给水扰动下超临界水堆堆芯温度特性研究  

Research on Core Temperature Features of SCWR with Water Disturbance

作　　者：周蓝宇 周涛 许鹏 唐剑宇 程品晶[4] 刘亮 ZHOU Lanyu;ZHOU Tao;XU Peng;TANG Jianyu;CHENG Pinjing;LIU Liang(China Nuclear Power Engineering Co.,Ltd.,Beijing 100840,China;Department of Nuclear Science and Technology,School of Energy and Environment,Southeast University,Nanjing Jiangsu 210096,China;School of Nuclear Science and Engineering,North China Electric Power University,Beijing 102026,China;School of Nuclear Science and Technology,University of South China,Hengyang Hunan 421001,China;Wave(Beijing)Technology Co.,Ltd.,Beijing 100085,China;Nuclear Thermal Safety and Standardization Research Team,China)

机构地区：[1]中国核电工程有限公司,北京100840 [2]东南大学能源与环境学院核科学与技术系,江苏南京210096 [3]华北电力大学核科学与工程学院,北京102206 [4]南华大学核科学与技术学院,湖南衡阳421001 [5]威富视界(北京)科技有限公司,北京100085 [6]核热工安全与标准化团队,中国

出　　处：《湖北电力》2021年第5期115-119,共5页Hubei Electric Power

基　　金：北京市自然科学基金(项目编号:3172032);新进教师科研启动项目(项目编号:3203002104A2)。

摘　　要：以超临界水堆为研究对象,计算研究了给水扰动对反应堆堆芯温度的影响。研究结果表明,给水流量5%阶跃下降后,第一流程最高包壳温度与第二流程最高包壳温度均有上升,主蒸汽温度上升;给水温度上升会带来多普勒反馈变化,这种变化会引入负反应性。在多普勒反馈中,寿期初变化比寿期末变化小。Taking supercritical water cooled reactor(SCWR)as the research object,this paper calculates and studies the influence of feed water disturbance on the core temperature. The result shows that when the feed water flow decreases by 5%,the maximum cladding temperature in the first process and that in the second process both rise,the main steam temperature also rising,that the rise of feed water temperature will bring about Doppler feedback change,which brings negative reactivity into the reactor,and that during the Doppler repercussion,the variation at the beginning of core life is smaller than that at the end of core life.

关 键 词：超临界水堆 给水扰动 堆芯温度 负反应性 多普勒反馈 

分 类 号：TL351[核科学技术—核技术及应用]