1. A. Abaraca, R. Miró, T. Barrachina, et al., 2011. A procedure for coupled thermal-hydraulic subchannel and neutronic codes using COBRA-TF and PARCS, 2011 International Nuclear Atlantic Conference, Belo Horizonte, MG, Brazil, October 24-28.
2. Impact of pin-by-pin thermal-hydraulic feedback modeling on steady-state core characteristics;Akio Yamamoto and Tsutomu Ikeno;Nucl. Technol.,2005
3. Brian N. Aviles, Daniel J. Kelly, David L. Aumiller, et al., 2016. Coupled MC21 and COBRA-IE solution to VERA core physics benchmark problem#6, In: PHYSOR2016, Sun Valley, ID, May 1-5.
4. Avramova M., Cuervo D., Ivanov K., 2006. Improvements and Applications of COBRA-TF for Stand-Alone and Coupled LWR Safety Analyses. In: PHYSOR2006 Conference, Vancouver, Canada.
5. Integration of the subchannel thermal-hydraulic code SubChanFlow into the reactor dynamics code PARCS: development and testing based on a computational benchmark;Basualdo;Prog. Nucl. Energy,2020