Initial and Operational Experience for MOX Scrap Measurement Using the PSMC

Year
1997
Author(s)
Howard Menlove - Los Alamos National Laboratory
R.D. McElroy - Canberra Industries Inc.
H. Maruyama - Power Reactor and Nuclear Fuel Dev. Corp.
D. Davidson - Canberra Industries
M. Ishikawa - Power Reactor and Nuclear Fuel Dev. Corp.
Abstract
The Plutonium Scrap Multiplicity Counter (PSMC) is a high efficiency neutron counter designed by Los Alamos National Laboratory for measuring impure samples such as mixed-oxide (MOX) scrap materials. The PSMC is able to accurately measure the plutonium content by using the enhanced multiplicity technique. PNC and Canberra installed two PMSC's at PNC MOX production facility in June 1995.