Izvestiya vuzov. Yadernaya Energetika

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

Nuclear Data Uncertainty on Generation IV Fast Reactors Criticality Calculations Analysis Comparison

3/28/2023 2023 - #01 Modelling processes at nuclear facilities

Chereshkov D.G. Ternovykh M.Y. Tikhomirov G.V. Ryzhkov A.A.

DOI: https://doi.org/10.26583/npe.2023.1.14

UDC: 621.039.51.17

The new calculation code capabilities are applied in the current work as well as important fast reactor criticality parameters uncertainty assessment articles’ results based on nuclear data libraries and covariance matrices. A comparative analysis of uncertainty estimations related to neutron reactions is presented for lead-cooled reactor models and sodium-cooled reactor models. For the models of advanced BN and BR fast reactors on three fuel types (UO2, MOX, (U-Pu)N), the multiplication factor uncertainty calculations are performed using 252-group covariance matrices based on the ENDF/B-VII.1 library via the SCALE 6.2.4 code system. The main uncertainty sources in the multiplication factor are determined. Recommendations are formulated for improving the cross sections accuracy for several nuclides in order to provide more reliable results of fast reactor criticality calculations. Lead-cooled reactors have no operational history compared to light-water and sodium-cooled reactors. The experimental data insufficiency calls into question the reliability of the simulation results and requires a comprehensive initial data uncertainty analysis for a neutron transport simulation. The obtained results support the idea that lead- and sodium-cooled reactors have similar nuclear data sensitivity when the same computation tools, nuclear data libraries and fuel compositions are used. This makes it possible to use the accumulated data of benchmarks for sodium-cooled reactors in the safety justification of lead-cooled reactors.


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fast reactors Generation IV covariance matrices sensitivity coefficient uncertainty SCALE MNPU MOX

Link for citing the article: Chereshkov D.G., Ternovykh M.Y., Tikhomirov G.V., Ryzhkov A.A. Nuclear Data Uncertainty on Generation IV Fast Reactors Criticality Calculations Analysis Comparison. Izvestiya vuzov. Yadernaya Energetika. 2023, no. 1, pp. 162-174; DOI: https://doi.org/10.26583/npe.2023.1.14 (in Russian).