Izvestiya vuzov. Yadernaya Energetika

The peer-reviewed scientific and technology journal. ISSN: 0204-3327

Development and verification of the TR-BN program for validation of the normal operation modes in the BN reactors

3/28/2016 2016 - #01 Modelling processes at nuclear facilities

Fadeev I.D. Dmitrieva I.V. Osipov S.L. Rogozhkin S.A.

DOI: https://doi.org/10.26583/npe.2016.1.04

UDC: 621.039.513:621.039.526

Validation of design parameters for the BN sodium cooled fast reactor plants in the normal operation modes is an important task that has to be solved to determine the safe and optimal operation conditions. Programs existing for this purpose enable computational analyses of individual equipment (for example, a steam generator) or a circulation circuit (secondary and third circuits). In order to accomplish the integrated analysis of the thermal-hydraulic parameters, the TR-BN program has been developed that is intended to define the main design characteristics (temperature, flow rate) for all heat transfer circuits (including the primary circuit) and to optimize the operation algorithms for the BN reactor plants in the normal operation modes at various power levels.

Presented is a brief description of the program, calculational procedure and possible analysis options depending on the steam generator design. The TR-BN program has been verified and cross-verified through comparing the calculated results with operational data from the BN-600 reactor plant and with the results calculated by the Korsar/GP program for the steam generator of the BN-800 reactor. The analysis of the obtained results has shown satisfactory agreement — the maximum relative deviation of the temperature is below 7.5% for sodium; and 14.2 %, for steam. For the parameters calculated by TR-BN, the root-mean-square errors have been defined that characterize the accuracy of the accomplished calculations. It has been shown that the TR-BN program can be used to validate safety of the BN reactor plants in the normal operation modes.

Ссылки

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verification sodium coolant steam generator error program reactor plant normal operation static parameters temperature