Impact of difference of neutron cross section libraries to isotopic concentration of actinides - 186

Calculated isotopic compositions with several neutron cross section libraries are compared with radiochemical analysis results of MALIBU international program, and the impact of difference of cross section libraries to isotopic compositions are measured. Continuous energy Monte-Carlo burnup code, 'MVP-BURN' is used in the computational calculations to eliminate the approximations both of geometry and of evaluation of effective resonance cross section, and JENDL-3.2, JENDL/AC-2008, ENDF/B-VII.0 and JEFF-3.1 are used in the calculation as incident neutron cross section libraries. In computational calculations, the detail irradiation conditions are considered. For major actinides, uranium and plutonium, the agreement between MALIBU measurement results and calculated results in this work is excellent. The differences are several percent for most of them. For minor actinides, relatively large uncertainty of measurements than for major actinides are given, and for some of them, the difference between MALIBU measurement results and calculated results in this work are several tens percent. Finally, the nuclides with large impact of difference of neutron cross section libraries are discussed for major and minor actinides. (authors)