Testing covariance matrices of uncertainties in the BNAB data system

Andrianova, Olga Nikolaevna; Golovko, Yury Evgen’evich; Jerdev, Gennady Mikhailovich; Zadornov, Dmitry Vital’evich; Koscheev, Vladimir Nikolaevich; Manturov, G. N.; Peregudov, A; Tsiboulya, Anatoly Makarovich

doi:10.26583/npe.2014.2.12

Cited by 2 publications

(1 citation statement)

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“…Leipunsky" on verification of the ROSFOND/ABBN-RF nuclear data (Zabrodskaya et al 2007, Andrianova et al 2012 and validation of the software and methodological base of the INDECS system of codes and data archives (Manturov 2017, Manturov et al 2017). The INDECS system includes the covariance neutron cross-sections data from ABBN (Andrianova et al 2014) and the statistical analysis program of calculational-experimental results, which make it possible to quantify both the a priori (due to the existing errors in the nuclear data) and a posteriori (based on the information from the archives of experimental data) errors in the calculated k eff values.…”

Section: Introductionmentioning

confidence: 99%

Verification of the ROSFOND/ABBN nuclear data based on the OECD/NEA benchmark on criticality safety of mox-fueled systems

Andrianova

Golovko²,

Manturov

2019

NUCET

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The paper presents the results of a computational analysis of the OECD/NEA benchmark conducted to estimate the accuracy of the critical safety parameters of multiplying MOX-fueled systems. The computational test is a set of 15 spherical multiplying systems that differ in their compositions and geometries. According to the test conditions, the keff values of the analyzed systems are unknown in advance. As part of the computational analysis of the test involving national codes and nuclear data libraries, along with the keff calculations, it is also necessary to estimate the a priori (due to the accuracy of the nuclear data used) and a posteriori (based on the accumulated experimental information) errors in the calculated keff values. Based on the benchmark, an updated version of the ROSFOND/ABBN-RF nuclear data was tested. The results of estimating the a priori and a posteriori errors in keff using the INDECS system for the proposed test models are presented. The analysis of the calculated data shows that (1) the observed spread in the keff values obtained from the Russian ROSFOND library and foreign evaluated nuclear data libraries (ENDF/B-VII.0, JEFF-3.2, JENDL-4.0) varies from –0.3 up to 0.8%; and (2) the deviation of the calculation results in the keff values obtained from the ROSFOND library and its group version, ABBN-RF, does not exceed 0.1%. The average a priori error in keff for all the tested options of multiplying systems is about 1% and, taking into account the selected set of experimental criticality data for MOX-fueled systems, including experiments at the BFS facilities, the average a posteriori error in keff can be reduced to 0.3%. The performed estimations confirm the high accuracy of the ROSFOND/ABBN-RF nuclear data for calculating the critical safety parameters of multiplying MOX-fueled systems.

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Section: Introductionmentioning

confidence: 99%

Verification of the ROSFOND/ABBN nuclear data based on the OECD/NEA benchmark on criticality safety of mox-fueled systems

Andrianova

Golovko²,

Manturov

2019

NUCET

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Nuclear data uncertainty on generation IV fast reactors criticality calculations analysis comparison

Chereshkov,

Ternovykh,

Tikhomirov

et al. 2023

NUCET

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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 different 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 with three fuel types (UO2, MOX, MNUP), the multiplication factor uncertainty calculations are performed using 252-group covariance matrices based on ENDF/B-VII.1 library via the SCALE 6.2.4 code system. The main nuclear data uncertainty contributors 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 in the question about reliability of the simulation results and requires a comprehensive initial data uncertainty analysis for the neutron transport simulation. The obtained results support the idea that lead- and sodium-cooled reactors have close nuclear data sensitivity using one and the same computation tools, nuclear data libraries and fuel compositions. This makes it possible to use the accumulated data of benchmarks for sodium-cooled reactors in the safety determination of lead-cooled reactors.

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Testing covariance matrices of uncertainties in the BNAB data system

Abstract: И з в е с т и я в у з о в • Я д е р н а я э н е р г е т и к а • № 2 • 2 0 1 4 109

Cited by 2 publications

References 1 publication

Verification of the ROSFOND/ABBN nuclear data based on the OECD/NEA benchmark on criticality safety of mox-fueled systems

Verification of the ROSFOND/ABBN nuclear data based on the OECD/NEA benchmark on criticality safety of mox-fueled systems

Nuclear data uncertainty on generation IV fast reactors criticality calculations analysis comparison

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Testing covariance matrices of uncertainties in the BNAB data system

Abstract: И з в е с т и я в у з о в • Я д е р н а я э н е р г е т и к а • № 2 • 2 0 1 4 109

Cited by 2 publications

References 1 publication

Verification of the ROSFOND/ABBN nuclear data based on the OECD/NEA benchmark on criticality safety of mox-fueled systems

Verification of the ROSFOND/ABBN nuclear data based on the OECD/NEA benchmark on criticality safety of mox-fueled systems

﻿Nuclear data uncertainty on generation IV fast reactors criticality calculations analysis comparison

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Nuclear data uncertainty on generation IV fast reactors criticality calculations analysis comparison