B. Goddard, W. Charlton, C. Gariazzo, and P. Peerani,
"A Concept for Quantitative NDA Measurements of Advanced Reprocessing Product Materials,"
Proceedings of GLOBAL 2011
, Makuhar, Japan, December 11-16, 2011.
As new reprocessing methods for spent nuclear fuel are
developed, such as the uranium extraction (UREX) process, methods
using nondestructive assay (NDA) techniques must also be developed
to allow for quantitative measurements of product materials.
Currently developed NDA techniques cannot directly quantify
materials containing U, Np, Pu, and Am. This research
investigates the ability to quantify these actinides in an oxide
form using neutron multiplicity measurements. This technique
assumes that the isotopic composition of the sample is known,
either through gamma spectroscopy or other means. This
measurement technique is based on performing three different
neutron measurements and analyzing their neutron multiplicity
response. The first is a passive measurement of the product
material to determine the effective plutonium-240
(240Pueff) content, self multiplication (M),
and alpha-neutron reaction rate (α). The second is an active,
AmLi (α, n) source, measurement of the product material to
determine the effective 235U content. The third is
an active, AmB (α, n) source, measurement of the product material
to determine the effective 237Np content. The
quantity of Am in the sample can be determined from α.
Simulated results using Monte Carlo N-Particle eXtended (MCNPX)
version 2.6 will illustrate the viability of this technique and its
Associated Project(s):Quantitative NDA Measurements of Advanced Reprocessing Product Materials