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ASTM C 753 : 2016 : REV A : R2021

Current
Current

The latest, up-to-date edition.

Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
Available format(s)

Hardcopy , PDF

Language(s)

English

Published date

10-22-2021

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

1.2This specification recognizes the presence of reprocessed U 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 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.

1.3This 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.

1.4This specification refers expressly to 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.

1.5The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard.

1.6This 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.

1.7This 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.

Committee
C 26
DocumentType
Standard
Pages
5
PublisherName
American Society for Testing and Materials
Status
Current
Supersedes

ASTM C 1453 : 2019 Standard Test Method for the Determination of Uranium by Ignition and the Oxygen to Uranium (O/U) Atomic Ratio of Nuclear Grade Uranium Dioxide Powders and Pellets
ASTM C 833 : 2017 Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors
ASTM C 1854 : 2017 Standard Test Method for Determination of Hydrogen (total from all sources) in Mixed Oxide ((U, Pu)O<inf>2</inf>) Sintered Pellets by the Inert Gas Fusion Technique Followed by Thermal Conductivity Measurement
ASTM C 1832 : 2021 Standard Test Method for Determination of Uranium Isotopic Composition by Modified Total Evaporation (MTE) Method Using Thermal Ionization Mass Spectrometer
ASTM C 1672 : 2017 Standard Test Method for Determination of Uranium or Plutonium Isotopic Composition or Concentration by the Total Evaporation Method Using a Thermal Ionization Mass Spectrometer
ASTM C 1413 : 2018 Standard Test Method for Isotopic Analysis of Hydrolyzed Uranium Hexafluoride and Uranyl Nitrate Solutions by Thermal Ionization Mass Spectrometry
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ASTM C 1625 : 2019 Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances by Thermal Ionization Mass Spectrometry
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ASTM C 776 : 2017 Standard Specification for Sintered Uranium Dioxide Pellets for Light Water Reactors
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ASTM C 696 : 2019 Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets
ASTM C 1502 : 2016 Standard Test Method for Determination of Total Chlorine and Fluorine in Uranium Dioxide and Gadolinium Oxide
ASTM C 1334 : 2005 : R2016 : EDT 1 Standard Specification for Uranium Oxides with a <sup>235</sup>U Content of Less Than 5 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Dioxide
ASTM C 1347 : 2008 : R2014 : EDT 1 Standard Practice for Preparation and Dissolution of Uranium Materials for Analysis
ASTM C 1853 : 2017 Standard Test Method for The Determination of Carbon (Total) Content in Mixed Oxide ((U, Pu)O<inf>2</inf>) Sintered Pellets by Direct Combustion-Infrared Detection Method
ASTM C 1871 : 2018 : REV A Standard Test Method for Determination of Uranium Isotopic Composition by the Double Spike Method Using a Thermal Ionization Mass Spectrometer
ASTM C 1817 : 2016 Standard Test Method for The Determination of the Oxygen to Metal (O/M) Ratio in Sintered Mixed Oxide ((U, Pu)O<inf>2</inf>) Pellets by Gravimetry
ASTM C 1474 : 2019 Standard Test Method for Analysis of Isotopic Composition of Uranium in Nuclear-Grade Fuel Material by Quadrupole Inductively Coupled Plasma-Mass Spectrometry
ASTM C 1457 : 2018 Standard Test Method for Determination of Total Hydrogen Content of Uranium Oxide Powders and Pellets by Carrier Gas Extraction

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