The paper presents an evaluation of RELAP5-3D code suitability to model specific transients that take place during RBMK-1500 reactor operation, where the neutronic response of the core is important. A successful best estimate RELAP5-3D model of the Ignalina NPP RBMK-1500 reactor has been developed and validated against real plant data. Certain RELAP5-3D transient calculation results were benchmarked against calculation results obtained using the Russian code STEPAN, specially designed for RBMK reactor analysis. Comparison of the results obtained, using the RELAP5-3D and STEPAN codes, showed quite good mutual coincidence of the calculation results and good agreement with real plant data.
- Nuclear Engineering Division
RELAP5-3D Code Application for RBMK-1500 Reactor Core Analysis
Bubelis, E, Kaliatka, A, & Uspuras, E. "RELAP5-3D Code Application for RBMK-1500 Reactor Core Analysis." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 14–18, 2002. pp. 757-765. ASME. https://doi.org/10.1115/ICONE10-22450
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