Nuclear Engineering Division

Software:

ETOE-2
MC2-3
SDX

PROTEUS

DIF3D
DIF3DK

REBUS-3
RCT
ORIGEN-RA

ADDER

VARI3D

PERSENT

SE2-ANL (SUPERENERGY2)

DASSH

SAS4A/SASSYS-1
SAM

MSET
PRO-AID

PyARC

OTERR

DYMOND

ACCERT

NE-COST


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Reactors designed by Argonne National Laboratory

Software

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

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 transfer software) - Calculates core-wide, steady-state coolant subchannel temperature and flow distributions in ducted, hexagonal assemblies

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)
  • SAM - A modern system analysis tool for advanced non-LWR safety analysis

Surveillance and Diagnostics Codes

  • MSET - Software system for real-time process monitoring
  • PRO-AID - (Parameter-Free Reasoning Operator for Automated Identification and Diagnosis) - Software package to perform real-time monitoring and diagnostics for an engineering system using a form of automated reasoning.

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) - Genetic algorithm for optimization of non-equilibrium fuel 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: Thu, January 21, 2021 10:43 AM