Significance and Use
Uranium dioxide is used as a nuclear-reactor fuel. This test method is designed to determine whether the percent uranium and O/U or O/M content meet Specifications C776 and C922.
1. Scope
1.1 This test method applies to the determination of uranium, the oxygen to uranium (O/U) ratio in sintered uranium dioxide pellets, and the oxygen to metal (O/M) ratio in sintered gadolinium oxide-uranium dioxide pellets with a Gd2O3 concentration of up to 12 weight %. The O/M calculations assume that the gadolinium and uranium oxides are present in a metal dioxide solid solution.
1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
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. For specific hazards statements, see Section 8.
2. Referenced Documents (purchase separately)
The documents listed below are referenced within the subject standard but are not provided as part of the standard.
ASTM Standards
C696 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets
C776 Specification for Sintered Uranium Dioxide Pellets
C922 Specification for Sintered Gadolinium Oxide-Uranium Dioxide Pellets
C968 Test Methods for Analysis of Sintered Gadolinium Oxide-Uranium Dioxide Pellets
C1287 Test Method for Determination of Impurities in Nuclear Grade Uranium Compounds by Inductively Coupled Plasma Mass Spectrometry
Keywords
atmospheric equilibration; equilibration; oxygen to metal; oxygen to uranium;Atmospheric equilibration; Equilibration; Gadolinium oxide-uranium dioxide powder/pellets; Oxygen-to-metal (O/M) ratio; Oxygen-to-uranium (O/U) atomic ratio; Sintered uranium dioxide; Uranium;
ICS Code
ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)
DOI: 10.1520/C1430-07R11E01
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Citing ASTM Standards
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