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Journal Information-measuring and Control Systems №6 for 2011 г.
Article in number:
Nuclear reactor-s neutron flux modeling application in case of technological characteristics random perturbations
Authors:
A. M. Zagrebayev, V. A. Nasonova
Abstract:
In this paper the mathematical model and application for nuclear reactor-s neutron flux statistical investigation are described. The goal for developing the application was verification of the possibility to determine the significant parameters for accident-free nuclear reactor running via neutron flux statistical characteristics in passive experiment. As mathematical model authors use correlated equation of reactor neutron physics with fluctuating absorption cross-section, thermal physics and control equations. Mathematical model numerical realization in application uses finite-difference implicit method. The application can be divided into four parts according to functionality: calculation, input, output and statistical processing. In the application it is possible to build the model dynamically i. e. the user can choose witch feedbacks (including control system) should be included into calculation. Also user can set output characteristics and feedback parameters, such as constants, reactivity coefficients structure and values. Numerical calculations proved that the application correctly represent physical processes in nuclear reactor and can be used for statistical researches.
Pages: 59-65
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