Neutron yield calculation from (α, n) reactions with SOURCES4

Abstract

Neutrons can induce background events in underground experiments looking for rare processes. Neutrons in a MeV range in deep underground laboratories are produced in spontaneous fission processes and (α, n) reactions. A number of computer codes are available to calculate cross-sections of (α, n) reactions, branching ratios to various states and neutron yields. We have used the SOURCES4 code to calculate neutron yields and energy spectra with input cross-sections and branching ratios taken from experimental data and calculations based on EMPIRE2.19/3.2.3 and TALYS1.9. We report here a comparison of SOURCES4 calculations with experimental data obtained with alpha beams with fixed energies.

Neutron production in ($\alpha$,n) reactions in SOURCES4

“…Above this energy and for branching ratios the model from TALYS1.9 [20] was implemented (see also Ref. [27] for the comparison of data and models for 19 F and some other isotopes). The neutron yields from SOURCES4A are in good agreement with data.…”