I have a UO2 fueled (20% enriched), polyethylene moderated, graphite reflected reactor (AGN-201). Beyond the graphite reflector, there is a 10 cm thick lead shield and then about a meter of water for neutron shielding. My nuclear instruments are located in the water.
I would like to develop a SCALE model of the reactor that will provide the neutron flux at the detector location. I am interested in the relationship between the reactor power and the flux at the detector.
Looking for some suggestions for smart ways to go about the problem.
Thanks in advance.
Chad Pope