Authors & Affiliations

Bahdanovich R.B.1,2, Romanenko V.I.1, Khokhlov S.Y.1, Tikhomirov G.V.1
1National Research Nuclear University MEPhI, Moscow, Russia
2Belarusian State University, Minsk, Belarus

Bahdanovich R.B. – post-graduate student, assistent, Institute of Nuclear Physics and Engineering, 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..
Romanenko V.I. – student, Institute of Nuclear Physics and Engineering, National Research Nuclear University MEPhI.
Khokhlov S.Y. – student, Institute of Nuclear Physics and Engineering, National Research Nuclear University MEPhI.
Tikhomirov G.V. – Dr. Sci. (Phys. and Math.), Professor, Deputy Director, Institute of Nuclear Physics and Engineering, National Research Nuclear University MEPhI.

Abstract

Calculation of an effective energy release in the fuel core is very important during the operation and design of a nuclear reactor. Use of the modern computing capacities and calculation methods allows to receive the results, close to reality, and also to solve problems inaccessible to the experimental consideration. Now the majority of calculating programs not absolutely correctly consider capture component of an energy release which is bound to reactions of neutron capture (reactions (n,γ), (n,α), etc.). When using approximate value of an effective energy release in the reactor, there can be an essential mistake in calculation of distribution of an energy release, burnup of fuel and characteristics of spent nuclear fuel. The developed method of calculation of components of an effective energy release in the nuclear reactor will allow to specify the used values of capture energy release for the fast reactors. The technique offered for calculation of a contribution of a capture component to the effective energy release in nuclear reactor assumes use of the high-precision codes based on a Monte-Carlo method (MCNP, MCU, SERPENT, etc.) which allows to carry out high-precision calculations and to receive the results which are very close to an experiment. Results of calculations of capture component fraction in an effective energy release for various models of the BN-600 reactor (with uranium fuel, the MOSS fuel, a hybrid fissile region) by three codes MCU 5, MCNP 4 and SERPENT 1.1.19 are given in work. It is shown that the fraction of capture component is approximately equal to 4-5% of an effective energy release. During the calculations we attempt to create a simple test model of the reactor for calculation of energy release components, taking into account its specific features.

Keywords
BN-600, energy release, method, neutron-capture reactions, capture component, fission energy, MCU, SERPENT, MCNP

Article Text (PDF, in Russian)

References

UDC 621.039.5

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants", 2017, issue 1, 1:9