VIM
A continuous energy neutronics and photon transport code.
Usage: ln -s input VIMINPT ; vim > output
Location: /usr/codes/vim
VIM solves the steady-state neutron of photon transport problem in any detailed
three-dimentional geometry using continuous energy-dependent nuclear data or
multigroup cross sections. The processed nuclear data and the code itself have
been extensively benchmarked on a wide variety of reactor problems. Neutron
transport is carried out in a criticality mode, or in a fixed source mode
optionally incorporating subcritical multiplication. The geometry options are
infinite medium, combinatorial geometry, place lattice, and hexagonal or
rectangular lattices of combinatorial geometry cells. Boundary conditions
include vacuum, specular and white reflection, and periodic boundaries for
reactor cell calculations. Reaction rates are tallied by energy group and
edit region to facilitate comparison to multigroup calculations.
VIM uses standard Monte Carlo methods for particle tracking with several
optional variance-reduction techniques. These include splitting/Russian
roulette, non-terminating absorption with nonanalog weight cutoff energy, and pseudoparticle collisions for scattering matrix estimation.
"VIM", R.N. Blomquist. Advances in Mathematics, Computations, and Reactor
Physics, Vol. 5. 1991.