EDN: CNHKJI
Authors & Affiliations
Ananyev A.V., Artemov V.G.
Alexandrov NITI, Sosnovy Bor, Russia
Ananyev A.V. – Engineer 3d category. Contacts: 72, Koporskoye shosse, Sosnovy Bor, Leningrad region, Russia, 188540. Tel.: +7 (81369) 6-08-83; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Artemov V.G. – Head of Laboratory, Cand. Sci. (Tech.).
Abstract
The paper presents results of numerical simulation of scram efficiency experiments. The simulation was performed using sensitivity and uncertainty analysis (SUA). The scheme of SUA computations with the KORSAR/GP computer code is described on the example of simulation of experiments performed in a real VVER-1000 power unit. The paper investigates how the simulation results are affected by uncertainties due to the error of control rod efficiency calculation, error of neutron flux density calculation in the core and ion chamber locations, and uncertainty of the values of delayed neutron parameters. The values of reactivity calculation error are obtained as uncertainty tubes from variations of the simulation model parameters. Correlation coefficients for the calculation results and model variables are computed and the most significant uncertainties of the simulation model are determined. The calculation results indicated that the most significant uncertainties are: the error of control rod efficiency, the uncertainty of radial neutron flux density distribution, the uncertainty of relative fractions of the delayed neutron groups, which correspond to the longer-lived precursors.
Keywords
VVER-1000, scram efficiency, sensitivity and uncertainty analysis method, error of reactivity measurement simulation, KORSAR/GP computer code
Article Text (PDF, in Russian)
References
- Kazanskiy Yu.A., Matusevich E.S. Eksperimental’nyye metody fiziki reaktorov [Experimental methods of reactor physics]. Moscow, Energoatomizdat Publ., 1984. 272 p.
- RB-074-12. Polozheniye o rekomendatsiyakh po sopostavleniyu rasschitannoy i izmerennoy reaktivnosti pri obosnovanii yadernoy bezopasnosti reaktornykh ustanovok s VVER [Guidelines for comparing calculated and measured reactivity values in VVER nuclear safety analysis]. Moscow, Federal Environmental, Industrial and Nuclear Supervision Service, 2012.
- NP-001-15. Obshchiye polozheniya obespecheniya bezopasnosti atomnykh stantsiy [General provisions for nuclear power plant safety assurance]. Moscow, Federal Environmental, Industrial and Nuclear Supervision Service, 2016.
- 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 [Procedure for examination of electronic computer programs used to build simulation models of processes related to safety of nuclear facilities and (or) activities]. Moscow, Federal Environmental, Industrial and Nuclear Supervision Service, 2018.
- Bogdan S.N., Kovalevich O.M., Kozlova N.A., Shevchenko S.A., Yashnikov D.A. Ob otsenke pogreshnostey i neopredelennostey raschetov, vypolnyayemykh pri obosnovanii bezopasnosti ob”yektov ispol’zovaniya atomnoy energii [Assessing the errors and uncertainties of calculations carried out in safety analysis of nuclear facilities]. Moscow, M.: FBU “NTTS YARB” Publ., 2017.
- Glaeser H. GRS Method for Uncertainty and Sensitivity Evaluation of Code Results and Applications. Science and Technology of Nuclear Installations, 2008, article ID 798901. DOI: https://dx.doi.org/10.1155/2008/798901.
- RB-166-20. Rekomendatsii po otsenke pogreshnostey i neopredelennostey rezul’tatov raschetnykh analizov bezopasnosti atomnykh stantsiy [Guidelines for evaluation of errors and uncertainties in results of numerical safety analyses of nuclear power plants]. Moscow, Federal Environmental, Industrial and Nuclear Supervision Service, 2020.
- Tsyganov S.V., Shishkov L.K. Measurement of VVER Control Rod Efficiency. Atomic Energy, 2004, vol. 96, issue 3, pp. 159–164. DOI: https://doi.org/10.1023/B:ATEN.0000030916.11152.e6.
- Artemov V.G., Gusev V.I., Zinatullin R.E., Karpov A.S., Kurakin K.Yu., Solov’yev A.A., Belyakov A.Yu. Issledovaniye vliyaniya tochnosti rascheta parametrov zapazdyvayushchikh neytronov na rezul’taty modelirovaniya eksperimentov po opredeleniyu effektivnosti avariynoy zashchity [Analyzing the effect of accuracy of delayed neutron parameter calculations on results of scram worth experiment simulations]. Materialy 5-y Mezhdunarodnoy nauchno-tekhnicheskoy konferentsii “Obespecheniye bezopasnosti AES s VVER” [Proc. of the 5th International Scientific-Technical Conference “Safety Assurance of VVER NPPs”]. Podolsk, 2007. Available at: http://www.gidropress.podolsk.ru/files/proceedings/mntk2007/disc/documents/f76.pdf (accessed 16.04.2023).
- Pinegin A.A., Shumskiy B.E. Eksperimental’nyye pogreshnosti i vozmozhnost’ ikh kompensatsii pri opredelenii effektivnosti avariynoy zashchity i differentsial’noy effektivnosti gruppy OR SUZ v reaktore VVER-1000 [Experimental errors and possibility of their compensation in assessment of scram worth and differential efficiency of control rod group in VVER-1000 reactor]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Nuclear Reactor Physics, 2007, issue 1, pp. 76–89.
- Kulikov V.I., Semenova T.V., Zhylmaganbetov N.M., Popykin A.I., Smirnova A.A. Sravneniye koeffitsiyentov vliyaniya dlya raschetov tokov ionizatsionnykh kamer dlya reaktora RU V-392M VVER-1200), rasschitannykh razlichnymi sposobami [Comparison of influence coefficients for calculations of ion chamber currents in V-392M reactor (VVER-1200) computed with different methods]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2019, issue 3, pp. 62–70. DOI: https://dx.doi.org/10.55176/2414-1038-2019-3-62-70.
- Artemov V.G., Zinatullin R.E., Karpov A.S., Piskarev A.V., Shemayev Yu.P. Podgotovka i obosnovaniye parametrov zapazdyvayushchikh neytronov v komplekse programm SAPFIR-KORSAR [Preparation and validation of delayed neutrons parameters in SAPFIR-KORSAR program package]. Tekhnologii obespecheniya zhiznennogo tsikla yadernykh energeticheskikh ustanovok [Nuclear propulsion reactor plants. Life cycle management technologies], 2016, no. 1(3), pp. 38–54.
- Zabrodskaya S.V., Nikolayev M.N., Tsibulya A.M. Dannyye po zapazdyvayushchim neytronam v sisteme konstantnogo obespecheniya BNAB-93 [Delayed neutron data in BNAB-93 system of constants]. Voprosy atomnoy nauki i tekhniki. Seriya: Yadernyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear constants, 1998, issue 1.
- Abagyan L.P., Bazazyants N.O., Nikolayev M.N., Tsibulya A.M. Gruppovyye konstanty dlya rascheta reaktorov i zashchity [Neutron group constants for reactors and shielding calculations]. Moscow, Energoizdat Publ., 1981. 23 p.
- Keepin G. Robert. Physics of Nuclear Kinetics . Мoscow, Atomizdat Publ., 1967. 428 p.
UDC 621.039.51
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 2, 2:2