1. Development of a coupling scheme between MCNP5 and SUBCHANFLOW for the pin-and fuel assembly-wise simulation of LWR and innovative reactors;Ivanov;Proc. M&C,2011
2. Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers;Jung;Ann. Nucl. Energy,2013
3. Liu, S.C., Yu, J.K., Liang, J.G., Wang, K., 2015. Study of neutronics and thermal-hydraulics coupling with RMC COBRA-EN system. In: 7th International Conference on Modelling and Simulation in Nuclear Science and Engineering (7ICMSNSE), pp. 18–21.
4. Coupled neutronics/thermal-hydraulics analysis of a full PWR core using RMC and CTF;Guo;Ann. Nucl. Energy,2017
5. The multiscale thermal‐hydraulic simulation for nuclear reactors: A classification of the coupling approaches and a review of the coupled codes;Zhang;Int. J. Energy Res.,2020