Lead Slowing-Down Spectrometry for Spent Fuel Assay: FY11 Status Report Page: 6 of 39
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Executive Summary
Developing a method for the accurate, direct, and independent assay of the fissile isotopes in
bulk materials (such as used fuel) from next-generation domestic nuclear fuel cycles is a goal of
the Office of Nuclear Energy, Fuel Cycle R&D, Material Protection and Control Technology
(MPACT) Campaign. To meet this goal, MPACT supports a multi-institutional collaboration to
study the feasibility of Lead Slowing Down Spectroscopy (LSDS). This technique is an active
nondestructive assay method that has the potential to provide independent, direct measurement
of Pu and U isotopic masses in used fuel with an uncertainty considerably lower than the
approximately 10% typical of today's confirmatory assay methods. This document is a
progress report for FY2011 collaboration activities.
Progress made by the collaboration in FY2011 continues to indicate the promise of LSDS
techniques applied to used fuel. PNNL developed an empirical model based on calibration of the
LSDS to responses generated from well-characterized used fuel. The empirical model
demonstrated the potential for the direct and independent assay of the sum of the masses of 239Pu
and 241Pu to within approximately 3% over a wide used fuel parameter space. Similar results
were obtained using a perturbation approach developed by LANL. Benchmark measurements
have been successfully conducted at LANL and at RPI using their respective LSDS instruments.
The ISU and UNLV collaborative effort is focused on the fabrication and testing of prototype
fission chambers lined with ultra-depleted 238U and 232Th, and uranium deposition on a stainless
steel disc.
In FY2012, the collaboration plans a broad array of activities. PNNL will focus on optimizing
its empirical model and minimizing its reliance on calibration data, as well as continuing efforts
towards developing an analytical model. Additional measurements are planned at LANL and
RPI. LANL measurements will include a Pu sample, which is expected to provide more counts
at longer slowing-down times to help identify discrepancies between experimental data and
MCNPX simulations. RPI measurements will include the assay of an entire fresh fuel assembly
for the study of self-shielding effects as well as the ability to detect diversion by detecting a
missing fuel pin in the fuel assembly. The development of threshold neutron sensors will
continue, and UNLV will calibrate existing ultra-depleted uranium deposits at ISU.iii
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Warren, Glen A.; Casella, Andrew M.; Haight, R. C.; Anderson, Kevin K.; Danon, Yaron; Hatchett, D. et al. Lead Slowing-Down Spectrometry for Spent Fuel Assay: FY11 Status Report, report, August 1, 2011; Richland, Washington. (https://digital.library.unt.edu/ark:/67531/metadc845295/m1/6/: accessed April 25, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.