AUTHOR=Kendrick William Reed , Forget Benoit 

TITLE=Coupled neutronic-thermal-mechanical simulation of the KRUSTY heat pipe microreactor

JOURNAL=Frontiers in Nuclear Engineering

VOLUME=Volume 4 - 2025

YEAR=2025

URL=https://www.frontiersin.org/journals/nuclear-engineering/articles/10.3389/fnuen.2025.1589780

DOI=10.3389/fnuen.2025.1589780

ISSN=2813-3412

ABSTRACT=Multiphysics analysis has become a common technique for nuclear reactor design validation, with neutronic-thermal analysis being the typical choice for understanding reactor dynamics. The concept of adding mechanical simulation such as thermal expansion to this coupling is still relatively new, however, and presents many computational challenges. While large reactors see relatively little neutronic impact from thermal expansion and may not warrant the challenge of undertaking this level of coupling, recent studies of microreactor geometries show that smaller reactors see larger impacts from thermal expansion. This work performs coupled neutronic-thermal-mechanical simulation of the Kilowatt Reactor Using Stirling TechnologY (KRUSTY) using OpenMC and Multiphysics Object-Oriented Simulation Environment in order to analyze the neutronic and thermal impact of including thermal expansion at steady state. The results show that while thermal expansion has a significant effect on global neutronic tallies, it has relatively minor impact on spatial heating rates or temperatures in the system. This remains true even when simulating a multiple heat pipe failure scenario to introduce thermal asymmetry.