Year
2016
Abstract
Neutron resonance transmission analysis (NRTA) is one of the plausible non-destructive assay techniques to measure U and Pu contents in a nuclear fuel. To apply the NRTA technique to quantification of spent fuels, next-generation Minor Actinides (MA)-Pu fuels and fuel debris, a compact NRTA system is needed and its prototype is under development. In this proceeding performance of a prototype using a DT tube with pulse width of 10 ?s is shown with Monte Carlo simulations. We optimized neutron flux in the thermal to epithermal energy region by changing thickness of polyethylene of a neutron source part. A transmission spectrum with the prototype is calculated in the case of application to spent fuel. We also compute a transmission spectrum obtained by a future compact NRTA system that has a small-type electron linear accelerator. A comparison between the two compact NRTA systems is briefly discussed.