Recent content by Kashif

basically the dose from neutron plus gammas is required. like we have to calculate dose a the surface of sphere filled with enriched uranium plus a point neutron source at center. in this case how we should define SOURCE TERM in MCNP5.

Greetings to all need forum members help regarding MCNP5 college assignment. The task is to calculate dose from a system comprising of a neutron source surrounded by natural uranium. the system is subcritical. The problem is how to calculate dose due to fissions in the uranium because dose from...