A Porous Media Simulation Method for Coupled Heat Transfer Model of Fast Reactor Bundle Components

Abstract

The invention discloses a porous medium simulation method aiming at the coupled heat transfer model of fast reactor rod bundle components, which comprises the following steps: establishing a geometric model of the core including the interior of the component box and the space between the boxes, and using a hexagonal prism to represent the interior of the component box when modeling ; Establish a planar topological structure for the lower end surface of the geometric model of the core, and generate a full quadrilateral surface mesh, in which the boundary layer mesh should be generated in the near wall area of ​​the component box; axially stretch the surface mesh to form a three-dimensional structured mesh model . Import the 3D grid model into the CFD solver, calculate the distance from the center point of the grid control body in the box to the wall, and then determine the properties of the control body (pure fluid or porous medium domain). Based on the structural characteristics of the rod bundle, the distributed resistance model and the mass and heat transfer model are introduced, and the momentum transport at the interface between the pure fluid domain and the porous medium domain is corrected. The invention can realize the rapid simulation of the flow and heat transfer phenomenon of the fast reactor rod bundle components, accurately predict the temperature distribution and heat transfer in and between the component boxes, and is beneficial to the simulation of the whole core.

Description

technical field [0001] The invention relates to the field of thermal hydraulic design of fast neutron reactor core, in particular to a simulation method for calculating the scale of fast reactor core. Background technique [0002] Different from the usual pressurized water reactors, fast reactors convert fissile nuclides U238 and Th232 into fissile nuclides Pu239 and U233 respectively through fast neutron capture, thereby realizing the multiplication of fissile nuclides in a chain reaction, so Fast reactors are also called breeder reactors. In order to increase the volume fraction of fuel and reduce neutron leakage, thereby reducing the ratio of fissile fuel in fast reactors, triangular fuel grids or hexagonal grids are used in fast reactor core design. In line with this grid layout, the fast reactor uses hexagonal stainless steel sleeves to divide the core into several areas, and the stainless steel sleeves and internal fuel rod bundles form a relatively independent unit (...

AI Technical Summary

Problems solved by technology

[0004] The technical problem solved by the present invention is to provide a porous medium simulation method for fast reactor rod bundle components in view of the deficiencies in the prior art, which solves the problem of serious distortion of simulation using traditional porous medium, and makes full use of the secondary development of the existing CFD platform The convenient and robust numerical solution algorithm and large-scale parallel capability provide a realistic and feasible technical solution for the study of the flow and heat transfer characteristics of the whole core of the fast reactor

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