MCNP-POLIMI SIMULATION OF ACTIVE AND PASSIVE MEASUREMENTS ON URANIUM AND PLUTONIUM OBJECTS

Year
2003
Author(s)
John T. Mihalczo - Oak Ridge National Laboratory
John K. Mattingly - Oak Ridge National Laboratory
Sara Pozzi - Oak Ridge National Laboratory
E. Padovani - Department of Nuclear Engineering
Abstract
ABSTRACT This paper presents the validation of the Monte Carlo code MCNP-PoliMi for the simulation of nuclear safeguards experiments with plutonium and uranium metal based on fast time-correlation measurements. A comparison is presented between experimental data acquired with the Nuclear Materials Identification System and the Monte Carlo simulations. The measurements and simulations were performed for assemblies of delta-phase plutonium metal shells of varying inner and outer diameter, in both passive and active mode, and for a highly enriched uranium annular metal casting in active mode. The simulation results are generally in good agreement with the measurement. The areas of partial disagreement with the measured data are discussed.