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Energy distribution of the neutron flux measurements at the Chilean Reactor RECH-1 using multi-foil neutron activation and the Expectation Maximization unfolding algorithm.
Applied Radiation and Isotopes 2017 November
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.
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