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