Initial verification of AZNHEX hexagonal-z neutron diffusion code with MCNP6 for two different study cases En este artículo publicado en Progress in Nuclear Energy 106 (2018) 284–292, se presentan avances en la verificación del código AZNHEX Abstract The core of the AZTLAN Mexican reactor analysis platform consists of a thermo-hydraulic code (AZTHECA), a neutron transport […]
