Analysis of auto gamma images of plutonium bearing fuels: a comparative study of experimental and simulation methods

Image analysis and spectroscopic method of evaluation are applied on Gamma auto radiographs (GAR) to assess the effect of plutonium concentration in (U,Pu)O2 mixed oxide (MOX) fuel samples on the characteristics of the irradiated film. Results of the two different methods of GAR analysis are compared with results of the earlier studies using alpha irradiated solid state nuclear track detectors using Pu bearing fuel samples with low as well as high plutonium content. Theoretical simulations using Monte Carlo method of radiation transport were carried out for comprehension of the process of GAR under ideal conditions and results were applied for understanding the relative degree of heterogeneity in Pu bearing fuel samples and compared with that from experimental methods of analysis.