Dévelopment of a new Monte Carlo Burnup computer code - Application to the calculation of neutronics and burnup parameters of TRIGA MARK II Moroccan Research Reactor -
en
Loading...
Authors
Collections
Journal Title
Journal ISSN
Volume Title
Publisher
Department
Supervisor
Date
Abstract
Description
Keywords
Physique nucléaire, Computer code, Calculation of neutronic, TRIGA MARK 2, Maroccan research Reactor