Authors & Affiliations
Belousov V.I., Gomin E.A., Davidenko V.D., Dyachkov I.I., Ioannisian M.V., Malkov M.R., Rozikhin E.V., Chernov K.G.
National research center “Kurchatov institute”, Moscow, Russia
Ioannisian M.V. – Head of Laboratory, Cand. Sci. (Phys.-Math.). Contacts: 1, Akademika Kurchatova pl., Moscow, Russia, 123182. Tel.:+7 (968) 388-28-22; e-mail:
Belousov V.I. – Head of Laboratory, Cand. Sci. (Phys.-Math.).
Gomin E.A. – Senior Researcher.
Davidenko V.D. – Director of Department, Dr. Sci. (Tech.).
Dyachkov I.I. – Junior Researcher.
Malkov M.R. – Senior Researcher, Cand. Sci. (Phys.-Math.).
Rozikhin E.V. – Senior Researcher.
Chernov K.G. – Senior Research.
Abstract
A method for taking into account the temperature dependence of the cross sections of materials for solving the problem of neutron transport using the KIR2 program using the Monte Carlo method is considered. Reconstruction of nuclide cross section temperature dependence in resonance energy region is carried out on the basis of a polynomial regression model for the square root of temperature. The model allows to approximate the temperature dependence of cross sections with polynomials in the energy region of resonances and the thermal region, provided that the ideal gas model is applied. The calculation of cross sections at a given temperature is carried out directly during the simulation of neutron transport by the KIR2 program. The use of the model allows to reduce the amount of computer RAM that is used by the data storage program to determine cross sections.
The polynomial coefficients are pre-calculated based on the developed ISOP code using ACE nuclide files and written to the polynomial coefficient library (PCL). The program calculated an OPF for 422 nuclides with using of ENDF/B VII.1 nuclear data.
The resulting PCL was verified on a test task and a series of benchmark experiments from the ICSBEP handbook. The calculation results were compared using the PCL, the temperature-proportional concentration method and based on the direct use of nuclear data files for a given temperature. It has been shown that the application of the polynomial regression model practically does not give differences in the results obtained with nuclear data files.
Keywords
neutron transport, KIR2 program, Monte Carlo method, neutron physics module, arbitrary temperature, modeling of stationary and transient processes, ACE format, libraries of polynomial coefficients
Article Text (PDF, in Russian)
UDC 621.039.51.17
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 1, 1:5