The determination of ¹²⁹I is not typically requested in nuclear fuel specifications however it is commonly requested for disposal of the spent fuel, or for disposal of excess uranium from national weapon complexes. This practice can provide results of sufficient quality for waste disposal repositories.

1.1 This method covers the determination of iodine-129 (¹²⁹I) in uranium oxide by gamma-ray spectrometry. The method could also be applicable to the determination of ¹²⁹I in aqueous matrices.

1.2 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 to determine the applicability of regulatory limitations prior to use.