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BURNUP CALCULATIONS USING THE ORIGEN CODE IN THE CONKEMO COMPUTING SYSTEM
Authors & Affiliations
Zabrodskaya S.V., Khomyakov Yu.S., Tsibulya A.A.
State Scientific Centre - A.I. Leipunsky Institute for Physics and Power Engineering, Obninsk, Russia
This article describes the CONKEMO computing system for kinetic multigroup calculations of nuclear reactors and their physical characteristics during burnup. The ORIGEN burnup calculation code has been added to the system. The results of an international benchmark calculation are also presented.
kinetic multigroup calculations, nuclear reactors, CONKEMO, physical characteristics, MOX fuel, nuclear data, library ABBN-93, ORIGEN, burnup calculation
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