PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY
Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

BROND-3.1

ISSUES

2022, Issue 2

MCU-RBMK ADDITIONAL VERIFICATION FOR NUCLEAR AND RADIATION SAFETY ANALYSIS OF NUCLEAR INDUSTRY FACILITIES

MCU-RBMK ADDITIONAL VERIFICATION FOR NUCLEAR AND RADIATION SAFETY ANALYSIS OF NUCLEAR INDUSTRY FACILITIES

EDN: JWDPJS

Authors & Affiliations

Alimov Yu.V., Kalugina K.M., Rozhdestvenskiy I.M., Sakharova T.Yu., Yufereva V.A.
N.A. Dollezhal Research & Development Institute of Power Engineering, Moscow, Russia

Rozhdestvenskiy I.M. – Lead Engineer. Contacts: 2/8, Malaya Krasnoselskaya str., Moscow, Russia, 107140. Tel.: +7 (499) 264-42-32; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Alimov Yu.V. – Senior Researcher.
Kalugina K.M. – Engineer.
Sakharova T.Yu. – Senior Researcher.
Yufereva V.A. – Researcher.

Abstract

MCU-RBMK code, based on Monte-Carlo method, has been verified and certified for neutron physics calculations of RBMK-1000 reactors, however, there are a number of tasks that can be successfully solved using the MCU-RBMK but require verification. During the development of the MCU-RBMK, the possibility of computational modeling of photon transfer determination of functionals associated with the interaction of photons with matter has been realized. The appearance of new experimental data related to the distribution of the fast neutron flux density and the distribution of the photon flux density expands the verification base and makes it possible to perform additional verification of the MCU-RBMK precision code. The realization of the neutrons and photons joint transfer, as well as the ability to determine the neutron and photon sources in a problem with a change the isotopic composition in materials, allow using MCU-RBMK to calculate the equivalent dose rate during operations with radioactive materials in problems with arbitrary geometry. In this paper, we consider fresh and spent nuclear fuel, including fuel with an increased content of uranium even isotopes. This opens up new possibilities for using the MCU-RBMK for calculations of fast neutron flux, photon flux, as well as for calculating the equivalent dose rate.

Keywords
safety, precision code, Monte-Carlo method, verification, fast neutron transfer, photon transfer, equivalent dose rate

Article Text (PDF, in Russian)

References

UDC 621.029.51

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2022, issue 2, 1:3