FAST: An advanced code system for fast reactor transient analysis

Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systems

“…Nevertheless, PARCS is used as a 3D neutron kinetics solver in the FAST code system developed at Paul Scherrer Institute for fast reactor transient analysis (Mikityuk et al, 2005). In the FAST code system PARCS is coupled with thermal-hydraulic code TRACE (Spore et al, 2001) and fuel performance code FRED (Mikityuk and Shestopalov, 2011).…”

GeN-Foam: a novel OpenFOAM® based multi-physics solver for 2D/3D transient analysis of nuclear reactors

“…Simulation of the transient behavior of nuclear reactors has been based for many years on the loose coupling of available legacy codes for neutron diffusion and 1-D or sub-channel thermal hydraulics (Mikityuk et al, 2005;Kozlowski et al, 2014). Typically the coupling is achieved through data exchange interfaces that exchange the most relevant information at each time step.…”

“…Section 3 describes the coupling strategy. Section 4 presents a preliminary code-to-code benchmark with the TRACE code (Mikityuk et al, 2005;Spore et al, 2000). The conclusions of the work are drawn in Section 5 while Appendix A presents the SFR design as used in this work.…”

BELLA: a multi-point dynamics code for safety-informed design of fast reactors

“…SAS4A/SASSYS-1 (Cahalan and Fanning, 2012), SIMMER (Kondo et al, 1992), GRIF (Chvetsov and Volkov, 1998) and DYNA-P (Natesan et al, 2011) are notable exceptions. In other cases, codes originally qualified for LWRs have been adapted for simulation of fast reactors (Mikityuk et al, 2005;Mochizuki et al, 2007;Tenchine et al, 2012).…”