Validation Work to Support the Idaho National Engineering and Environmental211 Laboratory Calculational Burnup Methodology Using Shippingport Light Water 211 Breeder Reactor (LWBR) Spent Fuel Assay Data

摘要

Six uranium isotopes and fourteen fission product isotopes were calculated on a211u001emass basis at end-of-life (EOL) conditions for three fuel rods from different 211u001eLight Water Breeder Reactor (LWBR) measurements. The three fuel rods evaluated 211u001ehere were taken from an LWBR seed module, a standard blanket module, and a 211u001ereflector (Type IV) module. The calculated results were derived using a depletion 211u001emethodology previously employed to evaluate many of the radionuclide inventories 211u001efor spent nuclear fuels at the Idaho National Engineering and Environmental 211u001eLaboratory. The primary goal of the calculational task was to further support the 211u001evalidation of this particular calculational methodology and its application to 211u001ediverse reactor types and fuels. Result comparisons between the calculated and 211u001emeasured mass concentrations in the three rods indicate good agreement for the 211u001ethree major uranium isotopes (U-233, U-234, U-235) with differences of less than 211u001e20%. For the seed and standard blanket rod, the U-233 and U-234 differences were 211u001ewithin 5% of the measured values (these two isotopes alone represent greater than 211u001e97% of the EOL total uranium mass). For the major krypton and xenon fission 211u001eproduct isotopes, differences of less than 20% and less than 30% were observed, 211u001erespectively. In general, good agreement was obtained for nearly all the measured 211u001eisotopes. For these isotopes exhibiting significant differences, possible 211u001eexplanations are discussed in terms of measurement uncertainty, complex 211u001etransmutations, etc.