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Abstract
A new 3-D nodal SNtransport method has been developed for Cartesian and hexagonal geometries. In the present method, the neutron angular distributions of intra-node fluxes and transverse-leakage are represented using the SNquadrature set, and the spatial distribution of neutron source is approximated by a quadratic polynomial expansion. Several considerations in numerical procedures to achieve stable convergence are also mentioned. Some numerical results are represented to show the validity of the method.
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