The nuclear simulation codes that currently form part of the STARS SwissP are listed below. The specific purpose of each code as currently used within STARS is specified noting that the given codes might be designed and/or employed for additional purposes. Finally, the code providers with whom STARS collaborates for development/validation are also specified.
| Code | Scope within STARS SwissP | Developer |
|---|---|---|
| Casmo-4/5 | Reference deterministic 2-D assembly transport/depletion (M-G MOC) | Studsvik |
| CMSLink | Few-group cross section processor for SIMULATE/S3K core static/transient core calculations | Studsvik |
| SIMULATE-3/5 | Reference deterministic 3-D steady-state core simulator (2-G/M-G diffusion/SPn) | Studsvik |
| SIMULATE-3K (S3K) | Reference deterministic 3-D transient core simulator (2-G diffusion) | Studsvik |
| SNF | Spent fuel inventory calculations | Studsvik |
| nTRACER | Complementary deterministic "Direct" pin-by-pin 3-D full core transport solver (M-G, 2-D MOC/1D SPn) | Seoul University |
| DYN3D | Complementary deterministic pin-cell homogenized 3-D core solver (M-G, SPn) | HDZR |
| Serpent | Reference Monte-Carlo-2-D/3-D code for fuel assembly depletion/decay | VTT |
| MCNP | Reference Monte-Carlo 3-D neutron/transport code for out-of-core applications and full core modelling | Los Alamos |
| Vesta | Monte-Carlo depletion interface code (for ORNL/Origen and IRSN/Phoenix depletion/decay modules) | IRSN |
| Cinder | Complementary fuel depletion/decay solver | LANL |
| NJOY | Nuclear data processing system | LANL |
| TRACE | Reference plant system code for 1-D/3-D thermal-hydraulics | US NRC |
| TRACE/PARCS | Complementary coupled 3-D core/plant code system for transient analyses | US NRC/UMICH |
| COBRA-TF | Reference code for sub-channel 3-D thermal-hydraulics | Penn State |
| STAR-CCM+ | Reference 3-D Computational Fluid Dynamics solver | CD-Adapco |
| OpenFOAM | Complementary 3-D Computational Dynamics slover | Open source |
| GOTHIC | Reference code for containment 3-D Thermal-Hydraulics (Under PSI/LH Responsiblity) | US NRC |
| FALCON MOD01 | Reference code for 2-D fuel Thermo-Mechanics (steady-state/transient) | EPRI |
| Falcon V1 | New version of Falcon 2-D Fuel thermo-mechanics code | EPRI/PSI |
| DIFFOX | Mechanistic modelling of clad oxygen diffusion during thermal transients | IRSN |
| CP2K | Atomistic simulations and multi-scale modelling of fuel materials | Open source |
| PERFORM-60 | Multi-Scale simulation and modelling platform for evolution of reactor pressure vessel materials | EDF-EU 7th FP |
| LAKIMOCA | Kinetic Monte-Carlo solver for irradiation-induced damage of steel material micro-structures | EDF |
| URANIE | Uncertainty and sensitivity analsys platform | CEA |
General Contact
Research Division
Nuclear Energy and Safety (NES)
Laboratory for Reactor Physics and Thermal-Hydraulics (LRT)
Paul Scherrer Institute
5232 Villigen PSI
Switzerland
Hakim Ferroukhi
Head of the Laboratory
Office: OHSA/C10
Telephone: +41 56 310 4062
E-mail: hakim.ferroukhi@psi.ch
Petra Kull
Administration and Assistance
Office: OHSA/C18
Telephone: + 41 56 310 2685
E-mail: petra.kull@psi.ch
Quality Management
NES Open positions
Current job openings in the Research Division for Nuclear Energy and Safety