Abstract
The neutron flux distribution within the pool of the SLOWPOKE-2 reactor at the RMC has been characterized using neutron activation measurements as well as MCNP simulations. Westcott equivalent thermal neutron flux values were calculated from measured activities of solutions of Co, Au, and Cd-shielded Au at several reactor flux settings and compared to tabulated fluxes from MCNP simulations. Good agreement was found between the simulated and experimental thermal flux values, while larger uncertainties were highlighted in higher energy neutron fluxes.
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