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ASTM C 1008 : 1999 : R2008

Withdrawn
Withdrawn

A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.

Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets—Fast Reactor Fuel (Withdrawn 2014)
Available format(s)

Hardcopy , PDF

Withdrawn date

05-20-2014

Language(s)

English

Published date

01-01-2008

CONTAINED IN VOL. 12.01, 2012 Describes finished sintered (uranium-plutonium) dioxide pellets. It applies to (uranium-plutonium) dioxide pellets containing plutonium additions in the range from 10 to 40 weight percent and uranium of any [235]U content.

1.1 This specification is for finished sintered (uranium-plutonium) dioxide pellets. It applies to (uranium-plutonium) dioxide pellets containing plutonium additions in the range from 10 to 40 weight % and uranium of any 235U content. The isotopic composition of the plutonium component will be as normally produced by in-reactor neutron irradiation of uranium having less than 5 % 235U or by in-reactor neutron irradiation of recycled plutonium mixed with uranium.

1.2 This specification does not include (1) provisions for preventing criticality accidents or (2) 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 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; Title 10, Part 71 Packaging and Transportation of Radioactive Material; and Title 49, Part 173 General Requirements for Shipments and Packaging.

1.3 The 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.

Committee
C 26
DocumentType
Standard
Pages
4
ProductNote
Reconfirmed 2008
PublisherName
American Society for Testing and Materials
Status
Withdrawn
Supersedes

ASTM C 1411 : 2014 Standard Practice for The Ion Exchange Separation of Uranium and Plutonium Prior to Isotopic Analysis
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 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 1625 : 2012 Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances by Thermal Ionization Mass Spectrometry

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)
ASTM C 1204 : 2014 : REDLINE Standard Test Method for Uranium in Presence of Plutonium by Iron(II) Reduction in Phosphoric Acid Followed by Chromium(VI) Titration

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