ASTM-C1348:2008 Edition
$40.63
C1348-01(2008) Standard Specification for Blended Uranium Oxides with 235U Content of Less Than 5 % for Direct Hydrogen Reduction to Nuclear Grade Uranium Dioxide
Published By | Publication Date | Number of Pages |
ASTM | 2008 | 5 |
ASTM C1348-01-Reapproved2008
Withdrawn Standard: Standard Specification for Blended Uranium Oxides with 235U Content of Less Than 5 % for Direct Hydrogen Reduction to Nuclear Grade Uranium Dioxide (Withdrawn 2013)
ASTM C1348
Scope
1.1 This specification covers blended uranium trioxide (UO3), U3O8, or mixtures of the two, powders that are intended for conversion into a sinterable uranium dioxide (UO2) powder by means of a direct reduction process. The UO2 powder product of the reduction process must meet the requirements of Specification C 753 and be suitable for subsequent UO2 pellet fabrication by pressing and sintering methods. This specification applies to uranium oxides with a 235U enrichment less than 5 %.
1.2 This specification includes chemical, physical, and test method requirements for uranium oxide powders as they relate to the suitability of the powder for storage, transportation, and direct reduction to UO2 powder. This specification is applicable to uranium oxide powders for such use from any source.
1.3 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents, for health and safety, or for shipping. Observance of this specification does not relieve the user of the obligation to conform to all international, national, state, and local regulations for processing, shipping, or any other way of using uranium oxide powders (see 2.2 and 2.3).
1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
1.5 The following safety hazards caveat pertains only to the test methods portion of the annexes in 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.
Keywords
conversion; nuclear fuel; reduction; uranium dioxide; uranium oxide ^INDEX TERMS: Blended uranium oxides; Conversion; Nuclear fuels (reactor)–specifications; Nuclear materials/applications–specifications; Reduction; Sinterability; Uranium–specifications; Uranium dioxide; Uranium oxide (U3O8); Uranium trioxide
ICS Code
ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)
DOI: 10.1520/C1348-01R08
PDF Catalog
PDF Pages | PDF Title |
---|---|
1 | Scope Referenced Documents |
2 | Terminology Isotopic Content Physical and Chemical Requirements TABLE 1 |
3 | Lot Requirements Test Methods Certification Packaging and Marking Quality Assurance Keywords A1. REDUCTION AND SINTERABILITY TESTS A1.1 Purpose A1.2 Reduction to UO2 A1.3 Fabrication of the Test Pellets |
4 | A1.4 Density Determination A1.5 Sintered Pellet Performance Test A2. SAMPLING A2.1 A2.2 A2.3 A2.4 A2.5 A2.6 A2.7 A2.8 |