Article ID Journal Published Year Pages File Type
1741581 Progress in Nuclear Energy 2006 9 Pages PDF
Abstract

We have participated in the Expert Group on 3-D Radiation Transport Benchmarks' 3-D Extension C5G7 MOX problems using the discrete ordinate transport code PARTISN. The computational mesh was created using the FRAC-IN-THE-BOX code, which produces a volume fraction Cartesian mesh from combinatorial geometry descriptions. keff eigenvalues, maximum pin powers, and average fuel assembly powers are reported and compared to an MCNP™ (MCNP is a trademark of the Regents of the University of California, Los Alamos National Laboratory) reference solution. We also present a two-dimensional mesh convergence study examining the affects of using volume fractions to approximate the water–pin cell interface. It is noted that the previous PARTISN results provided to the OECD/NEA Expert Group on 3-D Radiation Benchmarks contained a cross-section error, and therefore should be disregarded.

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