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 4

BURAN PROGRAM VALIDATION BASED ON EXPERIMENTS

BURAN PROGRAM VALIDATION BASED ON EXPERIMENTS

EDN: AJVFGA

Authors & Affiliations

Bolnov V.A., Bogdanova E.V., Malkin S.A.
Afrikantov OKBM JSC, Nizhny Novgorod, Russia

Bolnov V.A. – Head of Department.
Bogdanova E .V. – Head of Design Group.
Malkin S .A. – Lead Design Engineer, Cand. Sci. (Tech.). Contacts: 115 Burnakovsky proyezd, Nizhny Novgorod, Russia, 603074. Tel.: +7 (987) 111-54-93; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..

Abstract

The BURAN program is used to calculate the normal and emergency modes of BN-type installations at JSC Afrikantov OKBM. In 2021, her attestation passport expired. The program was upgraded, after which it was submitted for recertification to the SEC NRS. In the report on the justification of the applicability of the BURAN program, all available experimental data were used. This article presents the results of validation of the BURAN program by comparing the calculation results with experimental data obtained only at the BN-600 reactor plant. These are modes with a planned change in power, shutdown of the power unit at a power of 95 % Nnom, complex testing of the emergency cooling system and removal of residual heat due to heat losses from the reactor pressure vessel and from the secondary circuit in the absence of circulation in the third circuit. Based on the results of comparison of calculated and experimental data, the possibility of using the BURAN program for calculating transient processes in installations with fast neutron reactors with sodium coolant in normal operation modes, in modes with disruption of normal operation, requiring an emergency transfer of the installation to reduced power levels, is substantiated. Transient processes can be with long-term cooling down due to heat losses from the reactor vessel, from equipment and pipelines of the secondary circuit, with a complete failure of forced heat removal systems.

Keywords
validation, program, BURAN, reactor facilities, fast, BN-600, experiment, dynamics, temperature, deviations, results

Article Text (PDF, in Russian)

References

UDC 621.039.526

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2022, no. 4, 4:17