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ASTM C 833 : 2017 : REDLINE

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors

Available format(s)

PDF

Superseded date

04-08-2023

Language(s)

English

Published date

11-01-2017

€67.30
Excluding VAT

CONTAINED IN VOL. 12.01, 2017 Defines finished sintered and ground (U, Pu)O[2] pellets for use in light water reactors.

Committee
C 26
DocumentType
Redline
Pages
5
PublisherName
American Society for Testing and Materials
Status
Superseded
SupersededBy

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 934 : 1985 : R1990 : EDT 1 Guide for Design and Quality Assurance Practices for Nuclear Fuel Rods (Withdrawn 1995)
ASTM C 1474 : 2000 : R2006 : EDT 1 Standard Test Method for Analysis of Isotopic Composition of Uranium in Nuclear-Grade Fuel Material by Quadrupole Inductively Coupled Plasma-Mass Spectrometry
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 1307 : 2015 : REDLINE Standard Test Method for Plutonium Assay by Plutonium (III) Diode Array Spectrophotometry
ASTM C 1474 : 2000 : R2011 Standard Test Method for Analysis of Isotopic Composition of Uranium in Nuclear-Grade Fuel Material by Quadrupole Inductively Coupled Plasma-Mass Spectrometry
ASTM C 1832 : 2016 Standard Test Method for Determination of Uranium Isotopic Composition by the Modified Total Evaporation (MTE) Method Using a Thermal Ionization Mass Spectrometer
ASTM C 1672 : 2017 : REDLINE 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 1871 : 2018 Standard Test Method for Determination of Uranium Isotopic Composition by the Double Spike Method Using a Thermal Ionization Mass Spectrometer
ASTM C 1817 : 2016 : REDLINE 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 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 1625 : 2012 : REDLINE Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances by Thermal Ionization Mass Spectrometry
ASTM C 1168 : 2015 : REDLINE Standard Practice for Preparation and Dissolution of Plutonium Materials for Analysis
ASTM C 1816 : 2016 : REDLINE 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 698 : 2016 : REDLINE Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U, Pu)O<inf>2</inf>)
ASTM C 1474 : 2000 Standard Test Method for Analysis of Isotopic Composition of Uranium in Nuclear-Grade Fuel Material by Quadrupole Inductively Coupled Plasma-Mass Spectrometry
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 1411 : 2014 : REDLINE Standard Practice for The Ion Exchange Separation of Uranium and Plutonium Prior to Isotopic Analysis

ASTM C 1233 : 2015 : REDLINE Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials
ASTM E 105 : 2016 : REDLINE Standard Practice for Probability Sampling of Materials
ASTM C 698 : 2016 : REDLINE Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U, Pu)O<inf>2</inf>)
ASME NQA 1 : 2015 Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015)
CFR 49(PTS100-185) : 0 TRANSPORTATION

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