Progress in Nuclear Energy最新文献_第7页

GTES: A GNDS format nuclear data processing code interfacing AXSP

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.pnucene.2024.105567

Wenming Yi , Xubo Ma , Kui Hu

{"title":"GTES: A GNDS format nuclear data processing code interfacing AXSP","authors":"Wenming Yi , Xubo Ma , Kui Hu","doi":"10.1016/j.pnucene.2024.105567","DOIUrl":"10.1016/j.pnucene.2024.105567","url":null,"abstract":"<div><div>The Generalized Nuclear Data Structure (GNDS) is a new evaluated nuclear data format designed to replace the traditional ENDF-6 format. GNDS offers improved readability and easier expandability compared to ENDF-6. In this study, a new nuclear data processing code, GTES, written in the object-oriented language C#, has been developed for converting between GNDS and ENDF-6 formats. GTES interfaces with the advanced cross-section processing code AXSP, transforming GNDS-2.0 and generating ENDF-6 format structure files, which can be used for further calculations with AXSP. To verify the correctness of the GTES processing, the generated files have been processed into ACE format cross-sections by AXSP, and the Monte Carlo transport code RMC is used for criticality calculations to verify the accuracy of the results. The calculation results indicate that GTES can successfully process ENDF/B-VIII.0 evaluated nuclear data in GNDS-2.0 format. The cross-section data and criticality benchmark calculation results processed by AXSP are in good agreement with experimental results, although there are certain differences in some data when compared to the ENDF/B-VIII.0 evaluated nuclear data in ENDF-6 format. However, the calculation results are in excellent agreement with the results of transforming GNDS-2.0 format to ENDF/B-VIII.0 using FUDGE.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105567"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141647","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

Generalized Hébert method for double-heterogeneity problem

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.pnucene.2024.105573

Zhaoyu Liang , Ding She , Yutong Wen , Lei Shi , Zuoyi Zhang

引用次数: 0

A new fuel shuffling model for treating the random burnup histories of pebble-bed reactor

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.pnucene.2024.105571

Hongwei Wu , Yutong Wen , Bing Xia , Ding She , Zuoyi Zhang

引用次数: 0

Improved dynamic fuzzy neural network-based power control for the load following of lead-cooled fast reactor

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.pnucene.2024.105594

Yanyi Shen , Wenshun Duan , Sifan Dong , Junjie Tang , Hongli Chen

{"title":"Improved dynamic fuzzy neural network-based power control for the load following of lead-cooled fast reactor","authors":"Yanyi Shen , Wenshun Duan , Sifan Dong , Junjie Tang , Hongli Chen","doi":"10.1016/j.pnucene.2024.105594","DOIUrl":"10.1016/j.pnucene.2024.105594","url":null,"abstract":"<div><div>The load following of lead-cooled fast reactor (LFR) plays a critical role in ensuring the safe and efficient operation of nuclear power plants (NPPs). Although the research on intelligent control for power control has been conducted. Motivated by pronounced instability in operating parameters of LFR during load following, an intelligent control method based on an improved dynamic fuzzy neural network (IDFNN) is proposed in this study. The IDFNN adopts a flexible and simple network architecture to achieve online learning through structure growth algorithm and pruning algorithm. To test the performance of the data-driven power control, a unique co-simulation method is adopted. Online data of nuclear reactor system is generated using RELAP5 code, data interaction between online data and controllers is achieved through data interface, and the controllers are implemented by IDFNN. The outstanding control performance and robustness of the IDFNN-based power control are evaluated with a fuzzy PID controller and a PID controller in the load following operation. Additionally, It brings LFR back to normal operating after reactivity insertion accident.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105594"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141789","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

Irradiation-induced thermo-mechanical coupling method and deformation behaviors of hafnium control rod in the research reactor

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.pnucene.2024.105575

Haoyu Wang , Qi Zhang , Zengping Pu , Yuanming Li , Lei Shi , Feipeng Qi , Pan Yuan , LeLe Zheng

{"title":"Irradiation-induced thermo-mechanical coupling method and deformation behaviors of hafnium control rod in the research reactor","authors":"Haoyu Wang , Qi Zhang , Zengping Pu , Yuanming Li , Lei Shi , Feipeng Qi , Pan Yuan , LeLe Zheng","doi":"10.1016/j.pnucene.2024.105575","DOIUrl":"10.1016/j.pnucene.2024.105575","url":null,"abstract":"<div><div>The hafnium control rod is commonly used in research reactors due to hafnium's exceptional overall performance. As the reactor core is not uniformly irradiated, the hafnium control rod may get stuck due to irradiation-induced deformation, which will cause a serious accident. In the presented study, a novel approach of the irradiation-induced thermo-mechanical coupling method for the hafnium control rod is developed, which considers the heterogeneous fast neutron flux and heat production in the reactor core. The newly developed modeling method is used to analyze the irradiation deformation behavior of the hafnium control rod in the JRR-3M research reactor. The simulation results indicate that the control rod needs to be replaced after 8 years to prevent it from being stuck due to irradiation-induced deformation, which matches the operation experience of JRR-3M. Therefore, the effectiveness of the newly developed modeling method are conformed. The results indicate that (1) the temperature profile of the hafnium control rod remains nearly constant throughout its lifetime, with a maximum temperature of 496.2 K at the end of its life. (2) the control rod experiences a gradual C-shaped deformation along its length, resulting in maximum axial and lateral displacements of 6.041 mm and −1.558 mm, respectively, over a period of 5000 days. (3) as the operation time increases, the irradiation-induced deformation continues to increase at the upper end of the control rod, while it increases first and then decreases at the middle and lower ends. This phenomenon is caused by the saturation effect of hafnium irradiation growth. (4) the hafnium control rod as a whole experiences low levels of stress throughout its lifetime. Additionally, the relatively large stress caused by thermal expansion strain at the beginning of its life gradually diminishes as a result of irradiation-induced creep over time.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105575"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141790","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 efficient method for solving flow field in high temperature gas-cooled reactor

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.pnucene.2024.105599

Haojie Zhang, Bo Tan, Ding She, Lei Shi

{"title":"An efficient method for solving flow field in high temperature gas-cooled reactor","authors":"Haojie Zhang, Bo Tan, Ding She, Lei Shi","doi":"10.1016/j.pnucene.2024.105599","DOIUrl":"10.1016/j.pnucene.2024.105599","url":null,"abstract":"<div><div>In thermal-hydraulic analysis of pebble-bed high temperature gas-cooled reactor (HTR), the flow field calculation is a crucial and time-consuming process. It can be treated as a mathematical problem of solving sparse linear algebraic equations, which can be solved by direct method or iterative method. By analyzing the geometric model and flow field in HTR, it is found that the flow field consists of one-dimensional (1D) and multidimensional regions. Based on the characteristics of fluid flow in pebble-bed HTR, some acceleration methods are presented in this paper, including a new matrix reordering method, symbolic factorization and block matrix solving. The main idea of matrix reordering is to arrange the 1D regions in a specific order in front of the matrix, while the other regions are placed at the back. After reordering, the fill-ins in Gauss elimination can be greatly reduced, so the direct method can be speed up. The reordered matrix is also suitable for using block matrix solvers to enhance the efficiency of matrix solving. In addition, symbolic factorization is also an efficient technique to reduce the time cost in Gauss elimination by recording the fill-ins and the elimination process. These acceleration techniques can be integrated with matrix solvers to form a variety of solving methods, which have been implemented in the DAYU3D code developed in Institute of Nuclear and New Energy Technology (INET) at Tsinghua University. To evaluate the efficiency of these methods, calculations have been performed on a number of typical cases of pebble-bed HTR. It was found that Gauss elimination coupled with matrix reordering and symbolic factorization techniques, has remarkable advantage compared with other solvers. In comparison to Gauss elimination, about 84%–94% reduction in fluid matrix solving time is observed in the test cases of pebble-bed HTR.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105599"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141794","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

Dynamic analysis code development for space nuclear power systems

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.pnucene.2024.105601

Baihui Jiang , Yu Ji , Jun Sun , Qian Sun , Lei Shi

{"title":"Dynamic analysis code development for space nuclear power systems","authors":"Baihui Jiang , Yu Ji , Jun Sun , Qian Sun , Lei Shi","doi":"10.1016/j.pnucene.2024.105601","DOIUrl":"10.1016/j.pnucene.2024.105601","url":null,"abstract":"<div><div>Space nuclear power systems (SNPs) are considered an optimal power solution for future space missions. Among various system designs, a gas-cooled reactor coupled with closed Brayton cycle energy conversion systems has emerged as one of the most promising options for generating electrical power in the range of hundreds to thousands of kilowatts. Due to strong parameter coupling, small design margins, and limited control strategies, a reliable and accurate dynamic analysis tool is essential for the optimization and operation safety of SNPs. In this paper, RELAP5 is modified to support the dynamic analysis of these systems, following a comparison between the original code capabilities and the simulation requirements for SNPs. A compressor model and a turbine model are developed, and the heat transfer model is adapted for compact counterflow heat exchangers. Additionally, the convective and radiation heat transfer models are modified for open lattice reactors with compact rod bundles. The accuracy of the modified RELAP5 is verified through comparisons with results from the system design code Megrez, the CFD simulations and the JIMO reports. The results confirm that the dynamic analysis code developed in this paper is suitable for transient analysis of SNPs.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105601"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141795","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 the influence of gas injection on flashing in open natural circulation systems under stable boundary conditions

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.pnucene.2024.105541

Shengnan zhang , Wuqing Lin , Zhaoming Meng , Zhongning Sun , Nan Zhang

{"title":"Experimental study on the influence of gas injection on flashing in open natural circulation systems under stable boundary conditions","authors":"Shengnan zhang , Wuqing Lin , Zhaoming Meng , Zhongning Sun , Nan Zhang","doi":"10.1016/j.pnucene.2024.105541","DOIUrl":"10.1016/j.pnucene.2024.105541","url":null,"abstract":"<div><div>As an efficient passive heat exchange system, natural circulation systems are widely used in various fields, including passive containment cooling system in nuclear power plants. Flashing is the most common two-phase flow state in natural circulation systems. To enhance the circulation capacity and stability of natural circulation systems, this study conducts experiments on the effects of gas injection on flashing two-phase flow using water and air as mediums. The research analyzes the impact of different gas injection positions and volumes on the flow rate, flow pattern, flow instability, and void fraction of the flashing flow. The results indicate that gas injection enhances the circulation flow rate of the loop and improves system stability. The further the gas injection position is from the upstream of the flashing point, the better the enhancement effect on the circulation flow rate. As the gas injection volume increases, the circulation capacity of the loop strengthens; however, once a certain injection volume is reached, the circulation capacity no longer increases, with a maximum enhancement of up to 80% in circulation flow rate. The introduction of gas injection leads to significant fluctuations in the axial distribution of the void fraction in the rising section, but has a negligible effect on the bubble fraction at the exit of the rising section. The paper analyzes the pressure drops and driving force fractions in the rising section before and after gas injection, and presents the mechanisms by which different gas injection positions and amounts affect the flow in the loop. These findings provide important insights for enhancing and stabilizing natural circulation systems, contributing to improved design and operation of passive safety shell cooling systems.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105541"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141575","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

Independent Nuclide Simulation Method (INSM) – A depletion algorithm for simulating the intermediate process of nuclide transmutation

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.pnucene.2025.105635

Dongyuan Li, Qingquan Pan, Xiaojing Liu

引用次数: 0

Experimental study on condensation heat transfer of water-ethanol vapour mixtures inside inclined tubes

IF 3.3 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-02-01 DOI: 10.1016/j.pnucene.2024.105577

Ziqiang Ma , Yong Li , Guangyao Liu , Jun Yang , Jinshi Wang

{"title":"Experimental study on condensation heat transfer of water-ethanol vapour mixtures inside inclined tubes","authors":"Ziqiang Ma , Yong Li , Guangyao Liu , Jun Yang , Jinshi Wang","doi":"10.1016/j.pnucene.2024.105577","DOIUrl":"10.1016/j.pnucene.2024.105577","url":null,"abstract":"<div><div>Marangoni condensation is a new way to form dropwise condensation mode, which has significant potential applications in the industrial field. However, condensation with binary mixtures inside tubes, which can achieve pseudo-dropwise condensation mode is limited. This study experimentally investigated the heat transfer characteristic of water-ethanol vapour mixtures inside inclined tubes with an inner diameter of 21 mm. Experiments were conducted at inclination angles of 0°, −10°, and −30°, vapour mass fluxes of 10.81, 16.22, 21.62, and 27.03 kg•m<sup>−2</sup>•s<sup>−1</sup>, coolant flow rates of 1000 and 1800 kg•h<sup>−1</sup>, and thermal differentials from 15 K to 60 K. The results demonstrated that pseudo-dropwise condensation mode can be formed in the condensation of water-ethanol vapour mixtures inside macro-scale tubes. As vapour mass flux increased, flow regimes transformed from stratified-droplet to wavy-droplet flow. The heat transfer coefficients increased with the increase in coolant flow rates. When the coolant flow rate increased from 1000 to 1800 kg•h<sup>−1</sup>, condensation heat transfer coefficients in four segments increased by 38.12%, 11.75%, 24.51%, and 9.67%, respectively. The thermal transfer increased with inclination angles in the first condensation segment. Additionally, heat transfer was found to be increased with vapour qualities. These findings provide valuable insights for optimizing heat transfer processes in nuclear systems, where precise control of condensation dynamics is essential for safe and efficient operation.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"180 ","pages":"Article 105577"},"PeriodicalIF":3.3,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143141649","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