Evaluation of Internal Criticality of the Plutonium Disposition MOX SNF Waste Form
Evaluation of Internal Criticality of the Plutonium Disposition MOX SNF Waste Form
The purpose of this calculation is to perform a parametric study to determine the effects of fission product leaching, assembly collapse, and iron oxide loss on the reactivity of a waste package containing mixed oxide spent nuclear fuel. Previous calculations (CRWMS M&O 1998a) have shown that the criticality control features of the waste package are adequate to prevent criticality of a flooded WP for all the enrichment/burnup pairs expected for the MOX SNF.