Izvestia Vysshikh Uchebnykh Zawedeniy. Yadernaya Energetika

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

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

9/20/2018 2018 - #03 Global safety, reliability and diagnostics of nuclear power installations

Andrianova O.N. Golovko Yu. E. Manturov G.N.

DOI: https://doi.org/10.26583/npe.2018.3.14

UDC: 621.039.51.17

The paper presents the results of a computational analysis of the benchmark OECD/NEA test to assess the accuracy of critical safety parameters of multiplying MOX-fueled systems. The computational test is a set of 15 spherical multiplying systems that differ in composition and geometry characteristics. 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, using national codes and nuclear data libraries, along with the calculation of keff, it is also necessary to estimate the a priori (due to the accuracy of the nuclear data used) and a posteriori (taking into account the accumulated experimental information) keff calculation errors. Based on the benchmark test, 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 INDEX system for the proposed test models, are presented. The analysis of the calculation data shows that (1) the observed spread in the keff values obtained using 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 by the ROSFOND library and its group version, ABBN-RF, does not exceed 0.1%. The average a priori uncertainty in keff for all the tested variants 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 uncertainties in keff can be reduced to 0.3%. The performed evaluations confirm the high accuracy of the ROSFOND/ABBN nuclear data for calculating the critical safety parameters of multiplying MOX-fueled systems

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MOX fuel integral experiments BFS critical facility accuracy evaluation effective multiplication factor constant error OECD/NEA test maximum likelihood method