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ASTM-C753 2009

$35.75

C753-04(2009) Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder

Published By Publication Date Number of Pages
ASTM 2009 4
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ASTM C753-04-Reapproved2009

Historical Standard: Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder

ASTM C753

Scope

1.1 This specification covers nuclear-grade, sinterable uranium dioxide (UO2) powder. It applies to uranium dioxide powder containing uranium of any 235U concentration in the production of nuclear fuel pellets for use in nuclear reactors.

1.2 This specification recognizes the presence of reprocessed uranium in the fuel cycle and consequently defines isotopic limits for 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 unreprocessed 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 provisions for preventing criticality accidents or 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, national, or federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material.

1.4 This specification refers expressly to calcined UO2 powder before the addition of any die lubricant, binder, or pore former. If powder is sold with such additions or prepared as press feed, sampling procedures, allowable impurity contents, or powder physical requirements may need to be modified by agreement between the buyer and the seller.

1.5 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 requirements prior to use.

Keywords

nuclear fuel; powder; urania; uranium dioxide; Performance–nuclear materials/applications; Sinterability test; Urania; Uranium–specifications; Uranium dioxide powder (sinterable); Nuclear fuels (reactor)–specifications; Nuclear materials/applications–specifications

ICS Code

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

DOI: 10.1520/C0753-04R09

PDF Catalog

PDF Pages PDF Title
1 Scope
Referenced Documents
2 Terminology
Chemical Requirements
Physical Requirements
Sampling
TABLE 1
3 Test Methods
Certification
Packaging and Package Marking
Quality Assurance
Keywords
X1. SINTERABILITY TEST
X1.1 Purpose
X1.2 Fabrication of Test Pellets
4 X1.3 Density Determination
X1.4 Sintered Pellet Performance Test
ASTM-C753 2009
$35.75