Applicability of passive neutron non-destructive assay technique for Pu quantification in advanced fast fuels

Eguchi, Aya*; Sagara, Hiroshi*; Mitsuboshi, Natsumi; Nagatani, Taketeru 

Advanced fast reactor fuel contains minor actinides and fission products such as lanthanides in addition to uranium and plutonium, and it is supposed to include neutrons and gamma-ray originating from sources other than nuclear materials even in its fresh status. The purpose of this study is to evaluate the applicability of passive neutron nondestructive measurement techniques using coincidence accounting, Differential Die Away Self Interrogation assay technique to the quantification of plutonium in advanced fast reactor fuels. This paper shows the results of Pu-240 effective mass calculation in the Pu neutron sources in the simple simulation design by neutron coincidence accounting for the benchmark of simulation code.