Danilychev A.V., Korobeynikova L.V., Seregin A.S., Stogov V.Yu., Tchornyi V.A.
State Scientific Centre - A.I. Leipunsky Institute for Physics and Power Engineering,
Obninsk, Russia, Россия
Combined results of material worth calculation for IAEA benchmark model (BN-600 type reactor with hybrid core) are given. Comparison of results calculated by different participants permits to evaluate the accuracy of reactivity coefficient calculation and to formulate the requirements for modernization of codes currently in use for this purpose. Digital verification experiment performed constitutes additional substantiation of the most important neutronics parameters of hybrid BN-600 reactor safety.
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