Authors & Affiliations

Koscheev V.N., Peregudov A.A., Rozikhin E.V., Semenov M.Yu., Yakunin A.A.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia

Koscheev V.N. – Leading Research, Cand. Sci. (Phys.-Math.), A.I. Leypunsky Institute for Physics and Power Engineering. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-51-54; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Peregudov A.A. – Deputy head of laboratory, Cand. Sci. (Techn.), A.I. Leypunsky Institute for Physics and Power Engineering.
Rozikhin E.V. – Senior Research, A.I. Leypunsky Institute for Physics and Power Engineering.
Semenov M.Yu. – Leading Research, Cand. Sci. (Phys.-Math.), A.I. Leypunsky Institute for Physics and Power Engineering.
Yakunin A.A. – Researcher, A.I. Leypunsky Institute for Physics and Power Engineering.

Abstract

In the practice of calculating the neutron-physical characteristics of fast reactors, codes are used that utilize various calculation methods, both engineering (implementing a group approach) and precision (using detailed modeling). The prepared library of constants is verified and then recommended for use in computational studies. A change in the temperature mode for a computational model often leads to the need to modify the nuclear data library, which must then be verified under new temperature conditions.
In this work, we used the technique of temperature-proportional concentrations, with the help of which it is possible to avoid additional efforts to create nuclear data at new values of working temperatures.
Four test models of large fast reactors are considered, which are representative enough to justify the reliability of the findings of the work performed.
Calculations of the criticality of test models were performed with the MMKC code. Based on the ROSFOND-2010 library, nuclear data for calculations were prepared in two different ways. The first was using the NJOY code to directly prepare nuclear data in the ACE format for operating temperatures. The second method included the preparation of CE nuclear data in the ACE format at 6 “reference” values of temperatures, and further, for operating temperatures, the nuclear data were simulated using a temperature-proportional concentration technique.
The results of the criticality and the Doppler Effect calculations are given. Differences of calculated values are analyzed depending on the method of nuclear data preparation.

Keywords
neutron-physical calculation of fast reactor, ROSFOND-2010 library, preparation of nuclear data, code NJOY, ACE format, nuclear data modeling for arbitrary temperature, temperature-proportional concentration method, test models of fast reactors, code MMKC, Doppler effect

Article Text (PDF, in Russian)

References

UDC 004.94:681.3.06

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2019, issue 2, 2:7