Experimental determination and simulation of neutron and gamma flux parameters in horizontal channel for Prompt Gamma Neutron activation analysis implementation at Es-Salam research reactor

Experimental determination and simulation of neutron and gamma flux parameters in horizontal channel for Prompt Gamma Neutron activation analysis implementation at Es-Salam research reactor

Since 2004, the k0-standardization method has been applied and evaluated in three experimental channels at Es-Salam research reactor of the Algerian Centre de Recherche Nucléaire de Birine (CRNB). The NAA laboratory at CRNB is well involved in the implementation of the Prompt Gamma Neutron Activatio...

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Bibliographic Details
Published in:Applied radiation and isotopes Vol. 174; p. 109759
Main Authors: Hamidatou, L., Slamene, H., Dbacha, B., Aït-ziane, M., Badreddine, A., Benaskeur, N., Benkharfia, H., Alliti, M., Attari, K., Hachouf, M., Djebli, K., Lounis-Mokrani, Z.
Format: Journal Article
Language:English
Published: England Elsevier Ltd 01-08-2021
Subjects:
Activation detectors
LiF
Neutron and gamma spectrum
PGNAA method
SCALE package
Simulation
Thermal and epithermal fluxes
TLD 600
TLD 700
PGNAA method
Simulation
Ti
SCALE package
LiF
Neutron and gamma spectrum
Thermal and epithermal fluxes
Mg
TLD 700
TLD 600
Activation detectors
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Summary:Since 2004, the k0-standardization method has been applied and evaluated in three experimental channels at Es-Salam research reactor of the Algerian Centre de Recherche Nucléaire de Birine (CRNB). The NAA laboratory at CRNB is well involved in the implementation of the Prompt Gamma Neutron Activation Analysis to extend the field of analyses to some additional elements to the NAA method. In the frame work of the PGNAA research project, several works have been carried out in the present study including the experimental and simulation characterization of neutron and gamma flux parameters of the horizontal channel. The absolute and relative neutron fluxes of the studied channel have been determined by using a set of monitors including Al, Au, Cu, Fe and Zr. Furthermore, measurements of gamma and thermal neutron doses have been achieved using LiF: Mg, Ti (TLD 600 and TLD 700) detectors. The gamma dose rate at the experimental channel center position was found to be 0.6 Gy/min·MW. The experimental results obtained in this study have been used as input information for simulations and design of neutron facilities and radiation shielding, which are successfully established by SCALE code. The results were compared in terms of spectral detail and precision and a good agreement has been revealed. The value of the thermal neutron flux was found to be (6.29 ± 0.25) E+08 n/cm2.s which allows the implementation of PGNAA at the Es-Salam research reactor. •Experimental determination of Neutron Fluxes and epithermal neutron flux shape parameters in the horizontal channel of the Es-Salam Research Reactor in the frame work of PGNAA method implementation•The thermal, epithermal and fast neutron fluxes were determined by the method of foil activation•Determination of the gamma and thermal neutron dose rates using Thermoluminescent Detector (TLD) systems: LiF: Mg, Ti (TLD 600 and TLD 700) detectors•A simulation approach has been performed using SCALE 6.1 code and the outputs data were compared to the experimental results•The comparison was made in terms of spectral detail and precision
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ISSN:0969-8043
1872-9800
DOI:10.1016/j.apradiso.2021.109759