The Application Of OpenFOAM In Neutron Transport And Its Reduced Model Research

As a complex partial differential-integral equation,the neutron transport equation is the most important equation in the reactor core calculations,and i t is a relatively effective way to solve it by numerical calculation.At present,the development of the reactor is relatively fast,for the new generation reactors,their structure are complex and requirements for multi-physical calculation are high.Most of the current neutron transport calculation programs are based on neutron transport calculation methods,which are poor of multi-physics computing.At the same time,most software with strong physical computing capabilities are mostly commercial software,which is difficult to develop and calculate complex neutron transport process.In view of this,this paper establishes an open source solver for neutron transport based on OpenFOAM,an open source software coupled with multi-physical computing.In order to improve the computational efficiency of neutron transport,this paper firstly uses the POD method to establish a neutron transport reduced model.This work implementes the neutron diffusion equation in OpenFOAM to establish the neutron diffusion solver NDEFoam.To improve NDEFoam,the energy group discrete,eigenvalue calculation and transient dynamics calculation are realized in it.The results of typical benchmark problems,calculated by NDEFoam,show the correctness and generality of the program.The solver meets the requirements of large-scale reactor calculations while improving its multi-physics computing capabilities and the extended performance of in-depth development.This work implements the neutron transport equation,solved by the discrete ordinate method,in OpenFOAM to establish the neutron transport solver NDEFoam.Improving its multi-group calculation,eigenvalue calculation and dynamics calculation modules,dealing with its complex boundary conditions,makes it more perfect.Calculate the typical benchmark problems,and the results show the correctness and generality of the program.The solver meets the requirements of modern reactors for their calculation accuracy and provides a unified numerical method and the possibility of in-depth study for calculating complex multi-physics processes.This work introduces the proper orthogonal decomposition(POD)to the neutron transport calculation to establish the neutron transport reduced order model NTEROM solved by the discrete ordinate method.The multi-group calculation,eigenvalue calculation and dynamics calculation module are added to the model.The correctness and generality of NTEROM are tested by calculating typical benchmark problems,and it is more efficient than NTEFoam.The reduced order model can significantly improve the efficiency of neutron transport calculations while ensuring the accuracy of calculation,and can also calculate the steady-state optimization prediction and transient dynamics prediction problems.