| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 1728717 | Annals of Nuclear Energy | 2013 | 15 Pages |
Abstract
⺠A new hybrid transport method is described for whole core calculations in 3-D hexagonal geometry. ⺠A deterministic procedure uses stochastically-generated information to solve core problems without low-order or homogenization approximations. ⺠The method is evaluated using comparisons with full core Monte Carlo reference solutions of gas-cooled, graphite-moderated reactor core designs. ⺠This new method enables highly accurate determination of core eigenvalues and flux shapes in hexagonal cores. ⺠The efficiency far exceeds that of other transport methods.
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Authors
Kevin John Connolly, Farzad Rahnema,