Abstract Numerical simulation of nuclear reactors is a key technology in the quest for improvements in efficiency, safety, and reliability of both existing and future reactor designs. Historically, simulation of an entire reactor was accomplished by linking together multiple existing codes that each simulated a subset of the relevant multiphysics phenomena. Recent advances in the MOOSE (Multiphysics Object Oriented Simulation Environment) framework have enabled a new approach: multiple domain-specific applications, all built on the same software framework, are efficiently linked to create a cohesive application. This is accomplished with a flexible coupling capability that allows for a variety of different data exchanges to occur simultaneously on high performance parallel computational hardware. Examples based on the KAIST-3A benchmark core, as well as a simplified Westinghouse AP-1000 configuration, demonstrate the power of this new framework for tackling—in a coupled, multiscale manner—crucial reactor phenomena such as CRUD-induced power shift and fuel shuffle.

Physics-based multiscale coupling for full core nuclear reactor simulation

Heat pipe failure accident analysis in megawatt heat pipe cooled reactor

Neutronic and thermal-mechanical coupling analyses in a solid-state reactor using Monte Carlo and finite element methods

Transient heat pipe failure accident analysis of a megawatt heat pipe cooled reactor

Minyun Liu

Papers

Neutronic and thermal-mechanical coupling analyses in a solid-state reactor using Monte Carlo and finite element methods

A new neutronics-thermal-mechanics multi-physics coupling method for heat pipe cooled reactor based on RMC and OpenFOAM

Neutronics and thermal-hydraulics coupling analysis in accelerator-driven subcritical system

Coupled neutronic, thermal-mechanical and heat pipe analysis of a heat pipe cooled reactor

Thermal-hydraulic performance of zigzag channels with Bending number below unity for printed circuit heat exchanger