Available Nuclear Engineering Codes at the ANECL


The following codes are available for use at the ANECL

CPM-2: A multi-group two-dimensional lattice physics computer code designed for the analysis of the light water reactor fuel assembly designs.

GTRAN2: A multi-group two-dimensional lattice physics computer code designed for complex heterogeneous reactor fuel assembly designs.

ESCORE: A Nuclear reactor fuel performance code

MAGGENTA: A multi-group multi-assembly multi-processor 2D/3D lattice physics computer code developed for complex heterogeneous reactor core designs.

MAGG-SCALE: A multi-group multi-assembly 2D depletion physics computer code developed by coupling MAGGENTA and SCALE 4.3 for analysis of complex heterogeneous reactor core designs.

MCNP: A Monte Carlo N-Particle transport code

NJOY: A nuclear cross section processing system

NORGE-B: A linking module for neutronic analysis codes (BWR)

NORGE-P: A linking module for neutronic analysis codes (PWR)

RELAP: A thermohydraulic reactor analysis code

SCALE: A modular code system for performing standardized computer analysis for licensing evaluation

SIMULATE A full core 3D nuclear reactor analysis package

SWAN A 1D optimization code based on perturbation theory and 1D Sn method

TWODANT: Solves the two-dimensional multigroup transport equation

VIM A Monte Carlo code