1. Bandini, B.R., 1990. A Three-dimensional Transient Neutronics Routine for the TRAC-PF1 Reactor Thermal Hydraulic Computer, Ph.D. thesis, Pennsylvania State University, May 1990.
2. Three-dimensional variational nodal transport methods for Cartesian, triangular and hexagonal criticality calculations;Carrico;Nucl., Nucl. Sci. Eng. J. Am. Nucl. Soc.,1992
3. DeHart, M., Wang, Y., Gleicher, F., Ortensi, J., et al., 2016. Reactor physics tools for advanced multiphysics simulations. Physor 2016, Sun Valley, Idaho, USA, May 1-5, 2016.
4. Reactor analysis using the variational nodal method implemented in the ERANOS system;Doriath;Proc. R. Soc. Lond.,1994
5. Du, X., Cao, L., Zheng, Y., Wu, H., 2017. Developments of the Sodium Fast Reactor Analysis code SARAX: methods and verification, M&C 2017, Jeju, Korea, April 16-20, 2017.