A.A. Solodov, W.S. Charlton, S. Saavedra, and L. Khodalev,
"The Use of Self-induced XRF to Quantify the Pu Content in MOX Spent Nuclear Fuel,"
Proceedings of the 2010 Annual Meeting of the Institute of Nuclear Materials Management
, Baltimore, MD, July 11-15, 2010.
A number of nondestructive analysis (NDA) techniques are
being evaluated and developed to characterize spent nuclearfuel (SNF), its burnup,
and fissile material content and detect of
material diversion. Oak Ridge National Laboratory and Texas A&M
University are jointly investigating measurements of
fluorescence (XRF) of uranium and
plutonium for quantification of fissile content in SNF. Because
of the radioactive nature of SNF, decay energy is being deposited
in the rod material at a relatively constant rate. That decay
energy leads to self-induced XRF of the uranium and
plutonium atoms in the fuel. These resulting x-rays
are then emitted by the fuel rod and can be
measured in an appropriately designed and implemented instrument. A
previous study demonstrated measurability of the plutonium x-rays
for pressurized water reactor spent fuel with burnups
ranging from 35 to 70 GWd/MTU and the potential application of this
technique as a quantitative assay tool. This paper describes
measurements and analyses that were performed on
oxide lead test assembly rods irradiated at the
Catawba Nuclear Power Plant.
These rods received burnup up to 45 GWd/MT. Fuel rods were measured
using two high-purity germanium detectors (coaxial and planar) for
characterization of fission product ratios and x-rays
uranium and plutonium. Results of data analyses were compared to
burnup code simulations. In the future, there are plans to perform
destructive analysis on measured sections of fuel to determine the
accuracy of the NDA measurements.
Associated Project(s):Development of Advanced Safeguards Measurement Techniques Using the Coupled End-to-End (CETE) Demonstration at ORNL