Neutronic calculations of the MTR-22 MW research reactor loaded with MOX (PuO2&UO2) Caramel fuel using the MCNP5 Code

Autor:	Shaaban, Ismail, Albarhoum, Mohamad
Zdroj:	In Annals of Nuclear Energy August 2016 94:478-486
Databáze:	ScienceDirect
Externí odkaz:	Zobrazit plný text záznamu Full Text from ScienceDirect