Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

Authors & Affiliations

Bahdanovich R.B.1, Tikhomirov G.V.1, Saldikov I.S.1, Ternovykh M.Yu.1, Gerasimov A.S.2
1National Research Nuclear University MEPhI, Moscow, Russia
2Institute for Theoretical and Experimental Physics, Moscow, Russia

Bahdanovich R.B. – post-graduate student, assistent, National Research Nuclear University MEPhI. Contacts: 31, Kashirskoe shosse, Moscow, Russia, 115409. Tel.: (925)846-28-14, e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Tikhomirov G.V. – Engineer, National Research Nuclear University MEPhI.
Saldikov I.S. – Senior Lecturer, National Research Nuclear University MEPhI.
Ternovykh M.Yu. – Dr. Sci. (Phys. and Math.), Professor, Deputy Director, Institute of Nuclear Physics and Engineering, National Research Nuclear University MEPhI.
Gerasimov A.S. – Dr. Sci. (Tech.), Senior Scientist, Chief Scientist, Institute for Theoretical and Experimental Physics.


Nowadays most programs for calculation of nuclear reactors use models of energy release developed in the 70s. Since that time important changes have happened not only in computer science, but also in nuclear fuel: burnable absorbers and profiling of enrichment have been introduced.

From the standpoint of total energy release, these changes could considerably influence on its capturing component, that is on energy released in reactions with neutron disappearance by means of reaction channels (n,γ), (n,α), (n,p), etc. This is why the estimation of capturing component is a pressing problem. Addressing this problem could contribute to precision of released energy models and enhance precision of spent fuel characteristics. It is important to perform correct modeling of fuel burnup, which influences on its other characteristics.

The method for calculation of capturing reactions contribution to total energy release along with results of calculation is presented in the paper. This method assumes the use of programs based on Monte-Carlo method (MCNP, MCU, TDMCC, SERPENT, etc.), because these programs enable to conduct the most accurate calculations and obtain very close to experimental results.

The model of equivalent cell for VVER-1000 was calculated in order to test the developed method. After that, two models of fuel assembly for VVER-1000 with gadolinium as burnable absorber and without it were calculated to obtain more precise results and to estimate the influence of capturing component to total energy depending on the type of fuel assembly. Two models of fast BN-600 reactor were also considered. All models were calculated without fuel burn-up, considering only fresh fuel.

In calculations of energy released in active core by means of capturing reactions, one should determine these reactions along with their energy yield. Suggested model of active core with designation of material types and their volumes allowed to calculate reaction rates and instant and delayed energy release. These data make possible to calculate capturing reactions’ energy release and its part in total energy.

These calculations for VVER reactors demonstrated that total energy release decreases slightly as fuel abundance increases. The part of capturing energy release depends on the type of fuel assembly. This part makes 3,2% for fuel assembly without gadolinium and 3,6% for fuel assemblies with gadolinium.

Taking into account of capturing energy release enables to obtain more high precision in modeling nuclear reactor installations and in calculation spent fuel assemblies.

nuclear reactor, energy release, calculation, codes, nuclear reactions, neutron capture, VVER-1000

Article Text (PDF, in Russian)


UDC 620.039.5

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2017, issue 1, 1:15