Nuclear Engineering Division researchers have developed a number of large-scale computer codes for scientific and engineering applications. These codes are validated and maintained for application in a variety of nuclear energy research programs. |
Fast Reactor Cross Section Processing Codes
- ETOE-2 - A program for ENDF/B to MC22 data conversion
- MC2-3 - A code to calculate fast neutron spectra and multigroup cross sections
- SDX - A space dependent cross section generation capability
Diffusion and Transport Theory Codes
- DIF3D - DIF3D's nodal option solves the multigroup steady state neutron diffusion and transport equations in two- and three-dimensional hexagonal and cartesian geometries.
- DIF3DK - A Nodal Kinetics Code for Solving the Time-Dependent Diffusion Equation
- PROTEUS - Simulation toolset for high-fidelity reactor physics analysis based on Sn, Method of Characteristics (MOC) and nodal method
- VIM - A continuous energy neutron and photon transport code
Fuel Cycle / Depletion Codes
- REBUS-3 - A system of codes designed for the analysis of reactor fuel cycles
- RCT - Post-processor for the depletion-dependent results of REBUS-3/DIF3D nodal calculations
- ORIGEN-RA - Modified version of the ORIGEN code developed by Oak Ridge National Laboratory to perform nuclide transmutation calculations based on the flux history computed with REBUS-3 and RCT
- ADDER - Advanced Dimensional Depletion for Engineering of Reactors
Perturbation Theory Codes
- VARI3D - Generalized perturbation theory and uncertainty analysis code based on DIF3D diffusion option for computation of reactivity coefficient distributions and kinetics parameters
- PERSENT - Generalized perturbation theory code and uncertainty analysis code based on transport equation for computation of reactivity coefficient distributions and kinetics parameters
Thermal-Hydraulic Codes
- SE2-ANL - Modified version of the SUPERENERGY-2 thermal-hydraulic code
- DASSH - Ducted Assembly Steady-State Heat Equation software
Reactor Dynamics and Safety Analysis Codes
- SAS4A/SASSYS-1 - Systems-level software for the deterministic analysis of design basis and beyond-design basis accidents in liquid metal cooled reactors (LMRs)
- SAS-DIF3DK - Software designed to perform deterministic analysis of coupled neutronics/thermal-hydraulic transients in water-cooled thermal reactors
- SAM - A modern system analysis tool for advanced non-LWR safety analysis
Surveillance and Diagnostics Codes
- MSET - Software system for real-time process monitoring
- PRODIAG - Software environment for producing customized diagnostic systems for continuous thermal-hydraulic (T-H) processes
User Interface to ARC Codes
- Workbench/PyARC - User interface to the ARC codes that facilitates input generation, workflow management, and output processing
- OTERR (Optimization of TEst Reactor Reloading) - Developed to solve optimization problems related to the fuel handling and reloading in fast reactors
Fuel Cycle Transition Analysis Codes
- DYMOND - Nuclear fuel cycle systems code that simulates the time-dependent behavior and evolution of the entire nuclear fuel cycle
Economics Codes and Algorithms
- ACCERT - Algorithm for the Capital Cost Estimation of Reactor Technologies
- NE-COST - Combinations of algorithms that calculate levelized cost of nuclear fuel cycle options
Acquired Codes
- TWODANT
- KENO
- WIMS
- DRAGON
- MCNP
- FIDAP
- RELAP5-Mod 3.2
- DVSLR
- OpenMC
Last Modified: Mon, June 8, 2020 6:21 PM