Browsing by Author "Nichita, Eleodor M."
Now showing items 1-2 of 2
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Three dimensional heterogeneous finite element method for static multi-group neutron diffusion
Aydogdu, Elif Can (2010-08-01)Because current full-core neutronic-calculations use two-group neutron diffusion and rely on homogenizing fuel assemblies, reconstructing pin powers from such a calculation is an elaborate and not very accurate process; ... -
Transport-theory-equivalent diffusion coefficients for node-homogenized neutron diffusion problems in CANDU lattices
Patel, Amin (2010-04-01)Calculation of the neutron flux in a nuclear reactor core is ideally performed by solving the neutron transport equation for a detailed-geometry model using several tens of energy groups. However, performing such detailed ...