Izvestiya vuzov. Yadernaya Energetika

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

Generating a System of Group Constants for Neutron-Physical Calculations of Fast Reactors Based on ROSFOND-2020.2 Library Files

6/05/2024 2024 - #02 Modelling processes at nuclear facilities

Averchenkova E.P. Dyachenko Y.V. Zabrodskaia S.V. Mishin V.A. Panova D.V. Peregudov A.A. Semenov M.Yu. Tormyshev I.V. Lyapin E.P.

DOI: https://doi.org/10.26583/npe.2024.2.13

UDC: 539.172.4

The subject of constant support development is currently becoming increasingly important in connection with the national strategy of transition to a closed nuclear fuel cycle. At the same time, the importance of the tasks of refining calculation models and minimizing methodological, statistical, and constant errors is increasing. In this connection, the idea of creating a universal system of constants describing with equal accuracy both uranium loading and loading with mixed oxide uranium-plutonium fuel and the possibility to perform on its basis both precision Monte Carlo calculations (data format – ACE) and multigroup calculations (formats – BNAB and ANISN) was laid in the basis of this work.

In this paper we analyze the freely available libraries of evaluated nuclear data in order to justify the choice of source files for the formation of a new system of group constants for neutron-physical calculations of fast reactor cores, describe the process of formation of a new library of reactor constants, and verify the obtained system on computational test models of BN-800 reactor and critical systems.

The process of formation of the new system of group constants included selection of initial neutron data files, updating of data tables of basic neutron cross-sections, self-shielding factors and Doppler coefficients, as well as data on fission spectra for the main fuel nuclides.

The methodological component of the error for test models of the BN-800 core was evaluated. Using the BNAB-RF22 system of group constants it was possible to estimate the correction in the 299 groups calculation, which amounted to 0,3%. Previously, when using the BNAB-93 library, there was no such possibility due to the lack of continuity between the files of evaluated neutron data and the group constants used.

References

  1. Yaroslavtseva L.N. JAR program complex for calculation of neutron-physical characteristics of nuclear reactors. Voprosy atomnoy nauki i tekhniki. Series: Physics and Technology of Nuclear Reactors. 1983, no. 8 (37), pp. 41 – 43 (in Russian).
  2. Belov A.A., Seleznev E.F. Calculated support of BN-600 reactor operation. Computational tracking of BN-600 operation. Atomic Energy. 2010, vol. 108, no. 4, pp. 321 – 324 DOI: https://doi.org/10.1007/ s10512-010-9296-x
  3. Asatryan D.S., Belov A.A., Belousov V.I., Bereznev V.P., Ivchenko D.V., Seleznev E.F., Chernova I.S., Koscheev V.N., Manturov G.N., Peregudov A.A., Semenov M.Yu., Tsibulya A.M., Drobyshev Yu.Yu., Karpov S.A., Fedorov I.V. GEFEST800 Software Complex for Performing Real-Time Neutron-Physical Calculations of the BN-800 Reactor in a Stationary Regime. Atomic Energy. 2015, vol. 118, pp. 375 – 381. https:// doi.org/10.1007/s10512-015-0011-9
  4. Seregin A.S., Kislitsyna T.S. Abstract of the TRIGEX-CONSYST-BNAB-90 program complex. Preprint IPPE-2655. Obninsk, IPPE Publ., 1997 (in Russian).
  5. Expert Council for certification of NTC NRS software tools. Attestation passport of the software tool «FACT BR» (version 1.1), no. 433 dated 27.02.2018 Available at: https://www.secnrs.ru/expertise/software-review/База_аттестационных_паспортов_июнь_2023.pdf (accessed Mar. 14, 2024) (in Russian).
  6. Alcouffe R.E., Brinkley F.W., Marr D.R, O’Dell R.D. User’s guide for TWODANT: a code package for two-dimentional, diffusion-accelerated, neutral-particle transport. Los Alamos National Laboratory, Report LA-1049-M, Rev. 1, 1984. DOI: https://doi.org/10.2172/5985401
  7. Expert Council for certification of NTC NRS software tools. Attestation passport of the computer program KATRIN-2.5, no. 357 dated 17.04.2014. Available at: https://www.secnrs.ru/expertise/software-review/ База_аттестационных_паспортов_июнь_2023.pdf (accessed Mar. 14, 2024) (in Russian).
  8. Expert Council for certification of NTC NRS software tools. Attestation passport of the computer program CASCADE-3.0, no. 460 dated 30.05.2019. Available at: https://www.secnrs.ru/expertise/software-review/ База_аттестационных_паспортов_июнь_2023.pdf (accessed Mar. 14, 2024) (in Russian).
  9. MCNP – A General Monte Carlo N-Particle Transport Code, Version 5. Volume I: Overview and Theory. Los Alamos National Laboratory. LA-UR-03-1987, 2003. Available at: https://image.sciencenet.cn/olddata/kexue.com.cn/upload/blog/file/2009/8/2009891015 23420494.PDF (accessed Mar. 14, 2024).
  10. Blyskavka A.A., Manturov G.N., Nikolaev M.N., Tsibulya A.M. Program Complex CONSYST/ММККENO for Calculation of Nuclear Reactors by Monte Carlo Method in Multigroup Approximation with Scattering Indicatrices in Rp Approximation. IPPE Preprint-2887. Obninsk, IPPE Publ., 2001, 27 p. (in Russian).
  11. Expert Council for certification of NTC NRS software. Certification passport of MCU-FR computer program with MDBFR60 data bank no. 501 dated 14.12.2020. Available at: https://www.secnrs.ru/expertise/ software-review/База_аттестационных_паспортов_июнь_2023.pdf (accessed Mar. 14, 2024) (in Russian).
  12. Manturov G.N., Nikolaev M.N., Tsibulya A.M. CONSYST code for neutron constants preparation. Scope statement. Preprint IPPE-2828. Obninsk, IPPE Publ., 2000, 72 p. (in Russian).
  13. Manturov G.N., Nikolaev M.N., Tsibulya A.M. System of group constants BNAB-93. Part 1. Nuclear constants for calculation of neutron and photon radiation fields. Voprosy atomnoy nauki i tekhniki. Series: Nuclear Constants. 1996, vol. 1, pp. 59–98.
  14. Certificate of registration of the BNAB-93 database no. 2014620091 dated 15.01.2014. Available at: https://www.ippe.ru/images/oyarit/reactor-constants-datacenter/opis/abbn-93.pdf (accessed Mar. 14, 2024) (in Russian).
  15. Chadwick M.B., Herman M., Oblozinsky. P., Dunn M.E., Danon Y., Kahler A.C., Smith D.L., Pritychenko B., Arbanas G. et al. ENDF/B-VII.1 Nuclear data for science and technology: cross sections, covariances, fission product yields and decay data. Nuclear Data Sheets. 2011, vol. 112, iss. 12, pp. 2887 – 2996. DOI: https://doi.org/10.1016/j.nds.2011.11.002
  16. Brown D.A., Chadwick M.B., Capote R., Kahler A.C., Trkov A., Herman M., Sonzoghi A.A., Danon Y., Carlson A.D., Dunn M. et al. ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standarts and Termal Scattering Data. Nuclear Data Sheets. 2018, vol. 148, pp. 1 – 142. DOI: https://doi.org/10.1016/j.nds.2018.02.001
  17. The JEFF-3.3.1 Nuclear Data Library, NEA Nuclear Data Services, 2018. Available at: https://www. oecd-nea.org/dbdata/jeff/jeff33/ (accessed Mar. 14, 2024).
  18. Shibata K. Iwamoto O., Nakagawa T., Ichihara A., Kunieda S., Chiba S., Furutaka K., Otuka N., Ohsawa T., Murata T. et al. JENDL-4.0: A New Library for Nuclear Science and Engineering. Journal of Nuclear Science and Technology. 2011, vol. 48, iss. 1, pp. 1 – 30. DOI: https://doi.org/10.3327/jnst.48.1
  19. Zabrodskaya S.V., Ignatyuk A.V., Koscheev V.N. Manokhin V.N., Nikolaev M.N., Pronyaev V.G. ROSFOND – Russian National Library of Evaluated Neutron Data. Voprosy atomnoy nauki i tekhniki. Series: Nuclear Constants. 2007, no. 1 – 2, pp. 3 – 21. Available at: https://vant.ippe.ru/images/pdf/2007/1.pdf (accessed Mar. 14, 2024) (in Russian).
  20. Manturov G.N., Zabrodskaya S.V., Zuikov A.A., Levchenko Y.V., Melega N.A., Mishin V.A., Panova D.V., Peregudov A.A., Peregudova O.O., Semyonov M.Yu. Development status of the nuclear constants databases for fast reactor calculations on the basis of ROSFOND and BNAB-RF. Voprosy atomnoy nauki i tekhniki. Series: Nuclear Reactor Constants. 2022, no. 3, pp. 19–26. Available at: https://vant.ippe.ru/ images/pdf/2022/issue2022-3-19-26.pdf (accessed Mar. 14, 2024) (in Russian).
  21. Chadwick M., Capote R., Trkov A., Herman M., Brown D., Hale G.M., Kahler A.C., Talou P., Plompen A., Schillebeeckx P. et al. CIELO collaboration summary results: international valuations of neutron reactions on uranium, plutonium, iron, oxygen and hydrogen. Nuclear Data Sheets. 2018, vol. 148, pp. 189 – 213. DOI: https://doi.org/10.1016/j.nds.2018.02.003
  22. International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC(95)/03. Paris, 2016.
  23. Peregudov A.A., Kryachko M.V., Koscheev V.N., Maslov P.A., Tormyshev I.V., Semyonov M.Yu.1, Kuntsio G.A., Gurskaya O.S., Ivanov A.A., Erpalov P.A. BNcode – Advanced Code for Scientific Support of Operating BN Reactors. Voprosy atomnoy nauki i tekhniki. Series: Nuclear Reactor Constants. 2019, no 2, pp. 2 – 8. DOI: https://doi.org/10.55176/2414-1038-2019-2-77-86 (in Russian).
  24. MacFarlane R.E., Muir D.W., Boicourt R.M., Kahler A.C., Conlin J.L., Haeck W., The NJOY Nuclear Data Processing System. Version 2016. Volume I: User’s Manual, LA.-UR-17-20093, Los Alamos National Laboratory, 2019. Available at: https://www.njoy21.io/ (accessed Mar. 15, 2024).
  25. Herman M., Trkov A. ENDF-6 Formats Manual. Report BNL-90365-2009 (ENDF-102) Rev. 1, National Nuclear Data Center Brookhaven National Laboratory, 2010. Available at: https://www.oecd-nea.org/dbdata/data/manual-endf/endf102.pdf (accessed Mar. 15, 2024).
  26. Peregudov A.A., Koshcheev V.N., Manturov G.N. Methodology for obtaining neutron group constants for materials – mixtures of isotopes in the BNAB system. Izvestia Vysshikh Uchebnykh Zawedeniy. Yadernaya Energetika. 2011, no. 2. pp. 43 – 50. Available at: https://static.nuclear-power-engineering.ru/journals/2011/02.pdf (accessed Mar. 15, 2024).(in Russian).
  27. Expert Council on certification of program means of STC NRS. Attestation passport of MMKC com- puter program no. 474 dated 20.11.2019. Available at: https://www.secnrs.ru/expertise/software-review/ База_аттестационных_паспортов_июнь_2023.pdf (accessed Mar. 14, 2024) (in Russian).

BN-800 ROSFOND-2020.2 evaluated neutron data constant error group constants mixed oxide uranium-plutonium fue

Link for citing the article: Averchenkova E.P., Dyachenko Y.V., Zabrodskaia S.V., Mishin V.A., Panova D.V., Peregudov A.A., Semenov M.Yu., Tormyshev I.V., Lyapin E.P. Generating a System of Group Constants for Neutron-Physical Calculations of Fast Reactors Based on ROSFOND-2020.2 Library Files. Izvestiya vuzov. Yadernaya Energetika. 2024, no. 2, pp. 155-169; DOI: https://doi.org/10.26583/npe.2024.2.13 (in Russian).