IMPLEMENTATION OF THE POSSIBILITIES THE RADIATION ENERGY RELEASE CALCULATING IN THE MCU-PTR PROGRAM USING KERMA FACTORS

Authors & Affiliations

Bikeev A.S., Kalugin M.A., Kuznetcov A.N., Shkarovsky D.A.
National Research Centre "Kurchatov Institute", Moscow, Russia

Bikeev A.S. – Head of Software Laboratory, National Research Center "Kurchatov Institute".
Kalugin M.A. – Scientific Director of the Kurchatov Nuclear Power Complex, Dr. Sci. (Tech.), National Research Center "Kurchatov Institute".
Kuznetcov A.N. – Engineer, National Research Center "Kurchatov Institute". Contacts: 1, Akademika Kurchatova pl., Moscow, Russia, 123182. Tel: +7(499) 196-92-76; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Shkarovsky D.A. – Head of the Division of Benchmark Calculations of Nuclear Reactors, Cand. Sci. (Phys. and Math.), National Research Center "Kurchatov Institute".

Abstract

The paper describes the realization of the the radiation energy release calculating possibility in structural materials using the precision Verified MCU Monte Carlo code using KERMA factors. It is shown that for this calculation of energy release, the MCU-PTR program uses the submodule of the DOSIM registration module included in it, which works with the activation cross sections of neutrons and photons.In the case of using KERMA factors, all calculations are performed in the same way as usual, with the only difference being that instead of the activation cross sections, the cross sections of the radiation energy release are substituted into the desired functional. Thus, for calculation it is nec-essary to copy the files of the kerma factor library for neutrons and photons to the DOSIM folder, and then use their names in the standard way when specifying the source data for the registration module.
Using the NJOY code and the ENDF-B/VII.1 library, the KERMA library has been developed, which contains 422 files for neutrons and 100 for photons. Data libraries are contained in two formats - for calculation and visualization. To test both received KERMA-factors, and the approach to modernization, an infinite lattice of two-dimensional fuel cells is considered. It is assumed that the cladding of a fuel element is isotope, for which the quality of the calculation of radiation heating from neutrons and photons is checked by comparing the results of the calculation with the programs MCU-PTR and MCNP5. The discrepancy between the calculated energy releases reaches 21% in some cases. In addition, neutron and photon fluxes also differ – that is, in addition to the error related to the quality of KERMA factors, contribution is made by errors which are associated with libraries used to model the transport of neutrons and photons and used for the production of photons in neutron reactions, and also are associated with the difference in the ways of modeling these processes.

Keywords
KERMA factors, energy release, MCU-PTR, Monte-Carlo, Nuclear Data Libraries, KERMA, MCNP5, infinite lattice of fuel assemblies, neutrons, photons

Article Text (PDF, in Russian)

References

UDC 621.039.17

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2018, issue 4, 4:2