Dependence of Fast Reactor Fuel Burnup Characteristics on Nuclear Data Libraries

Oki, Shigeo ; Jin, Tomoyuki*

Burnup calculation and nuclear-data sensitivity analysis were carried out with respect to the heavy metal composition in fast reactors. The following nuclear data libraries were compared: JEF-2.2, ENDF/B-VI Release 5, JENDL-3.2, and JENDL-3.3. Differences for main heavy metal nuclides (U, U, Pu, Pu, and Pu) were small since the number densities after 1-cycle burnup did not change over 1 or 2% among those libraries. Relatively large differences were found for minor actinide nuclides, especially for U, Np, Am, Am, and curium isotopes. The number densities for these nuclides after burnup showed remarkable library dependence over 5% through 50%. A burnup sensitivity analytical system based on the generalized perturbation theory enabled us to find out quantitatively the causative nuclides and reactions, as well as their energy regions.