Izvestiya vuzov. Yadernaya Energetika

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

Improvement both of silicon and uranium neutron data based on integral and differential experiments

3/28/2016 2016 - #01 Modelling processes at nuclear facilities

Andrianova O.N. Lomakov G.B. Manturov G.N.

DOI: https://doi.org/10.26583/npe.2016.1.07

UDC: 539.17.013

This paper presents the results of calculation-to-experiment discrepancy analysis for differential (neutron transmission measurements) and integral experiments from ICSBEP Handbook (series of critical assemblies BFS-79 and BFS-81) carried out at the IPPE to examine the properties of fuel and structural materials on the basis of which were made proposals to corrections of neutron cross-sections for the Russian national library of evaluated neutron data (ROSFOND). The considered study is an example of implementing the framework for co-utilization of differential and integral experiments for neutron data adjustments, which demonstrate the impact of the resonance structure in neutron cross-sections on reactor characteristics measured at the BFS facilities.

One of the current trends in reactor physics is to improve accuracy of reactor characteristics assessment by reducing the neutron data uncertainty component in the overall calculation error. Sophisticated statistical approaches have been proposed and are nowadays widely used for the assessment of reactor characteristics uncertainties caused by nuclear data. Especially valuable is that such approaches provide capabilities to propagate point-wise nuclear data uncertainty on reactor characteristics uncertainties that allows carrying out neutron cross-sections adjustments with due account for both differential and integral experiments.

Neutron cross-sections testing and adjustments can be carried out based on new and more precise measurements of nuclear interaction characteristics as well as by means of revaluation of the existing experimental data sets. Since the capabilities of recent experimental techniques have been virtually exhausted and carrying out new experiments requires substantial time and material expenditures, the most realistic way to reduce the neutron data uncertainty in reactor functional calculations is to use evaluated neutron data obtained by taking into account all the experimental data including previously unconsidered.


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evaluated neutron data ROSFOND library critical experiments BFS facility neutron transmission