If you are an ASTM Compass Subscriber and this document is part of your subscription, you can access it for free at ASTM Compass
    ASTM C922 - 21

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

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

    Book of Standards Volume: 12.01


      Format Pages Price  
    PDF 4 $48.00   ADD TO CART
    Hardcopy (shipping and handling) 4 $48.00   ADD TO CART
    Standard + Redline PDF Bundle 8 $56.00   ADD TO CART



    Abstract

    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 (U,Gd)O2 pellets. It applies to (U,Gd)O2 pellets containing uranium (U) of any 235U concentration and any concentration of gadolinium oxide (Gd2O3) for use in nuclear reactors.

    1.2 This specification recognizes the presence of reprocessed U in the fuel cycle and consequently defines isotopic limits for (U,Gd)O2 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 U. 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 (a) provisions for preventing criticality accidents, (b) requirements for health and safety, (c) avoidance of hazards, or (d) shipping precautions and controls. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable 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 70, Title 10, Part 71, and Title 49, Part 173.

    1.4 Units—The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

    1.5 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.

    1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.


    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

    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

    E112 Test Methods for Determining Average Grain Size

    ANSI Standard

    ANSI/ASME NQA-1


    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/C0922-21

    Citation Format

    ASTM C922-21, Standard Specification for Sintered Gadolinium Oxide-Uranium Dioxide Pellets for Light Water Reactors, ASTM International, West Conshohocken, PA, 2021, www.astm.org

    Back to Top