Consider two groups of isotopes. Group A consisting of
U-233, U-235, Pu239, Pu-241 and group B of Th-232, U-238, Pu-240, and Pu-242.
Identify the group that represents fissile and the group that represents
Start with the one-group neutron diffusion equation and
derive the relation for neutron flux in a bare critical slab reactor. Find the
maximum to average flux for this reactor.