EPJ Web Conf.
Volume 170, 2018ANIMMA 2017 – Advancements in Nuclear Instrumentation Measurement Methods and their Applications
|Number of page(s)||6|
|Section||Decommissioning, dismantling and remote handling|
|Published online||10 January 2018|
Stochastic approach for radionuclides quantification
Nuclear Measurement Laboratory, French Commissariat à l’Energie Atomique, CEA/DAM/VA, F-21120 Is-sur-Tille
French Commissariat à l’Energie Atomique, CEA/DAM/DIF, F-91297 Arpajon CEDEX, France firstname.lastname@example.org, email@example.com
Published online: 10 January 2018
Gamma spectrometry is a passive non-destructive assay used to quantify radionuclides present in more or less complex objects. Basic methods using empirical calibration with a standard in order to quantify the activity of nuclear materials by determining the calibration coefficient are useless on non-reproducible, complex and single nuclear objects such as waste packages. Package specifications as composition or geometry change from one package to another and involve a high variability of objects. Current quantification process uses numerical modelling of the measured scene with few available data such as geometry or composition. These data are density, material, screen, geometric shape, matrix composition, matrix and source distribution. Some of them are strongly dependent on package data knowledge and operator backgrounds. The French Commissariat à l’Energie Atomique (CEA) is developing a new methodology to quantify nuclear materials in waste packages and waste drums without operator adjustment and internal package configuration knowledge. This method suggests combining a global stochastic approach which uses, among others, surrogate models available to simulate the gamma attenuation behaviour, a Bayesian approach which considers conditional probability densities of problem inputs, and Markov Chains Monte Carlo algorithms (MCMC) which solve inverse problems, with gamma ray emission radionuclide spectrum, and outside dimensions of interest objects. The methodology is testing to quantify actinide activity in different kind of matrix, composition, and configuration of sources standard in terms of actinide masses, locations and distributions. Activity uncertainties are taken into account by this adjustment methodology.
Key words: Nuclear quantification / Bayes Theorem / MCMC / Monte Carlo sampling
© The Authors, published by EDP Sciences, 2018
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited. (http://creativecommons.org/licenses/by/4.0/).
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