科技研发

R&D

COSINE

COSINE


系统分析程序以核电厂一、二回路为计算对象,采用多相多流场模型;主要用于核电厂系统设计、运行瞬态计算、设计瞬态计算、事故分析、核电厂仿真、实验台架设计等工作。该程序具备计算核电厂系统压力、流量、燃料与包壳温度、堆芯功率、蒸汽流量等电厂关键参数的能力,能模拟核电厂系统中各类设备的功能,如主冷却剂泵、管道、各类阀门、冷却器、加热器、换热器、蒸汽发生器、安注箱、稳压器、汽水分离器、汽轮机等,以及模拟核电厂的控制系统。此外,还能模拟瞬态与事故过程中的各类热工水力现象,包括喷放、热分层、液滴夹带、相向流动、固体导热、辐射、堆芯再淹没等。
COSINE system analysis code for simulating the primary and secondary loops of nuclear power plant (NPP), adopts multiphase flow model. It is mainly used for system designing, operation transient and other transients calculation, accident analysis, nuclear power plant simulation and experiment facility design, etc. The system analysis code can calculate those key parameters of NPP, such as system pressure, flow rate, fuel and cladding temperature, reactor core power, steam flow rate. This code can also simulate the function of all kinds of equipment in NPP, such as the main coolant pumps, pipes, valves, coolers, heaters, heat exchangers, steam generators, accumulators, pressurizer, separators, turbine, etc., and simulate the control systems of NPP. Besides, the system code can also simulate various thermal hydraulic phenomena of transient and accident, including blowdown, thermal stratification, droplet entrainment, CCFL, solid heat conduction, radiation, and core reflood heat transfer etc.