Review of Axial Burnup Distribution Considerations for Burnup Credit Calculations

Wagner, J.C. ; DeHart, M.D.

Oak Ridge National Laboratory

关键词: Criticality;    Multiplication Factors;    Actinides;    Neutrons;    Fission Products;   

DOI  :  10.2172/763169
RP-ID  :  ORNL/TM-1999/246
RP-ID  :  AC05-96OR22464
RP-ID  :  763169

美国|英语

来源: UNT Digital Library

【 摘 要 】

This report attempts to summarize and consolidate the existing knowledge on axial burnup distribution issues that are important to burnup credit criticality safety calculations. Recently released Nuclear Regulatory Commission (NRC) staff guidance permits limited burnup credit, and thus, has prompted resolution of the axial burnup distribution issue. The reactivity difference between the neutron multiplication factor (keff) calculated with explicit representation of the axial burnup distribution and keff calculated assuming a uniform axial burnup is referred to as the ``end effect.'' This end effect is shown to be dependent on many factors, including the axial-burnup profile, total accumulated burnup, cooling time, initial enrichment, assembly design, and the isotopics considered (i.e., actinide-only or actinides plus fission products). Axial modeling studies, efforts related to the development of axial-profile databases, and the determination of bounding axial profiles are also discussed. Finally, areas that could benefit from further efforts are identified.