ASTM C922-21 - 1.1.2021
 
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?UnitsThe 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

C753-16a(2021)

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

C859-24

Standard Terminology Relating to Nuclear Materials

C888-18

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

C968-19

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

C996-20

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

E105-21

Standard Guide for Probability Sampling of Materials

Code of Federal Regulations (Latest Edition), Title 10, Part 50,

Domestic Licensing of Production and Utilization Facilities

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

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, http://www.nrc.gov.

ANSI/ASME NQA-1

Quality Assurance Requirements for Nuclear Facility Applications