<p>Loss&nbsp;of coolant accident (LOCA) is one of most severe accidents of nuclear power plant. The coolant discharging from the break point when this accident occurred, causing large hydrodynamic&nbsp;load on the primary loop system because of the fluid thrust force as well as the propagation of pressure wave, and it may further influence the pressure boundary of the primary loop. Steam generator (SG) is a crucial device with complicated structure, hydrodynamic&nbsp;forces of its U-type tube and divider plant has been analyzed under various cases in this paper. Firstly, the reactor core and primary loop system of pressurized water reactor nuclear power plant is modeling with RELAP5. Then the pressure and mass flow rate these kind of thermal hydraulic parameters of loop system are acquired after the simulation of LOCA. Finally, the hydrodynamic&nbsp;forces of key positions of SG are calculated with the control volume integral method. Beside that, the sensitivity analysis are also studied in this paper, including the break opening time, number of control volumes as well as the time step chosen in the hydrodynamic force calculation. The results have shown that the break opening time has great influence on the numerical calculation that should be careful set during the simulation, and the maximum hydrodynamic force is obtained when double-ended offset shear break at outlet nozzle of SG, and the pressure difference of SG divider plate is obviously increased compared with normal operation condition. Thus, the results of this paper provide some meaningful references for the design and safety analysis of SG.</p>

Hydrodynamic Analysis of Steam Generator Under LOCA Conditions

Paper Proceedings: https://asmedigitalcollection.asme.org/ICONE/ICONE28/volume/85246

2021 28th International Conference on Nuclear Engineering (ICONE28)

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