A. Stafford, W, S. Charlton, J. White, A. Hoover, and S. Saavedra,
"Spent Nuclear Fuel Self-Induced X-ray Fluorescence Simulations for North Anna and TMI,"
Proceedings of the 2009 Annual Meeting of the Institute of Nuclear Materials Management
, Tucson, AZ, July 12-15, 2009.
The challenge of accurately quantifying the plutonium content
in spent nuclear fuel through passive methods
at reprocessing facilities has been a continuing dilemma. A recent
promising technique being developed is the measurement
of self-induced x-ray fluorescence (XRF) by
uranium and plutonium in spent nuclear fuel. XRF
measurements were performed on North Annaand
Three-Mile-Island-1 (TMI-1) fuel rod segments in a hot
cell at the Coupled-End-To-End (CETE) demonstration facility at Oak
Ridge National Laboratory. In order to verify the plutonium and
uranium x-ray measurement
results, simulations of the fuel and detector
configurations were conducted using TransLAT (a
3-D nuclear fuel depletion software system), Origen2
and MCNP. As an initial step, TransLAT simulations were
conducted to determine the radial distribution of materials and
activities in the spentfuel rod as a function
of fuel burn-up. The uranium to plutonium activity ratios
were then translated to source strength for the plutonium and
uranium x-rays via Origen2 simulations.
These simulations established a radial activity bias for
each fuel case, which were considered during MCNP
analysis. The MCNP simulations were used to predict
detector pulse height spectra for
theNorth Anna and TMI measurements at ORNL.
Results showed good agreement between the simulated and
Associated Project(s):Development of Advanced Safeguards Measurement Techniques Using the Coupled End-to-End (CETE) Demonstration at ORNL