Weihua Liao , Wanzong Li , Longxiang Zhu , Zaiyong Ma
{"title":"Study of cross-flow characteristics in sub-channels with numerical simulation","authors":"Weihua Liao , Wanzong Li , Longxiang Zhu , Zaiyong Ma","doi":"10.1016/j.anucene.2025.111856","DOIUrl":null,"url":null,"abstract":"<div><div>The study of the cross-flow mixing effects between adjacent sub-channels in an open channel is significant for quantifying the net mass transfer and the resulting momentum and energy exchange between channels in the fuel assembly. This paper investigates the local physical characteristics of cross-flow in a 1 × 2 rod bundle sub-channel without and with grids using numerical simulation. It focuses on analyzing the lateral flow under two scenarios: differences in inlet flow rates and differences in outlet flow rates. The analysis of the pressure differential across the channels and the distribution of cross-flow velocity reveals that the pressure differential exhibits an exponential variation trend along the axial direction in both scenarios. Additionally, this paper fits empirical relationships for the lateral cross-flow friction coefficient under different mainstream velocities. It compares the differences in friction coefficients between the two scenarios and the influence of various mainstream velocities on the friction coefficient. Moreover, the comparison of the total cross-flow between channels with and without a grid shows that the cross-flow with the grid is greater than the cross-flow without a grid under the same condition, indicating that the existence of a grid can enhance the cross-flow between sub-channels and balance the uneven flow between sub-channels.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"226 ","pages":"Article 111856"},"PeriodicalIF":2.3000,"publicationDate":"2025-09-03","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/S0306454925006735","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 study of the cross-flow mixing effects between adjacent sub-channels in an open channel is significant for quantifying the net mass transfer and the resulting momentum and energy exchange between channels in the fuel assembly. This paper investigates the local physical characteristics of cross-flow in a 1 × 2 rod bundle sub-channel without and with grids using numerical simulation. It focuses on analyzing the lateral flow under two scenarios: differences in inlet flow rates and differences in outlet flow rates. The analysis of the pressure differential across the channels and the distribution of cross-flow velocity reveals that the pressure differential exhibits an exponential variation trend along the axial direction in both scenarios. Additionally, this paper fits empirical relationships for the lateral cross-flow friction coefficient under different mainstream velocities. It compares the differences in friction coefficients between the two scenarios and the influence of various mainstream velocities on the friction coefficient. Moreover, the comparison of the total cross-flow between channels with and without a grid shows that the cross-flow with the grid is greater than the cross-flow without a grid under the same condition, indicating that the existence of a grid can enhance the cross-flow between sub-channels and balance the uneven flow between sub-channels.
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.