Abstract
The report presents the results of an analysis of benchmark experiments form the international ICSBEP Handbook (HEU-MET-INTER-005) carried out at the the SSC RF – IPPE in cooperation with the Idaho National Laboratory (INL, USA) applicable to the verification of calculations of a wide range of tasks related to safe storage of vitrified radioactive waste. Experiments on the BFS assemblies make it possible to perform a large series of studies needed for neutron data refinement, including measurements of reactivity effects which allow testing the neutron cross section resonance structure. This series of studies is considered as a sample joint analysis framework for differential and integral experiments required to correct nuclea data files of the ROSFOND evaluated neutron data library. Thus, it is shown that despite the wide range of available experimental data, in so far as it relates to the resonance region refinement, the experiments on reactivity measurement make it possible to more subtly reflect the resonance structure peculiarities in addition to the time-of-flight measurement method.
Highlights
Over the last few decades, data on BFS reactor physics experiments carried out at the SSC RF-IPPE have been widely used for correcting both nuclear data systems and software tools to be applied in calculation support for power and research reactors
Sophisticated statistical approaches have been proposed and are nowadays widely used for the assessment of reactor characteristics uncertainties caused by nuclear data uncertainties [for instance, 3–5]. Valuable is that such approaches provide capabilities to propagate pointwise nuclear data uncertainty on reactor characteristics uncertainties that allows carrying out neutron crosssections adjustments with due account for both differential and integral experiments
In cooperation with Idaho National Laboratory a program of critical experiments was executed on the BFS-1 facility at the SSC RF-IPPE
Summary
Over the last few decades, data on BFS reactor physics experiments carried out at the SSC RF-IPPE have been widely used for correcting both nuclear data systems and software tools to be applied in calculation support for power and research reactors. Neutron cross-section data were obtained from the experiments carried out at different times with different BFS core configurations and compositions to examine the properties of fuel and structural materials [1]. These data were used for corrections of the ABBN-group constant system and the ROSFOND – Russian library of evaluated neutron data [2]. Valuable is that such approaches provide capabilities to propagate pointwise nuclear data uncertainty on reactor characteristics uncertainties that allows carrying out neutron crosssections adjustments with due account for both differential and integral experiments
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