We present a methodology to obtain the energy distribution of the neutron flux of an experimental nuclear reactor, using multi-foil activation measurements and the Expectation Maximization unfolding algorithm, which is presented as an alternative to well known unfolding methods such as GRAVEL. Self-shielding flux corrections for energy bin groups were obtained using MCNP6 Monte Carlo simulations. We have made studies at the at the Dry Tube of RECH-1 obtaining fluxes of 1.5(4)×1013 cm−2 s−1 for the thermal neutron energy region, 1.9(5)×1012 cm−2 s−1 for the epithermal neutron energy region, and 4.3(11)×1011 cm−2 s−1 for the fast neutron energy region.
- Expectation maximization
- Experimental reactor neutron flux distribution
- Neutron activation
ASJC Scopus subject areas