Izvestiya vuzov. Yadernaya Energetika

The peer-reviewed scientific and technology journal. ISSN: 0204-3327

Verifcation of ABBN constants and CONSYST code in criticality calculations

7/14/2014 2014 - #02 Physics and technology of nuclear reactors

Golovko Yu. E. Koscheev V.N. Lomakov G.B. Manturov G.N. Rozhikhin E.V. Semenov M.Yu. Tsiboulya A.M. Yakunin A.A.

DOI: https://doi.org/10.26583/npe.2014.2.11

UDC: 621.039.51.17

The aim of current work is verification of up-to-date BNAB neutron constants library and CONSYST code for neutron constants preparation via calculations of a set of simplified calculation models of nuclear power systems and critical experiments from international handbook ICSBEP.

There is the description of up-to-date version of BNAB neutron constants library which was obtained from evaluated neutron data files RUSFOND2010 and intended for perspective fast reactor models calculations in current paper materials. The verification process is based on calculation results comparisons for numerous benchmark-models of critical experiments and simplified models of nuclear power systems – «Pruvost curves» – calculated by means of MMKKENO code with MCNP calculation results. The comparison with experimental data was made. Based on benchmark-experiments with fast neutron spectra the results of testing of neutron constants preparation method laid in up-to-date version of CONSYST code with BNAB neutron constants is given in paper. These results were obtained by means ofcomparison with calculation results using BNAB cross-sections prepared by TRANSX code.

Following the results of performed work a key conclusion have been made that the methodical uncertainty caused by applying the group-wise approach is estimated as less than ±0.2% Δk/k.


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neutron cross-sections RUSFOND BNAN-RF verification benchmark model Monte-Carlo method criticality