Analysis of neutron flux distribution for the validation of computational methods for the optimization of research reactor utilization

In order to verify and validate the computational methods for neutron flux calculation in TRIGA research reactor calculations a series of experiments has been performed The neutron activation method was used to verify the calculated neutron flux distribution in the TRIGA reactor Aluminium (99 9 wt%)-Gold (0 1 wt%) foils (disks of 5 mm diameter and 02 mm thick) were irradiated in 33 locations 6 in the core and 27 in the carrousel facility in the reflector The experimental results were compared to the calculations performed with Monte Carlo code MCNP using detailed geometrical model of the reactor The calculated and experimental normalized reaction rates in the core are in very good agreement for both isotopes indicating that the material and geometrical properties of the reactor core are modelled well In conclusion one can state that our computational model describes very well the neutron flux and reaction rate distribution in the reactor core In the reflector however the accuracy of the epithermal and thermal neutron flux distribution and attenuation is lower mainly due to lack of information about the material properties of the graphite reflector surrounding the core but the differences between measurements and calculations are within 10% Since our computational model properly describes the reactor core it can be used for calculations of reactor core parameters and for optimization of research reactor utilization (C) 2010 Elsevier Ltd All rights reserved