Published date:Feb 21 2018

Journal Title: KnE Engineering

Issue title: XIII International Youth Scientific and Practical Conference "FUTURE OF ATOMIC ENERGY - AtomFuture 2017"

Pages:490-499

DOI: 10.18502/keg.v3i3.1650

V.Y. Shorov

S.N. Ryzhov

M.Y. Ternovykh

G.V. Tikhomirov

In this work was carried out the simulation in the SCALE6 code of an experiment on the BN-600 reactor on irradiating of fuel assemblies, containing samples of mixed nitride uranium-plutonium fuel. A comparison of the results for SCALE6 on the results of other codes is presented. The results of an estimation of uncertainties in the calculated data connected with uncertainties of an irradiation of an experimental sample and used neutron cross-sections library. Discussion of possible differences between analytical and experimental results is given.

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