Simulation of neutron generator assisted gamma emission tomography for inspection of fissile content in spent nuclear fuel

Sammanfattning: This is a feasibility study of a new measurement technique for spent nuclear fuel. The technique combines gamma emission tomography with neutron activation analysis. The idea is to measure high-energy characteristic gamma from short-lived fission products and thereby verify the fissile material content in spent nuclear fuel assemblies. Simulations using MCNP were done to estimate the expected detector count rate for these characteristic gammas. The predicted count rate was too slow for the proposed technique to be of practical use. However, several improvements that could increase the count rate of the technique are suggested for further investigation of the prospects of this new technique.