In a certain thermal reactor, fueled with partially enriched uranium, 13% of the fission neutrons are absorbed in resonances of 238-u and 3% leak out of the reactor, both while these neutrons are slowing down; 5% of the neutrons that slow down in the reactor subsequently leak out; of those slow neutrons that do not leak out, 82% are absorbed in fuel, 74% of these in 235-u.

(a) what is the multiplication factor of this reactor?
(b) what is the conversion ratio?