In the present report a thermal neutron assembly for calibrating dosimetric instruments at the ENEA Radiation Protection Institute is described. The characterization of such a facility in terms of spectral neutron fluence rate and ambient dose equivalent rate according to the ICRP60 document is shown in detail. The developed study was aimed at characterizing all the components of the field inside the three calibration cavities placed within a polyethylene cube. Besides from the experimental point of view, the assembly was also numerically investigated by means of the Monte Carlo code MCNP. These techniques allowed to calculate, besides the dosimetric quantities to be compared with the experimental results, also the detailed neutron spectra along the cavities. Special variance reduction algorithms developed at ENEA allowed to obtain a satisfactory statistics for each energy group of the spectra.
|Titolo:||Experimental and Monte Carlo Evaluations of the Dosimetric Characteristics of a Thermal Neutron Calibration Assembly|
|Data di pubblicazione:||5-lug-1998|
|Appare nelle tipologie:||4.1 Contributo in Atti di convegno|