PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY
Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

EVALUATION OF REACTIVITY CALCULATION ERROR USING SENSITIVITY AND UNCERTAINTY ANALYSIS METHOD IN VERIFICATION OF TRANSIENT NEUTRONIC CODES

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

UDC 621.039.51

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 2, 2:2