Abstract
The shielding properties of commercial materials of reactor Experiments, Inc. (R/X) were analyzed at the facility which includes bare heavy water experimental reactor RB with external neutron converter ENC, The fast neutron spectrum measurements in energy range from 1 MeV to 10 MeV was performed using ORTEC semiconductor neutron detector with He{sup 3} in diode coincidence arrangement. The neutron spectra have been evaluated from measured pulse-height distribution using numerical code HE3 for computation of detector efficiency in a collimated neutron beam. The neutron dose rates behind ENC with and without sample R/X material were determined using cubic spline interpolation routine for calculating the corresponding flux-dose rate conversion factors. Satisfactory shielding properties of the examined material in a fast neutron field in measurements and calculations are demonstrated. (author)
Avdic, S;
Pesic, M;
[1]
Marinkovic, P
[2]
- Boris Kidric, Institute of Nuclear Sciences, Beograd (Yugoslavia)
- ETF Belgrade Univ. (Yugoslavia)
Citation Formats
Avdic, S, Pesic, M, and Marinkovic, P.
{sup 3}He detector analysis of some special shielding materials.
Serbia: N. p.,
1990.
Web.
Avdic, S, Pesic, M, & Marinkovic, P.
{sup 3}He detector analysis of some special shielding materials.
Serbia.
Avdic, S, Pesic, M, and Marinkovic, P.
1990.
"{sup 3}He detector analysis of some special shielding materials."
Serbia.
@misc{etde_21083746,
title = {{sup 3}He detector analysis of some special shielding materials}
author = {Avdic, S, Pesic, M, and Marinkovic, P}
abstractNote = {The shielding properties of commercial materials of reactor Experiments, Inc. (R/X) were analyzed at the facility which includes bare heavy water experimental reactor RB with external neutron converter ENC, The fast neutron spectrum measurements in energy range from 1 MeV to 10 MeV was performed using ORTEC semiconductor neutron detector with He{sup 3} in diode coincidence arrangement. The neutron spectra have been evaluated from measured pulse-height distribution using numerical code HE3 for computation of detector efficiency in a collimated neutron beam. The neutron dose rates behind ENC with and without sample R/X material were determined using cubic spline interpolation routine for calculating the corresponding flux-dose rate conversion factors. Satisfactory shielding properties of the examined material in a fast neutron field in measurements and calculations are demonstrated. (author)}
place = {Serbia}
year = {1990}
month = {Jul}
}
title = {{sup 3}He detector analysis of some special shielding materials}
author = {Avdic, S, Pesic, M, and Marinkovic, P}
abstractNote = {The shielding properties of commercial materials of reactor Experiments, Inc. (R/X) were analyzed at the facility which includes bare heavy water experimental reactor RB with external neutron converter ENC, The fast neutron spectrum measurements in energy range from 1 MeV to 10 MeV was performed using ORTEC semiconductor neutron detector with He{sup 3} in diode coincidence arrangement. The neutron spectra have been evaluated from measured pulse-height distribution using numerical code HE3 for computation of detector efficiency in a collimated neutron beam. The neutron dose rates behind ENC with and without sample R/X material were determined using cubic spline interpolation routine for calculating the corresponding flux-dose rate conversion factors. Satisfactory shielding properties of the examined material in a fast neutron field in measurements and calculations are demonstrated. (author)}
place = {Serbia}
year = {1990}
month = {Jul}
}