摘要
华龙一号(HPR1000)设置了反应堆冷却剂泵进出口压差表用于测量反应堆冷却剂系统(RCS系统)环路流量,取消了二代改进型核电机组设置的弯管流量计。环路流量测量方式的改变直接影响RCS系统流量测量试验的实施。通过研究主泵的运行特性和系统的阻力特性,提出了基于主泵电功率测量RCS系统流量的试验方法。结合理论分析结果和工程实践经验,给出了反应堆冷却剂惰走流量试验的试验方法和验收准则。研究表明,主泵电功率法可以测量RCS系统的流量,反应堆冷却剂惰走流量可以通过主泵惰转过程的转速变化进行验证。
The reactor coolant pump inlet and outlet differential pressure gauge was set in HPR1000 to measure the loop flow of the reactor coolant system, and the elbow flowmeter set in the second generation progressive nuclear power unit was eliminated. The change of the flow measurement means directly affects the implementation of the flow measurement tests of RCS system. By studying the operation characteristics of the main pump and the resistance characteristics of the system, a test method based on the electric power of the main pump to measure the flow of RCS system was proposed. Combined with theoretical analysis results and engineering practice experience, the test method and acceptance criteria of the reactor coolant idling flow test were given. The research shows that the main pump electric power method can measure the flow of RCS system, and the reactor coolant idling flow can be verified by the speed change of the main pump during the idling process.
作者
黄宗仁
王明利
李峰
Huang Zongren;Wang Mingli;Li Feng(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
2021年第2期193-196,共4页
Nuclear Power Engineering