Research on flow and heat transfer characteristics of built-in cooling system in shaft sealed reactor coolant pump

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-07-03 DOI:10.1016/j.anucene.2025.111698

Kun Tang , Yizhu Yang , Bin Yin , Xiyuan Cao , Wei Fu , Liang Zhao , Hui Dong

{"title":"Research on flow and heat transfer characteristics of built-in cooling system in shaft sealed reactor coolant pump","authors":"Kun Tang , Yizhu Yang , Bin Yin , Xiyuan Cao , Wei Fu , Liang Zhao , Hui Dong","doi":"10.1016/j.anucene.2025.111698","DOIUrl":null,"url":null,"abstract":"<div><div>The built-in cooling system (BCS) constitutes a critical component of reactor coolant pump (RCP), whose structure is fundamentally determined by the nuclear reactor. Four-bearing mechanical-seal centrifugal pump is widely used in RCP. Operating parameters significantly influence the flow and heat transfer mechanisms in BCS, thereby affecting the service life and operational stability of RCP. Current research on the flow and heat transfer characteristics of BCS lacks comprehensive numerical simulations, which results in insufficient understanding of RCP fundamental operational mechanisms. Therefore, it is necessary to analyze the flow and heat transfer characteristics of BCS. A numerical simulation model established to simulate accurately the multi-passage large-span variable cross-section geometric structural characteristics of BCS in a certain RCP. An experimental platform is constructed for verification, and the flow and heat transfer patterns in BCS under standard operating conditions are obtained. Consequently, the influences of operational parameters on resistance and internal flow distribution are investigated.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"224 ","pages":"Article 111698"},"PeriodicalIF":2.3000,"publicationDate":"2025-07-03","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/S0306454925005158","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}

引用次数: 0

Abstract

The built-in cooling system (BCS) constitutes a critical component of reactor coolant pump (RCP), whose structure is fundamentally determined by the nuclear reactor. Four-bearing mechanical-seal centrifugal pump is widely used in RCP. Operating parameters significantly influence the flow and heat transfer mechanisms in BCS, thereby affecting the service life and operational stability of RCP. Current research on the flow and heat transfer characteristics of BCS lacks comprehensive numerical simulations, which results in insufficient understanding of RCP fundamental operational mechanisms. Therefore, it is necessary to analyze the flow and heat transfer characteristics of BCS. A numerical simulation model established to simulate accurately the multi-passage large-span variable cross-section geometric structural characteristics of BCS in a certain RCP. An experimental platform is constructed for verification, and the flow and heat transfer patterns in BCS under standard operating conditions are obtained. Consequently, the influences of operational parameters on resistance and internal flow distribution are investigated.

查看原文本刊更多论文

轴封式反应堆冷却剂泵内置冷却系统的流动与传热特性研究

内建冷却系统（BCS）是反应堆冷却剂泵（RCP）的关键部件，其结构从根本上决定于核反应堆本身。四轴承机械密封离心泵在RCP中应用广泛。运行参数对BCS内的流动和换热机制有重要影响，从而影响RCP的使用寿命和运行稳定性。目前对BCS流动和换热特性的研究缺乏全面的数值模拟，导致对RCP基本运行机理的认识不足。因此，有必要对BCS的流动和传热特性进行分析。为准确模拟某RCP中BCS多通道大跨度变截面几何结构特性，建立了数值模拟模型。搭建了实验平台进行验证，得到了标准工况下BCS内部的流动和传热规律。因此，研究了操作参数对阻力和内部流动分布的影响。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

来源期刊

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

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.