Test Investigation on Steam Generator U-tube Rupture of Different Break Size
|School||China Institute of Atomic Energy|
|Course||Nuclear Energy Science and Engineering|
|Keywords||Steam generator Rupture accident The broken area Heat transfer tube Experimental study Integrated test device Qinshan Nuclear Power Plant Orifice aperture Thermal hydraulics System pressure|
To better understand the nuclear power plant steam generator tube rupture accident thermal-hydraulic phenomena , as well as analysis and evaluation of system analysis program of the pressurized water reactor (PWR) nuclear power plant , the steam generator on the high-voltage integrated test device heat transfer tube rupture Experimental study on high-pressure test device for analog objects Qinshan Nuclear Power the factory owners loop system , the device is a bicyclic loop system , the volume ratio of 1:1000 height ratio of 1:1 . The initial test conditions close to the Qinshan nuclear power plant operating conditions . Test to reproduce the thermal-hydraulic phenomena in the nuclear power plant steam generator heat transfer tube of the single-piece double-ended rupture accident and three heat transfer tube double-ended rupture accident , the accident process once the system pressure , the secondary system pressure , breaking port flow , the secondary side of steam generator water level, water level in the regulator element surface temperature, etc. the main parameters of the transient response. Single heat transfer tube rupture accident conditions simulation break orifice aperture 0.876mm, and the three heat transfer tube rupture accident conditions simulation break orifice aperture 1.518mm . Double -side of a single steam generator tube rupture accident conditions RELAP5/MOD2 system program analysis , calculated with the experimental results better match .