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Monte carlo simulations of gamma images: application to plutonium rich mixed carbide fuel

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Abstract

A novel approach for quantitave characterisation of nuclear fuel for homogeneity based on comparison of autoradiographs with simulated standards is proposed. Autoradiographs which are self generated radiation images are ususally only qualitatively evaluated due to the absence of calibration standards for reference which are not practically possible to synthesize in all possible variations owing to the difficulty in handling plutonium. Monte Carlo simulation for radiation transport has been attempted for the first time to estimate the minimum detectable limit (MDL) of pure PuC agglomerate and generate virtual autoradiographic images of plutonium rich mixed carbide fuel for visual comparison reference purpose.

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Acknowledgements

The authors express their sincere thanks to Shri.Vivek Bhasin, Associate director, Nuclear Fuels Group, BARC, Dr. Tapas Bandyopadhyay, HPD, Dr.R.M.Tripathi, Head, HPD and Dr. K.S. Pradeepkumar, Associate director, Health & Safety group, BARC, for their support.

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Authors and Affiliations

  1. Radiometallurgy Division, Bhabha Atomic Research Centre, Mumbai, 400094, India

    K. V. Vrinda Devi

  2. Health Physics Division, Bhabha Atomic Research Centre, Mumbai, 400094, India

    K. Biju

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  1. K. V. Vrinda Devi
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  2. K. Biju
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Correspondence to K. V. Vrinda Devi.

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Devi, K.V.V., Biju, K. Monte carlo simulations of gamma images: application to plutonium rich mixed carbide fuel. J Radioanal Nucl Chem 319, 167–173 (2019). https://doi.org/10.1007/s10967-018-6252-z

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  • DOI: https://doi.org/10.1007/s10967-018-6252-z

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