1. A pure dynamic Monte Carlo code for the neutronic analysis of nuclear reactors;Ajami;Ann. Nucl. Energy,2022
2. Derivation of a stochastic neutron transport equation;Allen;J. Difference Equ. Appl.,2010
3. Anon, ., 0000a. [link]. URL http://awing.reak.bme.hu/GUARDYAN.
4. Anon, ., 0000b. [link]. URL https://wwwndc.jaea.go.jp/jendl/j40/j40.html.
5. Stochastic Differential Equations: Theory and Applications;Arnold,1974