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Ce contenu n'est pas disponible en français.STARS Swiss Simulation Platform (SwissP) - Methods and Tools
A main objective of the STARS activities is the establishment of multi-physics and/or multi-scale computational schemes along with uncertainty quantification methodologies. Thereby a large fraction of the research relates to the development of SwissP specific platforms/modules aimed at coupling/linking the various codes/models such as to achieve systematic and integrated schemes as starting point for the best-estimate analyses with uncertainty quantifications. The main SwissP platforms, modules and methodologies currently under development and testing are listed below along with a short description of their purpose.
| Code | Scope within STARS SwissP |
|---|---|
| CMSYS | PSI Core Management SYStem for development and validation of CASMO/SIMULATE Swiss reference core analysis methodologies |
| PMSYS | PSI Plant Management SYStem for development and validation of TRACE Swiss reference plant system analysis methodologies |
| FMSYS | PSI Fuel Management SYStem for development and validation of FALCON Swiss reference fuel behaviour analysis methodologies |
| BOHR | Bundle Operating History Reconstruction module for model coupling to Falcon/nTRACER/MCNP |
| COBALT loop | System of modules for COnsolidated Best-estimate plus uncertainty Analysis of Lwr Transients |
| COMPLINK | Module for pin-wise nuclide COMPosition data LINKage between CMSYS and MCNP full core models |
| HDS | Hybrid deterministic/stochastic Depletion Scheme based on CASMO-5/Serpent coupling |
| SerpL | Module for Serpent few-group nuclear data Linkage with SIMULATE core models |
| SOURCE4MC | Computation scheme for CASMO/SIMULATE volumetric SOURCE transfer for MCNP core models |
| SHARK-X | PSI methodology for cross-section (Xs) and nuclear data uncertainty propagation with CASMO-5 |
| SHARK-RMB | PSI methodology for propagation of Reactor operation, Manufacturing tolerances and Burnup induced uncertainties with CASMO-5 |
| NUSS-RF | PSI methodology for nuclear data uncertainty quantification and global sensitivity analysis for MCNP calculations |
| MTUQ | PSI methodology for Manufacturing and Technological Uncertainty Quantification in MCNP calculation |
