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 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.

Neutron tomography simulation by MAVRIC/Monaco code.

In this study, MAVRIC/Monaco module integrated with SCALE6.1 package is used to elucidate experimental neutron transmission for various neutron-absorbing materials. Neutron beam hardening and its effect on shielding calculation and tomographic image reconstruction accuracy are presented. The experimental data for studied materials are used for comparison purpose and to prove the capability of MAVRIC/Monaco code in neutron tomography simulation. The good agreement between experimental and calculated values confirms the capability of SCALE6.1 package in obtaining physical data exactly analogous to an experimental measurement.