Optimization of Shielding- Collimator Parameters for ING-27 Neutron Generator Using MCNP5

Neutron generators are now used in various fields. They produce only fast neutrons; D-D neutron generator produces 2.45 MeV neutrons and D-T produces 14.1 MeV neutrons. In order to optimize shielding-collimator parameters to achieve higher neutron flux at the investigated sample (The signal) with lo...

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Main Authors: Hegazy Aya Hamdy, Skoy V.R., Hossny K.
Format: Article
Language:English
Published: EDP Sciences 2018-01-01
Series:EPJ Web of Conferences
Online Access:https://doi.org/10.1051/epjconf/201817702003
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spelling doaj-998b578d381a4fa8877e7605b96417462021-08-02T09:46:45ZengEDP SciencesEPJ Web of Conferences2100-014X2018-01-011770200310.1051/epjconf/201817702003epjconf_ayss2018_02003Optimization of Shielding- Collimator Parameters for ING-27 Neutron Generator Using MCNP5Hegazy Aya HamdySkoy V.R.Hossny K.Neutron generators are now used in various fields. They produce only fast neutrons; D-D neutron generator produces 2.45 MeV neutrons and D-T produces 14.1 MeV neutrons. In order to optimize shielding-collimator parameters to achieve higher neutron flux at the investigated sample (The signal) with lower neutron and gamma rays flux at the area of the detectors, design iterations are widely used. This work was applied to ROMASHA setup, TANGRA project, FLNP, Joint Institute for Nuclear Research. The studied parameters were; (1) shielding-collimator material, (2) Distance between the shielding-collimator assembly first plate and center of the neutron beam, and (3) thickness of collimator sheets. MCNP5 was used to simulate ROMASHA setup after it was validated on the experimental results of irradiation of Carbon-12 sample for one hour to detect its 4.44 MeV characteristic gamma line. The ratio between the signal and total neutron flux that enters each detector was calculated and plotted, concluding that the optimum shielding-collimator assembly is Tungsten of 5 cm thickness for each plate, and a distance of 2.3 cm. Also, the ratio between the signal and total gamma rays flux was calculated and plotted for each detector, leading to the previous conclusion but the distance was 1 cm.https://doi.org/10.1051/epjconf/201817702003
collection DOAJ
language English
format Article
sources DOAJ
author Hegazy Aya Hamdy
Skoy V.R.
Hossny K.
spellingShingle Hegazy Aya Hamdy
Skoy V.R.
Hossny K.
Optimization of Shielding- Collimator Parameters for ING-27 Neutron Generator Using MCNP5
EPJ Web of Conferences
author_facet Hegazy Aya Hamdy
Skoy V.R.
Hossny K.
author_sort Hegazy Aya Hamdy
title Optimization of Shielding- Collimator Parameters for ING-27 Neutron Generator Using MCNP5
title_short Optimization of Shielding- Collimator Parameters for ING-27 Neutron Generator Using MCNP5
title_full Optimization of Shielding- Collimator Parameters for ING-27 Neutron Generator Using MCNP5
title_fullStr Optimization of Shielding- Collimator Parameters for ING-27 Neutron Generator Using MCNP5
title_full_unstemmed Optimization of Shielding- Collimator Parameters for ING-27 Neutron Generator Using MCNP5
title_sort optimization of shielding- collimator parameters for ing-27 neutron generator using mcnp5
publisher EDP Sciences
series EPJ Web of Conferences
issn 2100-014X
publishDate 2018-01-01
description Neutron generators are now used in various fields. They produce only fast neutrons; D-D neutron generator produces 2.45 MeV neutrons and D-T produces 14.1 MeV neutrons. In order to optimize shielding-collimator parameters to achieve higher neutron flux at the investigated sample (The signal) with lower neutron and gamma rays flux at the area of the detectors, design iterations are widely used. This work was applied to ROMASHA setup, TANGRA project, FLNP, Joint Institute for Nuclear Research. The studied parameters were; (1) shielding-collimator material, (2) Distance between the shielding-collimator assembly first plate and center of the neutron beam, and (3) thickness of collimator sheets. MCNP5 was used to simulate ROMASHA setup after it was validated on the experimental results of irradiation of Carbon-12 sample for one hour to detect its 4.44 MeV characteristic gamma line. The ratio between the signal and total neutron flux that enters each detector was calculated and plotted, concluding that the optimum shielding-collimator assembly is Tungsten of 5 cm thickness for each plate, and a distance of 2.3 cm. Also, the ratio between the signal and total gamma rays flux was calculated and plotted for each detector, leading to the previous conclusion but the distance was 1 cm.
url https://doi.org/10.1051/epjconf/201817702003
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