Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances
|Publication Date:||27 July 1990|
|ICS Code (Fissile materials and nuclear fuel technology):||27.120.30|
|ICS Code (Radiation measurements):||17.240|
This test method is applicable to the determination of uranium (U) and plutonium (Pu) concentrations and their isotopic abundances (Note 1) in solutions which result from the dissolution of nuclear reactor fuels either before or after irradiation. A minimum sample size of 50 µg of irradiated U will contain sufficient Pu for measurement and will minimize the effects of cross contamination by environment U.
The procedure is applicable to dissolver solutions of uranium fuels containing plutonium, aluminum, stainless steel, or zirconium. Interference from other alloying constituents has not been investigated and no provision has been made in the test method for fuels used in the 232Th-233U fuel cycle.
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.