The results were further validated by Monte Carlo (MCNP) simulations.  For the geometry of studied rods, the MCNP calculation were done to calculate the dependence of the response to delayed neutrons on rod enrichment, to show the viability to use the method for rod enrichment verification.  An option of using cadmium inset in irradiation channel to overcome the effect of self-shielding for samples with higher enrichment was proposed, experimentally tested, and evaluated through MCNP calculations.
MCNP
The paper deals with delayed neutron counting of uranium pins with P385 portable DD neutron generator in polyethylene-based setup. 
P385 portable DD neutron generator