摘要
倒U型管蒸汽发生器(UTSG)在自然循环条件下存在倒流现象,影响一回路冷却剂系统载热能力及自然循环能力。本文参照芬兰压水堆热工实验装置(PWR PACTEL)中UTSG设计参数,利用计算流体力学(CFD)软件Fluent模拟流量匀速下降工况下UTSG中的倒流现象,研究一次侧运行参数、UTSG设计参数以及二次侧运行参数对于倒流现象的影响。结果表明,提高UTSG一次侧温度、一次侧运行压力、倒U型管热导率将增大UTSG的临界质量流量,使得UTSG更易发生倒流;提高UTSG二次侧给水量、二次侧温度以及倒U型管内壁粗糙度将使得UTSG临界质量流量下降,抑制倒流现象发生;而倒U型管壁厚对倒流现象几乎无影响;相较于改变二回路温度,改变一回路温度对于倒流现象的影响更为显著。本研究结果可为UTSG的参数优化提供一定参考。
Backflow exists in the inverted U-tube steam generator(UTSG)under the condition of natural circulation,which affects the heat carrying capacity and natural circulation capacity of the primary circuit coolant system.Referring to the design parameters of UTSG in PWR thermal experimental device(PWR PACTEL)in Finland,this paper uses computational fluid dynamics(CFD)software Fluent to simulate the backflow in UTSG under the condition of uniform flow decline,and studies the influence of primary side operation parameters,UTSG design parameters and secondary side operation parameters on the backflow.The results show that increasing the primary side temperature,primary side operating pressure and thermal conductivity of the inverted U-tube will increase the critical mass flow rate of the UTSG,making the UTSG more prone to backflow;Increasing the water supply and temperature on the secondary side of UTSG and the roughness of the inner wall of inverted U-tube will decrease the critical mass flow rate of UTSG and restrain the occurrence of backflow.Changing the wall thickness of inverted U-tube has little effect on the backflow;Compared with changing the temperature of the secondary circuit,changing the temperature of the primary circuit has a more significant impact on the backflow.The results of this study can provide some reference for the parameter optimization of UTSG.
作者
王天石
王宇轩
赵鹏程
王曦婕
凌煜凡
王雨晴
朱恩平
Wang Tianshi;Wang Yuxuan;Zhao Pengcheng;Wang Xijie;Ling Yufan;Wang Yuqing;Zhu Enping(School of Nuclear Science and Technology,University of South China,Hengyang,Hunan,421001,China;Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2022年第2期40-46,共7页
Nuclear Power Engineering
基金
国家自然科学基金(11905101)
装备预研重点实验室基金(6142A07180110)。