Progress on Establishing the Feasibility of Lead Slowing Down Spectroscopy for Direct Measurement of Plutonium in Used Fuel

Year
2011
Author(s)
Denis Beller - University of Nevada-Las Vegas
Sonya Bowyer - Pacific Northwest National Laboratory
A. Gavron - Los Alamos National Laboratory
Kevin K. Anderson - Pacific Northwest National Laboratory
C.J. Gesh - Pacific Northwest National Laboratory
L. Eric Smith - Pacific Northwest National Laboratory
Jon Kulisek - Pacific Northwest National Laboratory
Andy Casella - Pacific Northwest National Laboratory
M. Devlin - Los Alamos National Laboratory
J.M. O’Donnell - Los Alamos National Laboratory
Yaron Danon - Rensselaer Polytechnic Institute
Bjorn Becker - Rensselaer Polytechnic Institute
Abstract
Developing a method for the accurate, direct, and independent assay of the fissile isotopes in bulk materials (such as used fuel) of 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 continues to support a multi-institutional collaboration to address the feasibility of Lead Slowing Down Spectroscopy (LSDS) as 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. An LSDS is comprised of a stack of lead (typically 1-6 m 3 ) in which materials to be measured are placed in the lead and a pulse of neutrons is injected. The neutrons in this pulse lose energy due to inelastic and (subsequently) elastic scattering and the average energy of the neutrons decreases as the time increases by a well-defined relationship. In the interrogation energy region (~0.1-1000 eV) the neutrons have little energy spread (~30%) about the average neutron energy. Due to this characteristic, the energy of the (assay) neutrons can then be determined by measuring the time elapsed since the neutron pulse. By measuring the induced fission neutrons emitted from the used fuel, it is possible to determine isotopic-mass content by unfolding the unique structure of isotopic resonances across the interrogation energy region. This paper will present efforts on the development of time-spectral analysis algorithms, fast neutron detector advances, and validation and testing measurements.