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Radiation Protection Dosimetry 85:79-84 (1999)
© 1999 Oxford University Press

Experimental and Monte Carlo Evaluations of the Dosimetric Characteristics of a Thermal Neutron Calibration Assembly

E. Vilela, B. Morelli, G. Gualdrini, K.W. Burn and F. Monteventi

A thermal neutron assembly for calibrating dosimetric instruments at the ENEA Radiation Protection Institute is described. The characterisation of such a facility in terms of spectral neutron fluence rate and ambient dose equivalent rate according to the ICRP 60 document is shown in detail. The developed study was aimed at characterising all the components of the field inside the three calibration cavities placed within a polyethylene cube. In addition to the experimental point of view, the assembly was also numerically investigated by means of the Monte Carlo code MCNP. These techniques allowed us to calculate, besides the dosimetric quantities to be compared with the experimental results, the detailed neutron spectra along the cavities. Special variance reduction algorithms developed at ENEA allowed satisfactory statistics to be obtained for each energy group of the spectra.


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