Abstract
A new analysis technique for the composition measurement of mixed nuclear material by using a ssion neutron multiplicity distribution is proposed on the basis of the fact that the ssion neutron multiplicity distribution of each isotope has its own characteristics. The feasibility study for identifying a single isotope and determining the composition of a mixed material has been carried out using the Monte Carlo simulation method. The neutron counter system is simulated with the MCNPX code. In the single isotope case, the measured neutron multiplicity distributions result in over 1.0% dierence from that of each individual isotope using the following six isotopes simulated: 238 Pu, 240 Pu, 242 Pu, 242 Cm, 244 Cm, 252 Cf. In the mixed nuclear material case, the mixed materials of 239 Pu and 244 Cm isotopes are simulated with various mixing ratios. The neutron multiplicity distributions for the mixture of 239 Pu and 244 Cm are distinguishable when the mass mixing ratio of 244 Cm to 239 Pu is less than 10 8 and the composition of the mixture is measured by 1.0% relative
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