EDN: CIPNZC
Authors & Affiliations
Artemov V.G., Nersesian N.S.
Alexandrov Research Institute of Technoloqy, Sosnovy Bor, Russia
Nersesian N.S. – Researcher. 11/2 Krasnye Forts str., Leningrad Region, Sosnovy Bor, Russia, 188540, Тел.: +7 (813) 696-08-83; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Artemov V.G. – Head of the Laboratory, Cand. Sci. (Tech.)
Abstract
The paper presents results of simulation of experiments for evaluating the control rod worth using a neutronic model in the SAPFIR_RF&RC program package. The experiments were performed in a criticality facility with a small gas-cooled fast reactor core at FSUE “Alexandrov NITI”. Reactivity in experiments with insertion and withdrawal of rods was measured by an inverse solution of kinetics equation. A numerical analysis was performed to evaluate how a constant neutron source, positions of ex-core detectors with respect to perturbation, and parameters of delayed neutrons used in a reactivity meter would influence the reactivity measurements. The analysis results are reported. The numerical analysis was carried out using a 3D unsteady-state model with simulation of experiment conditions. The purpose of experiment simulations was to verify the simulation model and determine how the methodology of reactivity measurements by the inverse kinetic method would influence the results of control rod worth evaluation. The analysis has determined that the accuracy of experiment measurement simulations depends very much on the choice of a library (ENDF/B-V, VI, VII, ROSFOND, BNAB-78) for delayed neutron parameters. The best agreement with experiment is obtained using delayed neutron parameters from files in ROSFOND and BNAB-78 data banks. The uncertainty of measurement results depends on a constant neutron source and delayed neutron parameters as set in a reactivity meter. Since the reactor of interest is small, the spatial effects are negligible.
Keywords
gas-cooled fast reactor, core, critical assembly facility, measurement of reactivity, inverse kinetics approach, delayed neutrons parameters, spatial effects, neutron source, simulation of experiments, SAPFIR_RF&RC program package
Article Text (PDF, in Russian)
References
1. Kazansky Yu.A., Matusevich E.S. Eksperimental’nyye metody fiziki reaktorov: Ucheb. posobie dlya vuzov [Experimental methods of reactor physics: Textbook for universities]. Moscow, Energoatomizdat Publ., 1984. 272 p.
2. Kazansky Yu.A., Matveenko I.P., Tyutyunnikov P.L., Shokodko A.G. K uchetu prostranstvennyykh effektov pri izmerenii reaktivnosti metodom obrashennovo reshenia uravnenia kinetiki [To account for spatial effects when measuring reactivity by inverse kinetics approach]. Atomic Energy, 1981, vol. 51, issue 6, pp. 387–389.
3. Tsyganov S.V., Shishkov L.K. Izmereniya effektivnosti organov regulirovaniya VVER [Measurements of the WWER control rods effectiveness]. Atomic Energy, vol. 96, issue 3, 2004.
4. Pinegin A.A., Shumsky B.E. Eksperimental’nyye pogreshnosti i vozmozhnost’ ikh kompensasii pri opredelenii effektivnosti avariynoy zashity i differensial’noy effektivnosti gruppy OR SUZ v reaktore VVER-1000 [Experimental Errors and Possibility of their Compensation when Evaluating Emergency Protection Efficiency and Differential Efficiency of Control Rod Group in WWER-1000 Reactor]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics of Nuclear Reactors, 2007, issue 1, pp. 76–89.
5. Artemov V.G., Gusev V.I., Zinatullin R.E., Karpov A.S., Kurakin K.Y., Solovyov A.A., Belyakov A.Y. Issledovanie vliyaniya tochnosti rascheta parametrov zapazdyvaushikh neytronov na rezultaty modelirovaniya eksperimentov po opredeleniu effektivnosti avariynoy zashity VVER [Investigation of the influence of the calculation accuracy for delayed neutrons parameters on the results of modeling experiments to determine the effectiveness of emergency protection of WWER]. Proc. of the 5th Int. Sci. and Tech. Conf. “Ensuring the safety of NPPs with WWER reactors”. Podolsk, May 29–June 1, 2007. Available at: http://www.gidropress.podolsk.ru/files/proceedings/mntk2007/disc/autorun/article76-ru.htm (accessed 19.08.2022).
6. Gagarinsky A.Yu., Tsygankov L.S. O vliyanii neopredellennosti yadernykh dannykh na rezultaty obrabotki kineticheskikh izmereniy v reaktorakh s 235U na teplovykh neytronakh [On the influence of nuclear data uncertainty on the results of kinetic measurements processing in thermal reactors with 235U]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics of Nuclear Reactors, 1984, issue 9 (46), pp. 65–69.
7. Artemov V.G., Ivanov A.S., Mikheev P.A., Nersesian N.S. Podgotovka i verifikasiya modeli dlya rascheta neytronno-fizicheskikh kharakteristik aktivnykh zon reaktorov s bystrym spektrom neytronov i gazovym teplonositelem [Preparation and verification of a model for calculating the neutronic characteristics of reactor cores with fast neutron spectrum and gas coolant]. Nauchno-tekhnicheskiy sbornik “Tekhnologii obespecheniya zhiznennogo tsikla yadernykh energeticheskikh ustanovok” – Collection of papers “Nuclear propulsion reactor plants. Life cycle management technologies”, 2020, no. 1 (19), pp. 29–39.
8. Keepin G.R. Fizicheskie osnovy kinetiki yadernykh reaktorov [Physics of nuclear kinetics]. Moscow, Atomizdat Publ., 1967. 431 p.
9. Abagyan L.P., Bazazyants N.O., Nikolaev M.N., Tsybulya A.M. Ed. by M.N. Nikolaev. Gruppovyye konstanty dlya rascheta reaktorov i zashity [Group constants for calculating reactors and protection: Handbook]. Moscow, Energoizdat Publ., 1981. 232 p.
10. Artemov V.G., Zinatullin R.E., Karpov A.S., Piskarev A.V., Shemaev Yu.P. Podgotovka i obosnovanie parametrov zapazdyvaushikh neytronov v komplekse programm SAPFIR/KORSAR [Preparation and validation of delayed neutrons parameters in SAPFIR/KORSAR program package]. Nauchno-tekhnicheskiy sbornik “Tekhnologii obespecheniya zhiznennogo tsikla yadernykh energeticheskikh ustanovok” – Collection of papers “Nuclear propulsion reactor plants. Life cycle management technologies”, 2016, no. 1 (3), pp. 38–54.
UDC 621.039.51:006.91
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2022, no. 3, 3:5