Analysis on factors causing shipper/receiver difference of nuclear material (2). Uncertainty quantification of nuclear material inventories due to uncertainty of nuclear data

Uncertainty quantification of calculated nuclear material inventories in a spent fuel caused by uncertainty in nuclear data were performed for analysis on factors causing Shipper/Receiver Difference (SRD) of nuclear materials. Uncertainty quantification procedures have been developed by adding Shell sequences that can manipulate ORIGEN output files (f71 files) to Sampler and Polaris sequences in the SCALE Code system (Version 6.2.3). This procedure allows us to perform uncertainty quantification using the latest lattice physics code, Polaris, which adapts Method of Characteristics (MoC) as a neutron transport calculation. Cross section and covariance data generated based on the ENDF/B-VII.1 library were used. As a result of analysis in a fuel assembly geometry, uncertainty of the calculated ²³⁵U, ²³⁹Pu and ²⁴¹Pu inventories were found to be 2.3, 2.1 and 2.1%, respectively. Sensitivity analysis were also performed in a fuel rod geometry under various conditions, such as high enriched ²³⁵U, high boron concentration in moderator, high temperature fuel and moderator, etc. These results are expected to be used to explain one of the causes generating SRD by depletion calculations. (author)