Neutron yield detectors characterized with MCNP

In preparation for measuring neutrons generated in experiments on the Zebra 1-MA Z-pinch generator at the Nevada Terawatt Facility, we use the Monte Carlo N-Particles (MCNP) radiation transport code to characterize neutron activation detectors. For reasonable assumptions regarding the emitted neutron pulse characteristics, the MCNP code is used to predict the expected neutron signal taking into account scattering events and thermalization effects from the neutron scatter. These effects can bolster neutron yield derivations via unique room geometries and, in general, higher absorption cross-section values for lower neutron energies. We report on neutron yield detector characterization, calibrated against NSTec´s dense plasma focus for a known neutron yield, and the build-up factors calculated with MCNP necessary for a measurement of a correct neutron yield at NTF.