ASTM C1430-07 - 1.2.2007
 
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 C 776 and C 922.

 
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.

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

C922-21

Standard Specification for Sintered Gadolinium Oxide-Uranium Dioxide Pellets for Light Water Reactors

C1287-18

Standard Test Method for Determination of Impurities in Nuclear Grade Uranium Compounds by Inductively Coupled Plasma Mass Spectrometry

C696-19

Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets

C968-19

Standard Test Methods for Analysis of Sintered Gadolinium Oxide-Uranium Dioxide Pellets

C776-17(2022)

Standard Specification for Sintered Uranium Dioxide Pellets for Light Water Reactors