EDN: GWTOQP
Authors & Affiliations
Pastukhova P.V., Zarapina E.M., Mishin V.A., Peregudov A.A., Semenov M.Yu.
A.I. Leipunsky Institute of Physics and Power Engineering, Obninsk, Russia
Pastukhova P.V. – Research Engineer. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-70-00 (add. 50-53); e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Zarapina E.M. – Junior Researcher.
Mishin V.A. – Researcher.
Peregudov A.A. – Head of Department of Calculated Research of NPP Safety, Cand. Sci. (Tech.).
Semenov M.Yu. – Leading Researcher, Cand. Sci. (Phys.-Math.).
Abstract
Computational research in the field of fast reactors is based on the use of diffusion and precision codes. The accuracy of these specifications calculations is a significant element in confirming the reliable operation of the reactor facility.
Due to the rapid development of computing technology and the increasing introduction of calculation codes into practice, the methodological component of the calculated uncertainty is significantly reduced, therefore, the results of calculations using these codes are accompanied by an estimated of all the components of uncertainties.
Currently, the methodology implemented in the TRIUM code is being developed to evaluate the constant, technological and methodological uncertainties of calculations. The technique is based on the repeated drawing of random sets of input data for the calculation of the physical characteristics of the reactor model (nuclear constants and geometric and material parameters of the model) using the appropriate covariance uncertainty matrices (model parameters and group constants).
The purpose of this article is to evaluate the methodological component of the uncertainty of calculating the neutron-physical characteristics, considering heterogeneity, corrections for the diffusion approximation and instability. The calculations were carried out for several microcamps microcampaigns, for which simplified models were formed, in accordance with the stages of changing the cores of the BN-600 and BN-800.
It should be noted that today the program codes with BNAB-93 constants have been verified and certified for calculations of BN fast reactors: TRIGEX, GEFEST, JAR-FR, CARE, MMKK and MCNP.
The article presents the results of calculations obtained using an engineering program and a precision code for the following values: criticality, efficiency of control systems, and energy release. The calculations were performed using the MMKKENO and TRIGEX programs (using the CONSYST/BNAB-93 constant preparation system).
Keywords
methodological component of uncertainty, neutron-physical characteristics, Monte Carlo method, BN-600, BN-800, criticality, efficiency of control rods, energy release, MOX fuel, EK-164, SP TRIGEX, SP TRIUM
Article Text (PDF, in Russian)
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UDC 621.039.58
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2026, no. 1, 1:9
