Cross-section libraries for the ORIGEN-ARP system were extended to include four non-U.S. reactor types: the Magnox reactor, the Advanced Gas-Cooled Reactor, the VVER-440, and the VVER-1000. Typical design and operational parameters for these four reactor types were determined by an examination of a variety of published information sources. Burnup simulation models of the reactors were then developed using the SAS2H sequence from the Oak Ridge National Laboratory SCALE code system. In turn, these models were used to prepare the burnup-dependent cross-section libraries suitable for use with ORIGEN-ARP. The reactor designs together with the development of the SAS2H models are described, and a small number of validation results using spent-fuel assay data are reported.

As part of a larger program to study mixed-oxide fuel subject to high burnup, some UO 2 samples were exposed and analyzed. This report discusses results from the analysis of a UO sample 2 that was burned in a boiling-water reactor (BWR) to approximately 57 GWd/t. The sample enrichment was high (a U content of 4.94%) relative to the surrounding UO fuel. The isotopic 235 2

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