Active Standard ASTM C1408 | Developed by Subcommittee: C26.05
Book of Standards Volume: 12.01
Historical (view previous versions of standard)
Significance and Use
Uranium dioxide is used as a nuclear-reactor fuel. Gadolinium oxide is used as an additive to uranium dioxide. In order to be suitable for this purpose, these materials must meet certain criteria for impurity content. This test method is designed to determine whether the carbon content meets Specifications C 753
1.1 This test method covers the determination of carbon in nuclear-grade uranium oxide powders and pellets to determine compliance with specifications.
1.2 Gadolinium oxide (Gd2O3) and gadolinium oxide-uranium oxide powders and pellets may also be analyzed using this test method.
1.3 This test method covers the determination of 5 to 500 μg of residual carbon.
1.4 This test method describes an induction furnace carrier gas combustion system equipped with an infrared detector. It may also be applied to a similar instrument equipped with a thermal conductivity detector.
1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.5.1 The preferred system of units is micrograms carbon per gram of sample (μg/g sample) or micrograms carbon per gram of uranium (μg/g U).
1.6 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.
2. Referenced Documents (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.
C753 Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
C776 Specification for Sintered Uranium Dioxide Pellets
C888 Specification for Nuclear-Grade Gadolinium Oxide (Gd2O3) Powder
C922 Specification for Sintered Gadolinium Oxide-Uranium Dioxide Pellets
ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)