ASTM C 833 : 2017
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by
Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors
Hardcopy , PDF
04-08-2023
English
11-01-2017
Committee |
C 26
|
DocumentType |
Standard
|
Pages |
5
|
PublisherName |
American Society for Testing and Materials
|
Status |
Superseded
|
SupersededBy | |
Supersedes |
1.1This specification covers finished sintered and ground (U, Pu)O2 pellets for use in light water reactors. It applies to (U, Pu)O2 pellets containing plutonium additions up to 15 weight % (wt%; that is, 0.15 g Pu / g (U + Pu + Am)).
1.2Pellets produced under this specification are available in four grades.
1.2.1Grade R—240Pu content of (Pu + Am) (that is, g 240Pu / g (Pu + Am)) is at least 19 %.
1.2.2Grade F—240Pu content of (Pu + Am) is at least 7 % and less than 19 %.
1.2.3Grade N1—240Pu content of (Pu + Am) is less than 7 %.
1.2.4Grade N2—240Pu /239Pu does not exceed 0.10.
1.3There is no discussion of or provision for preventing criticality incidents, nor are health and safety requirements, the avoidance of hazards, or shipping precautions and controls discussed. 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, processing, shipping, or using source or special nuclear material. Examples of U.S. government documents are Code of Federal Regulations 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; and Code of Federal Regulations Title 49, Part 173—General Requirements for Shipments and Packaging.
1.4The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.5The following safety hazards 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.
ASTM C 1907 : 2021 | Standard Practice for Preparation of Plutonium Materials by Pyrohydrolysis for Determination of Fluoride, Chloride, or Both |
ASTM C 1832 : 2023 | Standard Test Method for Determination of Uranium Isotopic Composition by Modified Total Evaporation (MTE) Method Using Thermal Ionization Mass Spectrometer |
ASTM C 1411 : 2020 | Standard Practice for The Ion Exchange Separation of Uranium and Plutonium Prior to Isotopic Analysis |
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 1816 : 2016 | Standard Practice for The Ion Exchange Separation of Small Volume Samples Containing Uranium, Americium, and Plutonium Prior to Isotopic Abundance and Content 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 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 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 698 : 2016 | Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U, Pu)O<inf>2</inf>) |
ASTM C 1307 : 2021 | Standard Test Method for Plutonium Assay by Plutonium (III) Diode Array Spectrophotometry |
ASTM C 1868 : 2018 | Standard Practice for Ceramographic Preparation of UO<inf>2</inf> and Mixed Oxide (U,Pu)O<inf>2</inf> Pellets for Microstructural Analysis |
ASTM C 1625 : 2019 | Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances by Thermal Ionization Mass Spectrometry |
ASTM C 1865 : 2018 | Standard Test Method for The Determination of Carbon and Sulfur Content in Plutonium Oxide Powder by the Direct Combustion-Infrared Spectrophotometer |
ASTM C 1168 : 2015 | Standard Practice for Preparation and Dissolution of Plutonium Materials for Analysis |
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 1871 : 2022 | Standard Test Method for Determination of Uranium Isotopic Composition by the Double Spike Method Using a Thermal Ionization Mass Spectrometer |
ASTM C 859 : 2023 | Standard Terminology Relating to Nuclear Materials |
ASTM C 859 : 2014 : REV B | Standard Terminology Relating to Nuclear Materials |
ASTM C 757 : 1990 : R1996 : EDT 1 | Standard Specification for Nuclear-Grade Plutonium Dioxide Powder, Sinterable |
ASTM C 1233 : 2003 | Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials |
ASTM C 1233 : 1998 | Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials |
ASTM C 757 : 2016 : EDT 1 | Standard Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors |
ASTM B 243 : 2022 | Standard Terminology of Powder Metallurgy |
ASTM E 105 : 2021 | Standard Guide for Probability Sampling of Materials |
ASTM C 757 : 2016 : R2021 | Standard Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors |
ASTM C 1233 : 2015 : R2021 | Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials |
ASTM C 859 : 2022 | Standard Terminology Relating to Nuclear Materials |
ASTM C 859 : 2022 : REV A | Standard Terminology Relating to Nuclear Materials |
ASTM B 243 : 2020 | Standard Terminology of Powder Metallurgy |
ASTM C 753 : 2016 : REV A | Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder |
ASTM C 1233 : 2015 | Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials |
ASTM B 243 : 2023 | Standard Terminology of Powder Metallurgy |
ASTM E 105 : 2016 | Standard Practice for Probability Sampling of Materials |
ASTM E 112 : 2013 : R2021 | Standard Test Methods for Determining Average Grain Size |
ASTM E 112 : 2013 | Standard Test Methods for Determining Average Grain Size |
ASTM C 1233 : 2009 | Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials |
ASTM C 753 : 2016 : REV A : R2021 | Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder |
Access your standards online with a subscription
Features
-
Simple online access to standards, technical information and regulations.
-
Critical updates of standards and customisable alerts and notifications.
-
Multi-user online standards collection: secure, flexible and cost effective.