Look for them in Google or Wikipedia. For example, in Thermal-Hydraulics are GOTHIC, RELAP, RETRAN, etc. In Computational Fluid Dynamics are CFX, FLUENT, etc. In Severe Accidents, MELCOR, MAAP etc.

1. Monte Carlo Radiation Transport[edit]

• MCNP
• MCCARD
• Serpent
• Geant4
• OpenMC - https://github.com/openmc-dev/openmc
• TRIPOLI-4 - http://www.cea.fr/nucleaire/tripoli-4
• SCALE(KENO V and KENO VI) - https://www.ornl.gov/scale

2. Transmutation, fuel depletion

• ORIP_XXI code Isotope transmutation simulations
• ORILL Code 1D transmutation, fuel depletion (burn-up) and radiological protection code
• FISPACT-II Multiphysics, inventory and source-term code
• MURE Serpent-MCNP Utility for Reactor Evolution
• VESTA Monte Carlo depletion interface code
• PyNE The Nuclear Engineering Toolkit - https://pyne.io/

T/H Codes: Relap5

Neutronics: PARCS

Generals: MATLAB- Fortran- Pythone-

- MCNP, OpenMC or Serpent for particle transport

- NJOY for cross section preparation,

- JANIS for nuclear data analysis

- PARET, COOLOD, RELAP, COMSOL for thermal hydraulics

- Python, Cpp, VB, Fortran,

The US Department of Energy is supporting a lot of research where their MOOSE code is either being developed or applied.

Please have a look at this list:

https://github.com/paulromano/awesome-nuclear