ASTM C922 - 14

    Standard Specification for Sintered Gadolinium Oxide-Uranium Dioxide Pellets

    Active Standard ASTM C922 | Developed by Subcommittee: C26.02

    Book of Standards Volume: 12.01

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    This specification covers finished pellets composed of sintered gadolinium oxide-uranium dioxide of any concentration for use in light-water reactors. Materials shall adhere to specified chemical (impurity content, stoichiometry, moisture content, and gadolinium oxide concentration), nuclear (isotopic content), and physical (dimensions, density, homogeneity, integrity, axial and circumferential surface cracks, cylindrical surface chips, pellets ends, cleanliness and workmanship, identification, and irradiation stability) requirements.

    This abstract is a brief summary of the referenced standard. It is informational only and not an official part of the standard; the full text of the standard itself must be referred to for its use and application. ASTM does not give any warranty express or implied or make any representation that the contents of this abstract are accurate, complete or up to date.

    1. Scope

    1.1 This specification is for finished sintered gadolinium oxide-uranium dioxide pellets for use in light-water reactors. It applies to gadolinium oxide-uranium dioxide pellets containing uranium of any 235U concentration and any concentration of gadolinium oxide.

    1.2 This specification recognizes the presence of reprocessed uranium in the fuel cycle and consequently defines isotopic limits for gadolinium oxide-uranium dioxide pellets made from commercial grade UO2. Such commercial grade UO2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unirradiated uranium. UO2 falling outside these limits cannot necessarily be regarded as equivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design.

    1.3 This specification does not include (1) provisions for preventing criticality accidents or (2) requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all international, federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. Examples of U.S. Governmental documents are Code of Federal Regulations (Latest Edition), Title 10, Part 50, Title 10, Part 71, and Title 49, Part 173.

    1.4 The following precautionary caveat pertains only to the technical requirements portion, Section 4, of this specification: 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.

    ANSI Standard

    ANSI/ASME NQA-1 Quality Assurance Requirements for Nuclear Facility Applications

    U.S. Government Documents

    Code of Federal Regulations, Title 10, Part 71, Packaging and Transportation of Radioactive Material

    Code of Federal Regulations, Title 49, Part 173, Shippers--General Requirements for Shipments and Packagings

    Code of Federal Regulations (Latest Edition), Titl Domestic Licensing of Production and Utilization Facilities

    Regulatory Guide 1.126, An Acceptable Model and Related Statistical Methods for the Analysis of Fuel Densification, current version Available from U.S. Nuclear Regulatory Commission, Washington, DC 20555. Attention: Director, Division of Document Control,

    ASTM Standards

    C753 Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder

    C859 Terminology Relating to Nuclear Materials

    C888 Specification for Nuclear-Grade Gadolinium Oxide (Gd2O3) Powder

    C968 Test Methods for Analysis of Sintered Gadolinium Oxide-Uranium Dioxide Pellets

    C996 Specification for Uranium Hexafluoride Enriched to Less Than 5 %235U

    E105 Practice for Probability Sampling of Materials

    ICS Code

    ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)

    UNSPSC Code

    UNSPSC Code 15131500(Nuclear fuel)

    Referencing This Standard
    Link Here
    Link to Active (This link will always route to the current Active version of the standard.)

    DOI: 10.1520/C0922-14

    Citation Format

    ASTM C922-14, Standard Specification for Sintered Gadolinium Oxide-Uranium Dioxide Pellets, ASTM International, West Conshohocken, PA, 2014,

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