1. Transient fission matrix approach for assessing complex kinetics behavior in the ZEPHYR ZPR coupled core configurations;Blaise;Annals of Nuclear Energy,2018
2. Brown, F., Carney, S., Kiedrowski, B., Martin, W., 2014. Fission matrix capability for MCNP Monte Carlo. Transactions of the American Nuclear Society 107 03502, 06.
3. Theory and applications of the fission matrix method for continuous-energy Monte Carlo;Carney;Annals of Nuclear Energy,2014
4. Full MOX recycling in ALWR: Lessons drawn through the MISTRAL program;Cathalau;PHYSOR 2002 International Conference Seoul, South Korea,2002
5. Chiba, G., 2009. Nuclear data-induced uncertainty calculation for fast reactor eigenvalue separation. In Proc. NDS2008: 2008 annual symposium on nuclear data, Tokai, Ibaraki (Japan), 20–21 Nov 2008, 2009.