1967•Unpublished venueOpen access
A SURVEY AND EVALUATION OF THERMAL FISSION YIELDS FOR $sup 235$U, $sup 239$Pu, $sup 233$U, AND $sup 241$Pu.
General Electric Co., Pleasanton, Calif. Nuclear Technology Dept., B. Rider, C. Ruiz, J. Peterson, F.R. Smith
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Abstract
The accurate determination of atom percent.fission (burnup) in nuclear fuel by the fission product-to-fuel ratio method requires the use of accurate fission yields in the calculation.Recent measurements of chain yields in thermal-neutron induced fission of U-235, Pu-239, U-233, and Pu~241 have been made to improve the accuracy of fission yields.Fission yield accuracies of several mass chains used for burnup analysis now approach 2% at the 95%•confidence level.Thermal fission yields published through June 1967 are compiled and evaluated.From this compilation a set of thermal fission yields is pr~pared for use in nuclear fuel .burnupanalysis.
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