摘要
系统研究了中国先进压水堆非能动余热排出系统稳态特性,共取得237组试验数据。根据实验数据分析研究了系统压力、系统冷热芯位差、系统等效阻力系数、风速对两相自然循环流量和系统余热排出能力的影响。在理论分析的基础上,得到了两相自然循环稳态流量关系式。将试验数据与计算结果进行比较,有95%的试验结果在±16%的相对误差范围内。分析结果表明,影响冷热芯位差阈值的主要参数是系统状态参数(系统压力、阀门形状阻力系数)和系统边界条件(空气入口温度、烟囱高度),由此得到了两相自然循环系统冷热芯位差阈值关系式。稳态特性研究表明,中国先进压水堆核电站非能动余热排出系统具有堆芯2%额定功率的自然循环能力。
Research on the steady characteristic of passive residual heat removal system (PRHRS) for Chinese advanced PWR has been performed in a systematic way. A total of 237 sets of test data at steady state have been obtained and the main influence factors, for example, system pressure, height between heat resource and heat sink, system effective resistance coefficient, and wind velocity, on the two-phase natural circulation flow rate and residual heat removal capability were identified. On the basis of theory analysis, steady correlation of two-phase natural circulation has been obtained.Relative errors of 95% test data were less than ±16%. There is a considerable effect of system state parameter(such as system pressure and valve form resistance coefficient) and system boundary condition(such as environmental temperature and chimney height) on the threshold of elevation between heat resource and heat sink, and its correlation of two-phase natural circulation system has been obtained. Steady characteristic research shows that the PRHRS has the capability of removing the core decay power (2% full power) through natural circulation.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2005年第5期436-442,共7页
Nuclear Power Engineering
基金
2002年度四川省杰出青年学科带头人培养基金项目资助
关键词
中国先进压水堆
非能动余热排出系统
稳态特性
Chinese advanced PWR, Passive residual heat removal system, Steady characteristic