/sup 239/Pu decay heat evaluation

Based on recent measurements, a new evaluation for the decay heat from /sup 239/Pu was obtained. The results are important for /sup 239/Pu-fueled fast breeder reactors where decay heat values have previously been obtained from summation calculations. The evaluation was, in part, support for a revised ANS decay heat standard for light water reactors. The same statistical methods used previously in the evaluation of decay heat for the thermal fission of /sup 235/U were used here. The new evaluation is typically a few percent higher than values previously calculated from ENDF/B-IV. Final evaluated uncertainties are approx. 4% (1sigma) and reflect discrepancies in the measurements that are shown to exist. 8 references.