Abstract
The thermal hydraulic and neutronics coupling analysis is an important part of the high-fidelity simulation for nuclear reactor core. In this paper, a thermal hydraulic and neutronics coupling method was proposed for the plate type fuel reactor core based on the Fluent and Monte Carlo code. The coupling interface module was developed using the User Defined Function (UDF) in Fluent. The three-dimensional thermal hydraulic model and reactor core physics model were established using Fluent and Monte Carlo code for a typical plate type fuel assembly, respectively. Then, the thermal hydraulic and neutronics coupling analysis was performed using the developed coupling code. The simulation results with coupling and noncoupling analysis methods were compared to demonstrate the feasibility of coupling code, and it shows that the accuracy of the proposed coupling method is higher than that of the traditional method. Finally, the fuel assembly blockage accident was studied based on the coupling code. Under the inlet 30% blocked conditions, the maximum coolant temperature would increase around 20°C, while the maximum fuel temperature rises about 30°C. The developed coupling method provides an effective way for the plate type fuel reactor core high-fidelity analysis.
Highlights
Academic Editor: Fu Li e thermal hydraulic and neutronics coupling analysis is an important part of the high-fidelity simulation for nuclear reactor core
A thermal hydraulic and neutronics coupling method was proposed for the plate type fuel reactor core based on the Fluent and Monte Carlo code. e coupling interface module was developed using the User Defined Function (UDF) in Fluent. e three-dimensional thermal hydraulic model and reactor core physics model were established using Fluent and Monte Carlo code for a typical plate type fuel assembly, respectively. en, the thermal hydraulic and neutronics coupling analysis was performed using the developed coupling code. e simulation results with coupling and noncoupling analysis methods were compared to demonstrate the feasibility of coupling code, and it shows that the accuracy of the proposed coupling method is higher than that of the traditional method
Under the inlet 30% blocked conditions, the maximum coolant temperature would increase around 20°C, while the maximum fuel temperature rises about 30°C. e developed coupling method provides an effective way for the plate type fuel reactor core highfidelity analysis
Summary
Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core. A thermal hydraulic and neutronics coupling method was proposed for the plate type fuel reactor core based on the Fluent and Monte Carlo code. Xoubi et al investigated the impact of enrichment on neutron flux in the in-core facility of 10 MW MTR with OpenMC and found the importance of flux trap calculation while considering the conversion of reactor core from HEU to LEU [13] It demonstrated the feasibility of the Monte Carlo method in analyzing plate type fuel reactor. Erefore, an innovative thermal hydraulic and neutronics coupling method was proposed based on the Fluent and Monte Carlo code through the UDF module for the plate type fuel reactor core in this paper. E typical RANS-based models include the Reynolds stress model (RSM) and the models that introduce eddy viscosity hypothesis such as the k-ε model and k-ω model. e standard k-ε model is the most common turbulence model used in CFD, and its equation is described below as an example of RANS-based model [15]: ρ
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