Development of deterministic two and three dimensional neutron transport simulation methods for finite nuclear reactor calculations

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The main objective of this research proposal is to update the calculations techniques available in the code DRAGON, one of the very few lattice codes available worldwide that can deal with three dimensional deterministic transport problems, in such a way that it can be applied to full reactor systems. This implies: 1) generalizing DRAGON in such a way that it can treat more complex geometrical systems; 2) applying projection, extrusion and cyclic mapping methods to general prismatic geometries to accelerate the two and three dimensional line tracking process and to reduce by several orders of magnitude the dimensions of the resulting tracking file; 3) implementing parallel computation schemes in the code to benefit from the current development in computer technology; and 4) developing a robust acceleration scheme for the power iteration (fission sources and the multiplication constant) when large multi-energy (>100) and multi-region (> 100000) transport problems must be analyzed.