EDN: NPVDUL
Authors & Affiliations
Onegin M.S.1, Popykin A.I.2, Starova N.A.2
1 Petersburg Nuclear Physics Institute named by B.P. Konstantinov of National Research Centre «Kurchatov Institute», Gatchina, Russia
2 Scientific and Engineering Centre for Nuclear and Radiation Safety, Moscow, Russia
Onegin M.S.1 – Senior Researcher, Cand. Sci. (Phys. and Math.).
Petersburg Nuclear Physics Institute named by B.P. Konstantinov of National Research Centre “Kurchatov Institute”;
Popykin A.I.2 – Leading Researcher, Cand. Sci. (Phys. and Math.). Contact: 2/8, bld. 5, Malaya Krasnoselskaya st., Moscow, Russia, 107140. Tel.: +7 (499) 753-05-24; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Starova N.A.2 – Researcher.
Abstract
The safety guides RB-061-11 and RB-166-20 provide recommendations for determining the errors of neutron-physical calculation. This research aims to investigate the role of the impact of neutron cross-section uncertainty on the errors of neutron-physical calculation. The article considers some issues related to the assessment of this component of the error, performed using evaluated neutron data files, including covariance files. The specific recommendations for validation/verification of neutronic codes are discussed here. The scope of the article also included the issue of certifying the following codes: the nuclear data processing codes (NJOY, GRUKON) and codes (code packages) which are used for nuclear data sensitivity analysis. This article addresses attention to an approach to correction of neutron data systems using integral experiments in estimating error due to neutron cross-section uncertainty. This paper provides examples of estimating the impact of neutron cross-section uncertainty on the error of calculation results of the effective neutron multiplication factor for the VVER fuel assembly, the core model of the BREST-OD-300, and for the PIK reactor.
Keywords
error, neutron-physical calculation, ROSFOND, Code, validation, verification, the impact of neutron cross-section uncertainty on the errors
Article Text (PDF, in Russian)
References
- Popykin A.I., Zhylmaganbetov N.M., Smirnova A.A. O trebovaniyakh i rekomendatsiyakh reguliruyushchego organa k opredeleniyu pogreshnosti neytronno-fizicheskogo rascheta [About the Requirements and Recommendations of the Regulatory Body to Error Estimation of Neutronics Calculations]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2019, issue 2, pp. 127–133.
- RB-061-11. Polozheniye o provedenii verifikatsii i ekspertizy programmnykh sredstv po napravleniyu “Neytronno-fizicheskiye raschety” [Statute on verification and examination of codes in the direction of “Neutron-physical calculations”]. Available at: https://docs.secnrs.ru/catalog/RB/RB_061_11/ (accessed 13.05.2024).
- Ignatyuk A.V., Nikolaev M.N., Fursov B.I. Development of an Evaluated Nuclear Database for Modern Technologies. At Energy, 2014, vol. 116, issue 4, pp. 258–264. DOI: https://doi.org/10.1007/s10512-014-9851-y.
- Understanding NJOY. Available at: https://t2.lanl.gov/nis/njoy/ (accessed 10.02.2025).
- GRUCON – evaluated data processing code package. Available at: https://www-nds.iaea.org/grucon/ (accessed 10.02.2025).
- Poryadok provedeniya ekspertizy programm dlya elektronnykh vychislitel'nykh mashin, ispol'zuyemykh v tselyakh postroyeniya raschetnykh modeley protsessov, vliyayushchikh na bezopasnost' ob"yektov ispol'zovaniya atomnoy energii i (ili) vidov deyatel'nosti v oblasti ispol'zovaniya atomnoy energii [The procedure for conducting an examination of programs for electronic computers used for the purpose of constructing computational models of processes affecting the safety of nuclear facilities and (or) activities in the field of nuclear energy use]. Approved by the order of Rostekhnadzor dated 04.04.2023 No. 141, registered in the Ministry of Justice of the Russian Federation on 08.06.2023 No. 73783).]. Available at: https://www.secnrs.ru/emails/2023/Poryadok_prikaz_141.pdf (accessed 10.02.2025).
- MCU-PD s bankom dannykh MDBPD-50 [MCU-PD with the MDBPD-50 data bank]. Software Certification passport No. 456 dated October 24, 2018.
- Mayorov L.V., Yudkevich M.S. Neytronno-fizicheskiye konstanty v raschetakh teplovykh reaktorov [Neutron-physical constants in the calculations of thermal reactors]. Moscow, Energoatomizdat Publ., 1988.
- MCU-RFFI/A s bibliotekoy konstant DLC/MCUDAT-1.0 [MCU-RFFI/A with the DLC/MCUDAT-1.0 constant library]. Software Certification Passport No. 400, registered in OFAP-Yar under No. 388 dated 16.04.1996.
- Eksperimental'nyye issledovaniya uran-vodnykh reshetok tipa VVER [Experimental studies of WWER-type uranium-water lattices]. Sbornik trudov VMK [Proc. of the VMK]. Budapest: Kiado Academy, 1984. Vol. 1–3.
- International Handbook of Evaluated Criticality Safety Benchmark Experiments. OECD, NEA.
- MMKK. Software Certification Passport, No. 314, 2012.
- MMKС. Software Certification Passport, No. 474, 2019.
- MCU-FR s bankom dannyh MDBPD-60 [MCU-FR with MDBPD-60 data bank]. Software Certification Passport, No. 501, 2019.
- Usachev L.N., Bobkov Yu.G. Teoriya vozmushcheniy i planirovaniya eksperimenta v probleme yadernykh dannykh dlya reaktorov [Perturbation theory and experiment planning in the problem of nuclear data for reactors]. Moscow, Atomizdat Publ., 1980. 88 p.
- Manturov G.N. Metodicheskoye konstantnoye i programmnoye obespecheniye neytronno-fizicheskikh raschetov bystrykh reaktorov i otsenka pogreshnostey raschetnykh predskazaniy. Avtoreferat diss. dokt. tekh. nauk [Methodical constants and software for neutron-physical calculations of fast reactors and evaluation of errors in calculated predictions. Abstract of diss. dr. tech. sci.]. Obninsk: IPPE Publ., 2017.
- SCALE 6.2. A Comprehensive Modeling and Simulation Suite for Nuclear Safety. Analysis and Design; Includes ORIGEN and AMPX. RSCC Computer Code Collection. Oak Ridge National Laboratory. CCC-834.
- Broadhead B.L., Rearden B.T., Hopper C.M., Wagschal J.J., Parks C.V. Sensitivity- and Uncertainty-Based Criticality Safety Validation Techniques. Nuclear Science and Engineering, 2004, vol. 146, pp. 340–366.
- Rearden B.T., Williams M.L., Jessee M.A., Mueller D.E., Wiarda D.A. Sensitivity and uncertainty analysis capabilities and data in SCALE. Nuclear technology, 2011, vol. 174, pp. 236–288.
UDC 621.039.51
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 1, 1:9
