Monali-Rev.1: a Monte Carlo code for analysing fuel assemblies of nuclear reactors

MONALI-Rev.1 is a multigroup Monte Carlo program developed on ND computers for analysing fuel assemblies of nuclear reactors. This version of the code is flexibly dimensioned so that the allowed size of a problem is limited only by the total data storage required. The code can read multigroup data for various nuclides directly from WIMS multigroup (69/27) cross section sets. Most of the input data, with the exception of cross sections, if needed, are read in free format. The treatment of anisotropy (up to P1 at present) may be in selective mixtures. The input to the geometry module has been simplified. The code has flexibility in the definition of regions. The results calculated by the code include Keff, multigroup leakages and absorptions, group- and region-dependent fluxes. The multigroup leakages are calculated for each outer-most surface. Statistical confidence limits are also assigned to the results. In the end frequency distributions are found for the multiplication factor and optionally a normality test is also performed on the multiplication factors. (author). 8 refs., 4 figs., 2 tabs., 2 appendices