurt , Robert Hall , Fredrik Johansson , Amela Mehic , Jesper Kierkegaard , Henrik Liljenfeldt

{"title":"Evaluation of clab decay heat measurements from 2003 to 2021 under EPRI-SKB collaboration","authors":"Hatice Akkurt , Robert Hall , Fredrik Johansson , Amela Mehic , Jesper Kierkegaard , Henrik Liljenfeldt","doi":"10.1016/j.pnucene.2025.106001","DOIUrl":"10.1016/j.pnucene.2025.106001","url":null,"abstract":"<div><div>Accurate estimation of decay heat for spent nuclear fuel is important for wet storage (spent fuel pool heat management), cask/canister loading campaigns (ensuring that temperature limits are met), dry storage system aging management, transportation, and eventual disposal. Clab decay heat measurements performed between 2003 and 2004 were published in 2006 and used across the globe for computer code validation purposes. Currently, Clab is the only facility in the world that performs full assembly decay heat measurements. Recently, EPRI and SKB entered into a collaborative agreement to evaluate and publish all Clab decay heat measurements performed between 2003 and 2021. The publicly available publication has not only extended the decay heat validation range significantly but has also improved characterization and evaluation of the measurements, including associated uncertainties.</div><div>In this paper, an overview of Clab decay heat measurements and evaluation of the measurement uncertainties for the decay heat measurements performed between 2003 and 2021 are presented. Clab measurement uncertainty is re-evaluated to include previously unpublished calibration data, to assess the impact of data quality screening, and to review and revise certain prior conservative assumptions. The re-evaluation relies primarily on the accumulated population of Clab measured data. Finally, lessons learned and recommendations for future decay heat measurements are provided.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106001"},"PeriodicalIF":3.2,"publicationDate":"2025-09-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145060292","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

An in-situ multipoint optical fiber temperature sensor with applications to small modular reactors and thermal energy storage systems 一种原位多点光纤温度传感器，应用于小型模块化反应器和热能储存系统

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-09-13 DOI: 10.1016/j.pnucene.2025.106044

Yongqiang Deng, Jin Jiang

{"title":"An in-situ multipoint optical fiber temperature sensor with applications to small modular reactors and thermal energy storage systems","authors":"Yongqiang Deng, Jin Jiang","doi":"10.1016/j.pnucene.2025.106044","DOIUrl":"10.1016/j.pnucene.2025.106044","url":null,"abstract":"<div><div>A novel multipoint optical fiber temperature sensor architecture has been proposed to address temperature measurement problems often encountered in SMRs (small modular reactors) and thermal energy storage (TES) systems. This new sensor can be submerged into working fluids to acquire reliable <em>in-situ</em> temperature measurements for multiple locations simultaneously. The spatial resolution of the measurement locations can be controlled by the spacing of Fiber Bragg Gratings (FBGs). This multipoint sensor utilizes interlaced conductor-insulator-conductor sheath design to provide high speed of response and reduce probe-induced thermal smearing. This sensor is particularly suited for capturing nonuniform temperature distributions during transient operations of an SMR and a TES, which thermocline needs to be accurately monitored. This paper describes the principle of the sensor design, thermal and heat transfer analysis by finite element analysis, and experimental evaluation using wax to create a phase change environment to mimic properties of molten salts often found in advanced SMRs and TES. Both numerical analysis and experimental investigation have confirmed that the proposed multipoint optical fiber sensor can achieve reliable and accurate <em>in-situ</em> temperature measurements in environments where traditional temperature sensors, such as thermocouples, are cumbersome to be used.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106044"},"PeriodicalIF":3.2,"publicationDate":"2025-09-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145047172","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