1. Thermal-Hydraulics analysis of pressurized water reactor core by using single heated channel model;Akbari;J. Appl. Comput. Mech.,2017
2. Fuzzy logic control for improved pressurizer systems in nuclear power plants;Brown;Ann. Nucl. Energy,2014
3. Bushehr NPP final safety analysis report (BNPP FSAR), 2008. Atomic Energy Organization of Iran (AEOI).
4. Application of artificial intelligence techniques in modeling and control of a nuclear power plant pressurizer system;De Oliveira;Prog. Nucl. Energy,2013
5. Fletcher, G.D., Schultz, R.R., 1999. RELAP5/MOD3.3 code manual, Idaho National Engineering Laboratory Idaho.