Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

DOI: 10.55176/2414-1038-2020-4-16-25

Authors & Affiliations

Koscheev V.N., Tormischev I.V., Mischin V.A., Peregudov A.A., Raskach K.F., Semenov M.Yu., Yakunin A.A.

A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia

Koscheev V.N. – Leading Researcher, Cand. Sci. (Phys.-Math.).
Tormischev I.V. – Researcher.
Mischin V.A. – Researcher.
Peregudov A.A. – Researcher, Cand. Sci. (Phys.-Math.). Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-47-16; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Raskach K.F. – Researcher, Dr. Sci. (Phys.-Math.).
Semenov M.Yu. – Leading Researcher, Cand. Sci. (Phys.-Math.).
Yakunin A.A. – Researcher.


The purpose of this work was to test the CROSSER high-speed constant preparation module for use in the practice of engineering calculations of the neutron-physical characteristics of fast reactors. Computational models of fast reactors BN-600, BN-800 and BN-1200 were used as test tasks. The following neutron-physical parameters were calculated: the criticality of the reactor model, the efficiency of the CPS and the sodium void coefficient of reactivity. The main reactor functionals were calculated using the MMKK engineering program, the constants for which were prepared using the CROSSER module. The initial sets of nuclear data for the MMKK program were the ABBN-93 library of constants and the constants in the ABBN-RFE formats obtained on the basis of the ROSFOND-2010 library. The results obtained using the MMKC program with detailed tracking of the particle energy were used as the reference calculation results. Detailed data in ACE format obtained from the ROSFOND-2010 library were used as the initial nuclear data for this program.

optimization, acceleration of the preparation of group constants, libraries of group constants ABBN-93, ABBN-RF, neutron library ROSFOND-2010, programs for calculating MMKK, MMKS, calculation of neutronic characteristics, models of fast reactors BN-600, BN-800, BN-1200

Article Text (PDF, in Russian)


UDC 519.688

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2020, issue 4, 4:2