J.M. Eigenbrodt, W.S. Charlton, A.A. Solodov,
"Sensitivity Analysis and Benchmarking of Low and Broad Energy Photon Measurements for Spent Nuclear Fuel,"
Proceedings of GLOBAL 2011
, Makuhari, Japan, Dec. 11-16, 2011.
While gamma measurements are a well understood technique for
estimating burn up and cooling time in spent nuclear fuel, only a
few isotopes are currently used and calculations are dependent on
operator declarations. Utilizing a larger set of nuclide
measurements as well as including low energy measurements (around
100 keV) could provide a significant increase in the information
gained from such measurements. Nuclides investigated in this work
include 235U, 238U, 239Pu, 240Pu, 137Cs, 154Eu, 241Am, 155Eu,
149Sm, and 155Gd. Low energy, broad range, and high energy gamma
measurements have been performed on a variety of spent uranium
dioxide and MOX fuel from PWRs. Selected measured fuel locations
have been simulated with Origen, TransLAT, SCALE, and Monteburns to
benchmark each of these programs with destructive analysis results.
Monteburns was identified as the most accurate program for
prediction of isotopes of interest and will be used for future
analysis. Origen was chosen as a quick but relatively accurate
program to perform a preliminary sensitivity analysis of the
effects of fuel parameters (burnup, cooling time, and initial
enrichment) on each nuclide measurement.
Associated Project(s):Development of Advanced Safeguards Measurement Techniques Using the Coupled End-to-End (CETE) Demonstration at ORNL