ASTM C1817-15 - 1.6.2015
 
Significance and Use

5.1 MOX is used as a nuclear-reactor fuel. This test method is designed to determine whether the O/M ratio meets the requirements of the fuel specification. Examples for establishing a fuel specification are given in Specification C833.

5.2 This method is suitable for all sintered MOX pellets containing up to 10 weight % PuO2 when the UO2 and PuO2 meet the requirements of Specifications C753 and C757.

 
1. Scope

1.1 This practice is an alternative method to Test Method C698 for the determination of the oxygen-to-metal atom ratio (O/M) in sintered mixed oxide fuel (MOX) pellets. The method presented in Test Method C698 is a one-step thermogravimetric method for determining O/M ratio in sintered MOX powders and pellets. As stated in Test Method C698, thermogravimetric methods using a two-step heating cycle are also satisfactory (1, 2).2 The method presented in this test method is a two-step heating cycle method. This test method is applicable to sintered MOX pellets containing up to 10 weight percent PuO2.

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.

 
2. Referenced Documents

C757-16(2021)

Standard Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors

C833-23

Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors

Nuclear Fuel TechnologyDetermination of the O/M Ratio in MOX PelletsGravimetric MethodFirst Edition

D1356-26

Standard Terminology Relating to Sampling and Analysis of Atmospheres

D1193-24

Standard Specification for Reagent Water

C1672-23

Standard Test Method for Determination of the Uranium, Plutonium or Americium Isotopic Composition or Concentration by the Total Evaporation Method Using a Thermal Ionization Mass Spectrometer

C1068-21

Standard Guide for Qualification of Measurement Methods by a Laboratory Within the Nuclear Industry

C859-26

Standard Terminology Relating to Nuclear Materials

C753-16a(2021)

Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder (Includes all amendments and changes 10/22/2021).

C698-24

Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U, Pu)O2)