Session: 08-03: Computational Fluid Dynamics (CFD) and Applications - III

Paper Number: 134682

134682 - Cfd Analysis of a Four-Loop Pressurized Water Reactor With Multiple Operating Conditions 

Abstract: 

Abstract: The flow field characterization of the core pressure vessel is an important part of the thermal-hydraulic design of nuclear power plants, which is related to the reactor internal structure design, core inlet flow distribution and nuclear power plant safety; this paper takes the Siemens KONVOI type pressurized water reactor as the object of study, and carries out the modeling and large watershed simulation calculations for the upper plenum, the lower plenum, the outlet section, the inlet section and the core of the RPV, and adopts the porous The porous media model is used to simulate the fuel assembly level refinement of the core; Siemens KONVOI reactor-type core operation data and ROCOM experimental data are selected for numerical validation of this study. The distribution and intermixing of salt tracer were simulated by solving the scalar equations. The results show that the coolant undergoes homogeneous mixing with the flow, which is consistent with the experimental results of the ROCOM device. On this basis, the core thermal parameters are verified to ensure the accuracy of the core part calculation.

In this paper, the reasonableness of the calculation results of the low plenum and the core is verified by comparing with the existing data, and the polyhedral mesh division scheme and the wall function model suitable for the calculation of the low plenum are given, and the characteristics of the coolant flow and mixing are analyzed under different operating conditions, and the calculation results show that the low plenum of the reactor can effectively carry out the mixing and flow distribution of the coolant, and the flow rate of the external core inlet channel is relatively large in the The flow in the core inlet channel at the vertical projection of the perforated drum (flow distribution device) is relatively small, and the flow distribution in the central area of the core inlet channel is relatively uniform;

Finally, this paper investigates the transient response characteristics of the flow in the RPV under different operating conditions, and carries out the simulation of thermo-hydrodynamic characteristics of the KONVOI-type pressurized water reactor under multiple operating conditions. The flow distribution characteristics at the core inlet and outlet under the asymmetric loop flow conditions and the dynamic response characteristics of the thermo-mechanical parameters in the process of variable operating conditions are summarized.This study provides a method to analyze RPV under variable operating conditions, which provides certain reference values for reactor optimization design and safety analysis.

Presenting Author: Yizhi Tian Harbin engineering university

Presenting Author Biography: Master's student at Harbin Engineering University, focusing on reactor thermo-hydraulics research.

Authors:

Yizhi Tian Harbin engineering university
Guangliang Chen Haibin Engineering University
Ruojun Xue Harbin engineering university
Yuchen Sun Harbin Engineering University
Jinchao Li Harbin engineering university
Rui Li Harbin Engineering University