Application of MCPN nonanalog techniques for calculations of reaction rate measurements at the BFS facilities

Andrianova, Olga Nikolaevna; Manturov, G. N.; Rozhikhin, Yevgenij Valer’evich

doi:10.26583/npe.2016.2.07

Cited by 1 publication

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“…The program of experimental studies based on the BFS-61 assemblies included measuring the ratios of the neutron interaction cross-sections (〈σ f i /〈σ f j ) averaged by the spectrum at a certain point of the critical assembly (spectral indices) containing ample information on the properties of the fast neutron reactor composition under investigation (Andrianova et al 2016, 2017, Andrianova 2017. By definition,…”

Section: Specification Of Benchmark Experiments On the Bfs-61 Assembliesmentioning

confidence: 99%

Consideration of heterogeneous effects in preparing neutron multigroup constants in the CONSYST/BNAB-RF system

Andrianova¹,

Zherdev²,

Lomakov³

et al. 2020

NUCET

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The need for building mutually self-agreed computational models for high-precision and engineering neutronic codes is defined by requirements to certification and verification of software products and nuclear data in accordance with the Regulations for Verification and Expert Examination of Neutronic Calculation Software Tools (RB-061-11). The key requirement in RB-061-11 is that there shall be a methodically transparent and reproducible procedure to estimate the methodological and nuclear data component of the neutronic parameter uncertainties to be implemented only if there are mutually self-agreed computational neutronic models. Using an example of a series of measurements carried out on three critical BFS-61 configurations, factors are discussed which need to be taken into account when building such types of neutronic models and the peculiarities of their application for calculating the neutronic parameters of BFS-61 assemblies. Improved functional capabilities of updated software tools and nuclear data for the computational and experimental analysis of integral BFS experiments (ROSFOND/BNAB-RF, CONSYST and MMK-RF) have been demonstrated, allowing a much shorter time and the smallest risks of errors in preparing mutually self-agreed computational models for various neutronic codes, as well as correct estimation of the methodological and nuclear data components of the uncertainties in neutronic parameters in accordance with RB-061-11. The results of estimating the uncertainty in neutronic parameters with respect to the group approximation approach, are presented. It has been shown based on an analysis of the obtained results that the discrepancies in the calculations of the BFS-61 configurations in the transition from the ROSFOND evaluated neutron data library to its group version, BNAB-RF, does not exceed 0.3% in criticality (heterogeneous effects uncertainty of 0.2 to 0.8 %). The estimated spectral index data biases lie in the limits of the Monte Carlo statistical error. Based on the results of a computational and experimental analysis for the entire set of measurements performed on a series of BFS-61 assemblies, the ROSFOND library is the optimal nuclear data library.

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Section: Specification Of Benchmark Experiments On the Bfs-61 Assembliesmentioning

confidence: 99%

Consideration of heterogeneous effects in preparing neutron multigroup constants in the CONSYST/BNAB-RF system

Andrianova¹,

Zherdev²,

Lomakov³

et al. 2020

NUCET

View full text Add to dashboard Cite

show abstract

Application of MCPN nonanalog techniques for calculations of reaction rate measurements at the BFS facilities

Cited by 1 publication

References 0 publications

Consideration of heterogeneous effects in preparing neutron multigroup constants in the CONSYST/BNAB-RF system

Consideration of heterogeneous effects in preparing neutron multigroup constants in the CONSYST/BNAB-RF system

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