Izvestiya vuzov. Yadernaya Energetika

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

Calculation and Experimental Analysis of Integral Experiments with Fast Neutron Spectrum and Models of Sodium- and Lead-Cooled Fast Reactors based on Different Evaluated Nuclear Data Libraries

3/18/2021 2021 - #01 Physics and technology of nuclear reactors

Andrianova O.N. Golovko Yu. E. Zherdev G.M. Lomakov G.B. Teplukhina E.S.

DOI: https://doi.org/10.26583/npe.2021.1.07

UDC: 621.039.51.17

The paper deals with a comparative analysis of criticality calculations using a Monte-Carlo neutronic code and the BNAB-93 and BNAB-RF multi-group nuclear data libraries as well as evaluated neutron data files from the Russian ROSFOND library and foreign libraries (ENDF, JENDL, JEFF) of different years. The object of analysis was a set of integral experiments on BFS facilities performed in different years at the Institute of Physics and Power Engineering (60 different critical configurations). The considered integral experiments are included in the base of evaluated experimental neutron-physical data, intended to substantiate the neutronic characteristics of fast reactors (FR) with sodium and lead coolants, to verify the neutronic codes nuclear data, and to estimate the nuclear data component of the uncertainties associated with neutronic parameters of fast reactors. It is shown that the ROSFOND evaluated nuclear data library is a library that minimizes the calculation and experimental discrepancies for the considered set of integral experiments. The authors also present the results of calculating the criticality for the models of fast reactors with sodium and lead coolants based on various libraries of evaluated neutron data and give an estimate of the nuclear data component of the calculated uncertainties. Based on the results of the analysis, a conclusion is made on the directions of further development of Russian nuclear data for fast reactor neutronics calculations.

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integral experiments BFS ENDF JENDL JEFF ROSFOND ABBN database ща integral experiments fast neutron reactors