B. Goddard, W.S. Charlton, C. Gariazzo, P. Peerani,
"A Concept for Quantitative NDA MOX Measurements Using Only Neutron Radiation,"
Proceedings of the INMM 52nd Annual Meeting
, Palm Desert, CA, July 17-21, 2011.
There is a desire in the world to reduce the quantity of Pu in
storage by burning it as mixed oxide (MOX) fuel in nuclear
reactors. For safeguards reasons, the masses of both the
235U and Pu in MOX fuel must be quantified, preferably
using non-destructive assay (NDA) techniques. Current NDA
techniques require both gamma ray and neutron measurements to be
performed. This research investigates the ability to quantify the
235U and Pu content of MOX fuel using only neutron
measurements. This would reduce the amount of equipment needed and
subsequently the cost required to conduct the measurement. This
measurement technique is based on performing three different
neutron measurements and analyzing their neutron multiplicity
response. The first measurement is a passive measurement of a
252Cf standard to determine the detector efficiency (ε).
The second measurement, in a passive configuration, will determine
the effective plutonium-240 (240Pueff)
content, self multiplication (M), and alpha-neutron reaction rate
(α). The third measurement, in an active configuration using
interrogation neutrons from an Am-Li alpha neutron source, will
determine the effective plutonium-239
(239Pueff) content and 235U
content. Simulated and measured results will illustrate the
viability of this technique and its practical limitations.
Associated Project(s):Quantitative NDA Measurements of Advanced Reprocessing Product Materials