1. Krištofová, K. et al “Comparision of determinated MCNP source terms for VVER-440/V230 decommissioning”. 26th Symposium of AER on VVER Reactor Physics and Reactor Safety, october 2016, Helsinki, Finland.
2. Oravkin, M. Determination of neutron source term for calculation of inventory of induced activity of VVER-440 / V230 by MCNP code. Diploma thesis, FEI-104410-9040, FEI STU Bratislava 2016. (In Slovak)
3. Narkunas, E., Poskas, G., Smaizys, A., “Impact of shield elements on the WWER-440 reactor pressure vessel activation”, Nuclear Engineering Laboratory, Lithuanian Energy Institute, Breslaujos 3, 44403 Kaunas, Lithuania, 2019; Availievable at: https://www.sciencedirect.com/science/article/pii/S0306454919301331
4. X-5 Monte Carlo Team. MCNP – A General Monte Carlo N-Particle Transport Code, Version 5, Volume II: User’s Guide, LA-CP-03-0245, 2003.
5. Chrapčiak, V. et. al. Neutrónovo-fyzikálne charakteristiky AZ pre prevádzku reaktora 3. bloku EBO v 23. kampani. 2006.