Advanced Nodal Diffusion code for Reactor Analysis: Status of development

AR. Josek, L. Klecka, V. Stary, R. Vocka, J. Vysoudil, Czech Republic, Nuclear Research Institute Řež

18th Symposium of AER on VVER Reactor Physics and Reactor Safety (2008, Eger, Hungary)
Spectral and Core Calculation

Abstract

ANDREA is a new macrocode for core design and safety evaluation, which is being developed at NRI. The core simulator is based on the nodal expansion method. Standard features such as pinwise power reconstruction and feedback iterations on critical control rod position, boron concentration and reactor power are implemented. Thermomechanical model of the fuel rod is based on FEMAXI-V calculations and the predictions were benchmarked against HRP experimental data. A branch of the code, designed for the calculation of reactivity induced transients, is currently being developed, based on GAKIN method.

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