Abstract
PuBeneutrons sources of Educational Neutron Laboratory in the Center for Physical Sciences and Technology are used in several activities including neutron activation for educational purposes and laboratory irradiation experiments. In this work we address the dose rate estimation in the irradiation channels of reconstructed PuBe neutron sources storage device in the particular positions dedicated for neutron irradiation experiments using neutron activation analysis (NAA) and MCNP6 modelling.The results on neutron activation of V2O5, MnO2, Al and Na2CO3were analyzed and compared with MCNP6 model prediction results. The conclusions on the actual neutron flux energy distribution and model corrections are drawn. The absolute neutron intensity at dedicated irradiation points as well as neutron and gamma dose rates are obtained.
Highlights
Alpha-neutron sources produce neutrons through the (α, n) reaction: 9Be + α o 13*C on+ 12C; o8Be+n+ α; on+ 3α
In the Educational Neutron Laboratory (ENL) at the Center for Physical Sciences and Technology (CPST) the neutrons are produced by 4 PuBe neutron sources (2 239PuBe and 2 238PuBe) all together are of 4.5·107 n/s of total activity according to existing documents
They are used mainly for educational purposes. They are situated in the neutron storage device on the first floor of the building which construction initially was designed to work with various kinds of radiation
Summary
Alpha-neutron sources produce neutrons through the (α, n) reaction: 9Be + α o 13*C on+ 12C; o8Be+n+ α; on+ 3α. In the Educational Neutron Laboratory (ENL) at the Center for Physical Sciences and Technology (CPST) the neutrons are produced by 4 PuBe neutron sources (2 239PuBe and 2 238PuBe) all together are of 4.5·107 n/s of total activity according to existing documents. They are used mainly for educational purposes. The aim of this work was to estimate the neutron flux intensity and energy distribution in the particular positions dedicated for neutron activation/irradiation experiments. The samples were irradiated at different positions and by measuring γ spectra the neutron flux intensity was identified. Peculiar elements with established neutron capture cross sections – V2O5+KNO3, MnO2+KNO3, Al and Na2CO3+KNO3 have been measured for neutron activation analysis to cover the all (activation) neutron energy diapason from thermal to fast neutron
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