Abstract

The neutron flux trap effect was experimentally studied in the subcritical assembly of the Atomic and Nuclear Physics Laboratory of the Aristotle University of Thessaloniki, using delayed gamma neutron activation analysis. Measurements were taken within the natural uranium fuel grid, in vertical levels symmetrical to the Am–Be neutron source, before and after the removal of fuel elements, permitting likewise a basic study of the vertical flux profile. Three identical flux traps of diamond shape were created by removing four fuel rods for each one. Two (n, γ) reactions and one (n, p) threshold reaction were selected for thermal, epithermal and fast flux study. Results of thermal and epithermal flux obtained through the ¹⁹⁷Au (n, γ) ¹⁹⁸Au and ¹⁸⁶W (n, γ) ¹⁸⁷W reactions, with and without Cd covers, to differentiate between the two flux regions. The ⁵⁸Ni (n, p) ⁵⁸Co reaction was used for the fast flux determination. An interpolation technique based on local procedures was applied to fit the cross sections data and the neutron flux spectrum. End results show a maximum thermal flux increase of 105% at the source level, pointing to a high potential to increase in the available thermal flux for future experiments. The increase in thermal flux is not accompanied by a comparable decrease in epithermal or fast flux, since thermal flux gain is higher than epithermal and fast neutron flux loss. So, the neutron reflection is mainly responsible for the thermal neutron increase, contributing to 89% at the central axial position.

K. Routsonis, S. Stoulos, A. Clouvas, N. Catsaros, M. Varvayianni & M. Manolopoulou  Radiation Effects and Defects in Solids,  2016 171:9-10, 746-753, DOI: 10.1080/10420150.2016.1257620