摘要
针对核动力舰艇航行时可能发生的摇摆运动情况,本文采用数值模拟方法探究海洋摇摆运动条件下超临界水冷堆(Supercritical-water-cooled reactor,SCWR)堆芯冷却通道内超临界水湍流流动与传热特性,揭示海洋摇摆运动对通道内瞬时及时均换热性能的影响。研究表明:在摇摆条件下通道内超临界水横流强度大幅增强,流体质量流量、压降损失、瞬时换热系数、燃料棒外壁面最高温度等均出现周期性波动现象,在流体温度接近拟临界温度时摇摆运动对通道内对流传热过程的影响最显著。并且,上述参数波动幅度与摇摆幅度和摇摆周期之比正相关。随通道摇摆幅度增大或摇摆周期减小,瞬时换热系数与瞬时压降波动幅度增大。总体而言,与竖直静止情形相比,在摇摆条件下通道内时均压降损失与时均换热系数均有一定程度增大,但增长幅度有限。
Considering the rolling motion of nuclear-powered ships,the turbulence flow and heat transfer characteristics of supercritical water in the cooling channel in the core of supercritical-water-cooled reactor(SCWR)under rolling conditions are numerically investigated,in order to reveal the impact of rolling motion on transient and time-averaged heat transfer performance.The results show that the crossflow intensity of the supercritical water is strengthened under rolling conditions.The mass flow rate of the fluid,the pressure drop,the transient heat transfer coefficient and the maximum wall temperature on the outer surface of fuel rod are observed to fluctuate periodically.The impact of rolling motion on convective heat transfer characteristics will be more significant as the fluid temperature gets closer to pseudocritical temperature,and there is positive correlation between the fluctuation amplitude of transient parameters and the ratio of rolling amplitude to rolling period.As the rolling amplitude increases or rolling period decreases,the fluctuation amplitude of transient heat transfer coefficient and transient pressure drop rises.In general,both the time-averaged heat transfer coefficient and pressure drop increase under rolling condition,when compared with the vertical static situation,but the increment is limited.
作者
李鑫
谢公南
LI Xin;XIE Gongnan(School of Marine Science and Technology,Northwestern Polytechnical University,Xi’an 710072,China)
出处
《南京航空航天大学学报》
CAS
CSCD
北大核心
2022年第4期623-634,共12页
Journal of Nanjing University of Aeronautics & Astronautics
基金
高等学校学科创新引智计划(B18041)
深圳市科创委基础研究项目(NJCYJ20170306155153048)。
关键词
核动力舰船
超临界水冷堆
堆芯冷却
摇摆运动
湍流流动传热
nuclear-powered ships
supercritical-water-cooled reactor(SCWR)
core cooling
rolling motion
turbulence flow and heat transfer
