BWR transient analysis with the coupled code system S3K/RELAP5
-
C. Jönsson
Abstract
This paper describes the coupled code system S3K-RELAP5 and the application of the code system to BWR transients without scram. In addition short descriptions are given for application of the coupled system to fast transients and rod drop accidents. The models and methods of the code system are presented. Validation results are shown for a recorded transient event in the Forsmark 3 reactor. It is concluded that S3K-RELAP5 adequately captures the complicated interaction between physical processes in the reactor as well as the essential reactor protection and control systems, which qualifies it for applications to fast and slow transients, with or without scram, and Reactivity Initiated Accidents (RIA).
Kurzfassung
Dieser Beitrag beschreibt das gekoppelte Programmsystem S3K-RELAP5 und seine Anwendung auf SWR Transienten ohne Reaktorschnellabschaltung (RESA). Darüber hinaus wird kurz die Anwendung des gekoppelten Systems auf schnelle Transienten und auf einen Reaktivitätsstörfall durch Ausfall eines Steuerstabs aufgezeigt. Die Methoden und Modelle des Programmsystems werden dargestellt. Ergebnisse der Validierung für ein Ereignis in Forsmark 3 werden präsentiert. Es wird gezeigt, dass S3K-RELAP5 die komplexen Interaktionen zwischen den physikalischen Prozessen im Reaktor und den wesentlichen Systemen des Reaktorschutzsystems und der Steuerung adäquat wiedergibt. Diese Validierung qualifiziert das System für die Anwendungen auf schnelle und langsame Transienten mit und ohne RESA und auf Reaktivitätsstörfälle.
References
1 Grandi, G.; Smith, K.: S3K Explicit Fuel Pin Modeling during RIA. Trans. Am. Nucl. Soc.96 (2007) 627Search in Google Scholar
2 Judd, J.; Grandi, G.: SIMULATE-3K/RELAP5-3D, A Coupled Code System. Trans. Am. Nuc. Soc.. 97 (2007) 709Search in Google Scholar
3 NKS-162 RADDA – Comparison of Results of Three ATWS/ATWC Scenarios Simulator with the Help of POLCA-T and S3K/RELAP5, Nordic Nuclear Safety Research, March 2008Search in Google Scholar
4 Jönsson, C.; Grandi, G.; Judd, J.: Severe Reactivity Initiated Accidents with SIMULATE-3K and SIMULATE-3K/RELAP5 in Forsmark 3 BWR. TopFuel, 2010, Orlando, Florida, USASearch in Google Scholar
5 Belblidia, L. A.; Grandi, G. M.; Jönsson, C.: SIMULATE-3K Peach Bottom 2 Turbine Trip 2 Benchmark Calculations. Nuclear Science and Engineering148 (2004) 325–326Search in Google Scholar
6 Judd, J.; Grandi, G.: A Best-estimate Coupled Code for Reactor Safety Analyses using SIMULATE-3K and RELAP5-3D, ANFM-IV, 2009, Hilton Head Island, South Carolina, USASearch in Google Scholar
7 Nikitin, K.; Judd, J.; Grandi, G.: Peach Bottom 2 Turbine Trip 2 Simulation by TRACE/SIMULATE3-K Coupled Code, 2010 International Conference on the Physics of Reactors, 2010, Pittsburgh, Pennsylvania, USASearch in Google Scholar
© 2011, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Plant behaviour and coupling with reactor physics
- Technical Contributions/Fachbeiträge
- Multi-scale coupled code systems: from coarse-mesh to high-fidelity LWR core calculations
- Development of multi-physics code systems based on the reactor dynamics code DYN3D
- Development of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR
- Influence of nuclear data uncertainties on reactor core calculations
- Analysis of reactor lattice and core parameters in view of nuclear data modifications
- A complementary Doppler Broadening formalism and its impact on nuclear reactor simulation
- Experiences with the coupled code system S3R/RELAP5-3D in training simulators
- BWR transient analysis with the coupled code system S3K/RELAP5
- The development and assessment of TRACE model for Lungmen ABWR
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Plant behaviour and coupling with reactor physics
- Technical Contributions/Fachbeiträge
- Multi-scale coupled code systems: from coarse-mesh to high-fidelity LWR core calculations
- Development of multi-physics code systems based on the reactor dynamics code DYN3D
- Development of the coupled 3D neutron kinetics/thermal-hydraulics code DYN3D-HTR for the simulation of transients in block-type HTGR
- Influence of nuclear data uncertainties on reactor core calculations
- Analysis of reactor lattice and core parameters in view of nuclear data modifications
- A complementary Doppler Broadening formalism and its impact on nuclear reactor simulation
- Experiences with the coupled code system S3R/RELAP5-3D in training simulators
- BWR transient analysis with the coupled code system S3K/RELAP5
- The development and assessment of TRACE model for Lungmen ABWR
