Scope
1.1 This test method covers the determination of stable fission product 148 Nd in irradiated uranium (U) fuel (with initial plutonium (Pu) content from 0 to 50%) as a measure of fuel burnup (1-3).
1.2 It is possible to obtain additional information about the uranium and plutonium concentrations and isotopic abundances on the same sample taken for burnup analysis. If this additional information is desired, it can be obtained by precisely measuring the spike and sample volumes and following the instructions in Test Method E267.
1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.
