This paper deals with RELAP5-3D code validation through the modeling of RBMK-1500 specific transients taking place at Ignalina NPP. A successful best estimate RELAP5-3D model of the INPP RBMK-1500 reactor has been developed and validated against real plant data. The obtained calculation results demonstrate reasonable agreement with Ignalina NPP measured data. Behaviors of the separate MCC thermal-hydraulic parameters as well as physical processes are predicted reasonably well to the real processes, occurring in the primary circuit of RBMK-1500 reactor. The calculated reactivity and the total reactor core power behavior in time are also in reasonable agreement with the measured plant data, which demonstrates the correct modeling of the neutronic processes taking place in RBMK-1500 reactor core. The performed validation of RELAP5-3D model of Ignalina NPP RBMK-1500 reactor allowed to improve the model, which in the future would be used for the safety substantiation calculations of RBMK-1500 reactors.
Skip Nav Destination
12th International Conference on Nuclear Engineering
April 25–29, 2004
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4689-X
PROCEEDINGS PAPER
RELAP5-3D Code Validation for RBMK-1500 Reactors Available to Purchase
Evaldas Bubelis,
Evaldas Bubelis
Lithuanian Energy Institute, Kaunas, Lithuania
Search for other works by this author on:
Algirdas Kaliatka,
Algirdas Kaliatka
Lithuanian Energy Institute, Kaunas, Lithuania
Search for other works by this author on:
Eugenijus Uspuras
Eugenijus Uspuras
Lithuanian Energy Institute, Kaunas, Lithuania
Search for other works by this author on:
Evaldas Bubelis
Lithuanian Energy Institute, Kaunas, Lithuania
Algirdas Kaliatka
Lithuanian Energy Institute, Kaunas, Lithuania
Eugenijus Uspuras
Lithuanian Energy Institute, Kaunas, Lithuania
Paper No:
ICONE12-49122, pp. 429-438; 10 pages
Published Online:
November 17, 2008
Citation
Bubelis, E, Kaliatka, A, & Uspuras, E. "RELAP5-3D Code Validation for RBMK-1500 Reactors." Proceedings of the 12th International Conference on Nuclear Engineering. 12th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 25–29, 2004. pp. 429-438. ASME. https://doi.org/10.1115/ICONE12-49122
Download citation file:
7
Views
Related Proceedings Papers
Related Articles
A Simplified Two-Group Multipoint Kinetics Model
ASME J of Nuclear Rad Sci (January,2021)
The Fabulous Nuclear Odyssey of Belgium
J. Pressure Vessel Technol (June,2009)
Safety Evaluation of the HTTR-IS Nuclear Hydrogen Production System
J. Eng. Gas Turbines Power (February,2011)
Related Chapters
Developing Human Performance Measures (PSAM-0207)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
QRAS Approach to Phased Mission Analysis (PSAM-0444)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Modeling of SAMG Operator Actions in Level 2 PSA (PSAM-0164)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)