Talamo, A., Ji, W., Cetnar, J., & Gudowski, W. (2006). Comparison of MCB and MONTEBURNS Monte Carlo burnup codes on a one-pass deep burn. Ann. Nucl. Energy, 33(14/15), 1176–1188. doi.org/10.1016/j.anucene.2006.08.006.
International Atomic Energy Agency. (2012). Role of thorium to supplement fuel cycles of future nuclear energy systems. Vienna: IAEA. (Nuclear Energy Series NF-T-2.4).
Shamanin, I. V., Grachev, V. M., Chertkov, Yu. B., Bedenko, S. V., Mendoza, O., & Knyshev, V. V. (2018). Neutronic properties of high-temperature gas-cooled reactors with thorium fuel. Ann. Nucl. Energy, 113, 286–293. DOI: 10.1016/j.anucene.2017.11.045.
Oettingen, M., & Stanisz, P. (2018). Monte Carlo modelling of Th-Pb fuel assembly with californium neutron source. Nukleonika, 63(3), 87–91. DOI: 10.2478/nuka-2018-0011.
Oettingen, M., Cetnar, J., & Mirowski, T. (2015). The MCB code for numerical modelling of fourth generation nuclear reactors. Computer Science, 16, 329–350. DOI: 10.7494/csci.2015.16.4.329.
Oettingen, M. (2021). Assessment of the radiotoxicity of spent nuclear fuel from a fleet of PWR reactors (2021). Energies, 14, 3094. https://doi.org/10.3390/en14113094.