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A study of the performance of a sparse grid cross section representation methodology as applied to MOX fuel

Danniëll Botes, Saymore Chifamba, Pavel M. Bokov

Ann. Nucl. Energy, vol: 99, num: 0, Pages 444-454, published: 01 January 2017,


   Nuclear reactor physics.
      Theory and calculation of nuclear reactors and radiation transport.
         Calculation methods and computer codes.
            Heterogeneous methods. Homogenization.

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