ASTM C922-00
Historical Standard: ASTM C922-00 Standard Specification for Sintered Gadolinium Oxide-Uranium Dioxide Pellets
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Translated Standard: Russian
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ASTM C922
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 235 U 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 UO 2 . Such commercial grade UO 2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unreprocessed uranium. UO 2 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 on 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.
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
ANSI Standard
ANSI/ASMENQA-1 Quality Assurance Requirements for Nuclear Facility ApplicationsU.S. Government Documents
RegulatoryGuideNUREG An Acceptable Model and Related Statistical Methods for the Analysis of Fuel Densification, Rev. 1 March 1978 Available form U.S. Nuclear Regulatory Commission, Washington, DC 20555. Attention: Director, Division of Document Control.Keywords
burnable poison; gadolinia; nuclear fuel; nuclear fuel pellets; urania ; uranium dioxide; Burnable poison; Gadolinia; Gadolinium oxide-uranium dioxide powder/pellets; Nuclear fuel pellets; Nuclear materials/applications--specifications; Urania ;
ICS Code
ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)
DOI: 10.1520/C0922-00
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