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Technical Brief

Investigation of 127I(n,2n)126I and 23Na(n,2n)22Na reactions using 252Cf neutron source

[+] Author and Article Information
Martin Schulc

Research Center Rez, Hlavní 130, Husinec Řež 250 68, Czech Republic
martin.schulc@cvrez.cz

Michal Košt'ál

Research Center Rez, Hlavní 130, Husinec Řež 250 68, Czech Republic
michal.kostal@cvrez.cz

Evžen Novák

Research Center Rez, Hlavní 130, Husinec Řež 250 68, Czech Republic
evzen.novak@cvrez.cz

Jan Šimon

Research Center Rez, Hlavní 130, Husinec Řež 250 68, Czech Republic
jan.simon@cvrez.cz

Nicola Burianová

Research Center Rez, Hlavní 130, Husinec Řež 250 68, Czech Republic
nicola.burianova@cvrez.cz

1Corresponding author.

ASME doi:10.1115/1.4039774 History: Received February 09, 2018; Revised March 20, 2018

Abstract

The presented work deals with 23Na(n,2n)22Na and 127I(n,2n)126I reactions in the 252Cf spontaneous fission neutron source. 252Cf neutron source with approximate emission of 6E8 n/s was employed for the irradiation of sodium iodide. The spectrum averaged cross sections were then inferred from experimentally determined reaction rates and compared with calculations in MCNP6 using various nuclear data libraries. The experimental reaction rates were derived from the Net Peak Areas measured using the high purity germanium spectroscopy. The measured spectrum averaged cross section for the 23Na(n,2n)22Na reaction in the 252Cf spectrum was determined as equal to 8.98 ± 0.32 µb. The resulting spectrum averaged cross section for the 127I(n,2n)126I reaction in the 252Cf spectrum was derived as 2.044 ± 0.0072 mb. These experimental data can be used for nuclear data libraries validation and to specify high energy tail of the 252Cf neutron spectrum.

Copyright (c) 2018 by ASME
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