Bo Wang, Yan Zhang, Yang Yang, Zhengrong Guo, Jun Fan, Mingyang Li
{"title":"钠冷快堆原型蒸汽发生器的精细化数值分析","authors":"Bo Wang, Yan Zhang, Yang Yang, Zhengrong Guo, Jun Fan, Mingyang Li","doi":"10.1016/j.anucene.2025.111776","DOIUrl":null,"url":null,"abstract":"<div><div>This paper presents a comprehensive three-dimensional numerical simulation of a prototype steam generator for a sodium-cooled fast reactor. The model features a 1:1 geometric representation of the sodium side with detailed meshing, while the water side utilizes a User-Defined Function for accurate thermal modeling. The simulation integrates the coupled flow and heat transfer processes on both sides of the sodium-water steam generator. Validation against experimental data confirms the model’s reliability, showing good agreement in sodium temperature and heat load distribution under both rated and 28% power conditions. The study reveals detailed flow and heat transfer characteristics, including sodium-side flow fields, pressure fields, and temperature fields, as well as water-side fluid and wall temperatures and heat transfer coefficients. Results indicate a relatively uniform heat load distribution in most areas of the tube bundle. This work provides a robust theoretical foundation and effective technical support for the design optimization, performance improvement, and safety assessment of sodium-cooled fast reactor steam generators.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"225 ","pages":"Article 111776"},"PeriodicalIF":2.3000,"publicationDate":"2025-07-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Refined numerical analysis of prototype steam generator for sodium-cooled fast reactor\",\"authors\":\"Bo Wang, Yan Zhang, Yang Yang, Zhengrong Guo, Jun Fan, Mingyang Li\",\"doi\":\"10.1016/j.anucene.2025.111776\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>This paper presents a comprehensive three-dimensional numerical simulation of a prototype steam generator for a sodium-cooled fast reactor. The model features a 1:1 geometric representation of the sodium side with detailed meshing, while the water side utilizes a User-Defined Function for accurate thermal modeling. The simulation integrates the coupled flow and heat transfer processes on both sides of the sodium-water steam generator. Validation against experimental data confirms the model’s reliability, showing good agreement in sodium temperature and heat load distribution under both rated and 28% power conditions. The study reveals detailed flow and heat transfer characteristics, including sodium-side flow fields, pressure fields, and temperature fields, as well as water-side fluid and wall temperatures and heat transfer coefficients. Results indicate a relatively uniform heat load distribution in most areas of the tube bundle. This work provides a robust theoretical foundation and effective technical support for the design optimization, performance improvement, and safety assessment of sodium-cooled fast reactor steam generators.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"225 \",\"pages\":\"Article 111776\"},\"PeriodicalIF\":2.3000,\"publicationDate\":\"2025-07-30\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Annals of Nuclear Energy\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0306454925005936\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925005936","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Refined numerical analysis of prototype steam generator for sodium-cooled fast reactor
This paper presents a comprehensive three-dimensional numerical simulation of a prototype steam generator for a sodium-cooled fast reactor. The model features a 1:1 geometric representation of the sodium side with detailed meshing, while the water side utilizes a User-Defined Function for accurate thermal modeling. The simulation integrates the coupled flow and heat transfer processes on both sides of the sodium-water steam generator. Validation against experimental data confirms the model’s reliability, showing good agreement in sodium temperature and heat load distribution under both rated and 28% power conditions. The study reveals detailed flow and heat transfer characteristics, including sodium-side flow fields, pressure fields, and temperature fields, as well as water-side fluid and wall temperatures and heat transfer coefficients. Results indicate a relatively uniform heat load distribution in most areas of the tube bundle. This work provides a robust theoretical foundation and effective technical support for the design optimization, performance improvement, and safety assessment of sodium-cooled fast reactor steam generators.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.