The reconstruction of fields and adjustment of the parameters of reactor models are increasingly prioritized for reactor physics because the efficiency and safety of the control of a nuclear plant depend on solving them. The results of reconstruction and parameter adjustments are largely determined by the probability distributions of the computed and measured data. The probability distribution of the computed data in turn depends on the properties of the neutron-physical model and probabilistic characteristics of the parameters of this model. The present work is devoted to the search for and investigations of efficient algorithms for calculating the covariation functions of the neutron flux density. A model of a stationary subcritical reactor with an internal neutron source is studied. Linear perturbation theory, the theorem on the spectral decomposition of operators, and the theory of stochastic processes are the tools used for performing the analysis.
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Translated from Atomnaya Énergiya, Vol. 117, No. 5, pp. 243–248, November, 2014.
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Cherezov, A.L., Shchukin, N.V., Semenov, A.A. et al. Calculation of the Covariation Matrix of the Neutron Flux Density in the Multigroup Diffusion Model of a Subcritical Reactor. At Energy 117, 299–306 (2015). https://doi.org/10.1007/s10512-015-9925-5
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DOI: https://doi.org/10.1007/s10512-015-9925-5