The preceeding year's most commonly requested code packages from CPS are listed below by category. This list is not intended to be exhaustive, but rather to provide a shortcut for users wishing to request these popular packages. To submit a request, click the link nested in the name of the desired package.
If you desire a package that is not listed, we invite you to search in the full catalogue to place your request.
CRISTAL V2.0.2 - criticality calculations for nuclear fuel cycle facilities (fabrication, reprocessing, etc.), storage and transportation of fissile materials.
SCALE 6.2.3 - tool set for criticality safety, reactor and lattice physics, radiation shielding, spent fuel and radioactive source term characterization, and sensitivity and uncertainty analysis.
MORET 5.D.1 - simulation tool that solves the Bolzmann's equation using the Monte Carlo method.
ADVANTG 3.2.1 - automated tool for generating variance reduction parameters for fixed-source continuous-energy Monte Carlo simulations with MCNP.
INES-CLASS - assessment of accidents of significance that occurred at nuclear facilities.
SERPENT 1.1.7 - tool for continuous-energy Monte Carlo reactor physics burnup calculation, lattice physics applications.
SUPERMC 3.3.0 - transport calculation tool of neutron, gamma radiation process that can also be applied for criticality and shielding design of reactors as well as analysis in medical physics.
TRIPOLI-4 VERSION 9S - coupled neutron, photon, electron, positron 3-D, time dependent Monte-Carlo transport calculation software.
VISUAL EDITOR 61 - program that can run and plot MCNP geometries and calculations.
FISPACT-II 4.0 - inventory simulation platform for nuclear observables and materials science.
PENELOPE 2014 - a Monte Carlo code system for coupled electron photon transport at high energies.
PHITS-2.88 - transport suite covering almost all particles over wide energy ranges, using several nuclear reaction models and relevant nuclear data libraries.
FINIX 1.19.1 - a fuel behavior module that calculates the thermal and mechanical behavior of a nuclear fuel rod during steady-state and transient conditions.
SOURCES-4C - code system that determines neutron production rates and spectra from (alpha,n) reactions, spontaneous fission, and delayed neutron emission due to radionuclide decay.
VARSKIN 4 V4.0.0 - skin contamination dose calculation utility.