Authors & Affiliations

Kavun V.O., Kavun O.Yu.
Scientific and Engineering Centre for Nuclear and Radiation Safety, Moscow, Russia

Kavun V.O. – Junior Research, Scientific and Engineering Centre for Nuclear and Radiation Safety. Contacts: bld. 5, 2/8, Malaya Krasnoselskaya st., Moscow, Russia, 107140. Tel.: +7(499)264-05-84; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Kavun O.Yu. – Head of the Laboratory of Dynamic Modes, Dr. Sci. (Tech.), Scientific and Engineering Centre for Nuclear and Radiation Safety.

Abstract

For emergency response purposes, Rostekhnadzor has established an information and analytical center (IAC). Working groups of scientific and technical support of SECNRS operate as a part of Rostekhnadzor in the emergency mode. The task of the working groups is to assess the state of the emergency power unit of the NPP and forecast its possible development. To solve the above-mentioned task by the working groups, it is necessary to determine the release of radionuclides into the environment in case of a severe accident, as well as the efficiency of the control and protection system and reactivity coefficients for the current moment of the fuel download for Express assessment models. To determine these parameters in SECNRS was developed the neutron-physical model of the cores of the reactors of all power units of NPP with VVER. The article is devoted to the application of the above-mentioned models, which are a set of initial data for the performance of neutron-physical calculations by DESNA code with neutron-physical cross sections, the calculation of which is performed on the code SAPHIRE-95. The developed models are kept up-to-date, taking into account the current fuel loads. In the simulation of reactivity-induced accidents, which require the use of three-dimensional models of the core, the developed model will connect to the models of rapid assessment. The verification of the developed calculation models of cores by comparing the results of calculations for the code DESNA with the results of design calculations, which demonstrated the correctness of the developed models. The article presents the results of calculations for DESNA code and the results of verification of the developed calculation models of cores by comparing the results of calculations for DESNA code with the results of design calculations.

Keywords
neutron-physical models, VVER, verification, security provision

Article Text (PDF, in Russian)

References

UDC 621.039.5

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants", 2018, issue 2, 2:19