A Monte Carlo program is described that calculates Dancoff factors in
arbitrary arrangements of cylindrical or spherical fuel elements. The
fuel elements can have different diameters and material compositions,
and they are allowed to be black or partially transparent. Calculation
of the Dancoff factor is based on its collision probability definitio
n. The Monte Carlo approach is recommended because it is equally appli
cable in simple and in complicated geometries. It is shown that some o
f the commonly used algorithms are inaccurate even in infinite regular
lattices. An example of application includes the Canada deuterium ura
nium (CANDU) 37-pin fuel bundle, which requires different Dancoff fact
ors for the symmetrically different fuel pin positions.