ASTM C753-04(2009)
(Specification)Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
ABSTRACT
This specification covers nuclear-grade, sinterable uranium dioxide (UO2) powder and applies to uranium dioxide powder containing uranium of any 235U concentration in the production of nuclear fuel pellets for use in nuclear reactors. This specification refers expressly to calcined UO2 powder before the addition of any die lubricant, binder, or pore former, and defines isotopic limits for commercial grade UO2 so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unreprocessed uranium and. Provisions for preventing criticality accidents or requirements for health and safety are not included in this specification. The powder shall conform to the specified chemical requirements including uranium content, oxygen-to-uranium ratio, impurity content (such as aluminum, carbon, calcium and magnesium, chlorine, fluorine, iron, lead, manganese, molybdenum, nickel, nitrogen, phosphorus, silicon, tantalum, thorium, tin, titanium, tungsten, vanadium, and zinc), moisture content, isotopic content, equivalent boron content, and cleanliness and workmanship. The powder shall also meet the specified physical requirements including particle size, bulk density, and sinterability. Sampling requirements for the test specimen and the test methods for chemical analysis and acceptance testing are detailed.
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.
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Designation:C753 −04(Reapproved 2009)
Standard Specification for
1
Nuclear-Grade, Sinterable Uranium Dioxide Powder
This standard is issued under the fixed designation C753; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
INTRODUCTION
This specification is intended to provide the nuclear industry with a general specification for
sinterable uranium dioxide powder. It recognizes the diversity of manufacturing methods by which
uranium dioxide powders are produced and the many special requirements for chemical and physical
characterization which may be imposed by the end use of the powder in a specific reactor system. It
is,therefore,anticipatedthatthebuyermaysupplementthisspecificationwithadditionalrequirements
for specific applications.
1. Scope 1.5 This standard does not purport to address all of the
safety concerns, if any, associated with its use. It is the
1.1 This specification covers nuclear-grade, sinterable ura-
responsibility of the user of this standard to establish appro-
nium dioxide (UO ) powder. It applies to uranium dioxide
2
235 priate safety and health practices and determine the applica-
powder containing uranium of any U concentration in the
bility of regulatory requirements prior to use.
production of nuclear fuel pellets for use in nuclear reactors.
2. Referenced Documents
1.2 This specification recognizes the presence of repro-
2
cessed uranium in the fuel cycle and consequently defines
2.1 ASTM Standards:
isotopic limits for commercial grade UO . Such commercial
2
B329 Test Method for Apparent Density of Metal Powders
grade UO is defined so that, regarding fuel design and
2 and Compounds Using the Scott Volumeter
manufacture, the product is essentially equivalent to that made
C696 Test Methods for Chemical, Mass Spectrometric, and
from unreprocessed uranium. UO falling outside these limits
2 Spectrochemical Analysis of Nuclear-Grade Uranium Di-
cannot necessarily be regarded as equivalent and may thus
oxide Powders and Pellets
need special provisions at the fuel fabrication plant or in the
C859 Terminology Relating to Nuclear Materials
fuel design.
C996 Specification for Uranium Hexafluoride Enriched to
235
Less Than 5 % U
1.3 This specification does not include provisions for pre-
C1233 Practice for Determining Equivalent Boron Contents
venting criticality accidents or requirements for health and
of Nuclear Materials
safety. Observance of this specification does not relieve the
E11 Specification for Woven Wire Test Sieve Cloth and Test
user of the obligation to be aware of and conform to all
Sieves
international, national, or federal, state, and local regulations
E105 Practice for Probability Sampling of Materials
pertaining to possessing, shipping, processing, or using source
3
2.2 ANSI Standard:
or special nuclear material.
ANSI/ASME NQA-1 Quality Assurance Requirements for
1.4 This specification refers expressly to calcined UO
2
Nuclear Facility Applications
powder before the addition of any die lubricant, binder, or pore
4
2.3 Federal Regulation:
former. If powder is sold with such additions or prepared as
Code of Federal Regulations, Title 10, Chapter 1, Nuclear
press feed, sampling procedures, allowable impurity contents,
Regulatory Commission, Applicable Parts
or powder physical requirements may need to be modified by
agreement between the buyer and the seller.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Standards volume information, refer to the standard’s Document Summary page on
1
This specification is under the jurisdiction of ASTM Committee C26 on the ASTM website.
3
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
and Fertile Material Specifications. 4th Floor, New York, NY 10036, http://www.ansi.org.
4
CurrenteditionapprovedJune1,2009.PublishedJuly2009.Originallyapproved Available from Standardization Documents Order Desk, DODSSP, Bldg. 4,
in 1973. Last previous edition approved in 2004 as C753 – 04. DOI: 10.1520/ Section D, 700 Robbins Ave., Philadelphia, PA 19111-5098, http://
C0753-04R09. www.dodssp.daps.mil.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
C753−04 (2009)
236
3. Terminology seller’s quality assurance records. A U content greater than
that specified in C996 for Enriched Commercial Grade UF
6
3.1 Definitions—Definitions of terms ar
...
This document is not anASTM standard and is intended only to provide the user of anASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation:C753–99 Designation: C 753 – 04 (Reapproved 2009)
Standard Specification for
1
Nuclear-Grade, Sinterable Uranium Dioxide Powder
This standard is issued under the fixed designation C 753; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
INTRODUCTION
This specification is intended to provide the nuclear industry with a general specification for
sinterable uranium dioxide powder. It recognizes the diversity of manufacturing methods by which
uranium dioxide powders are produced and the many special requirements for chemical and physical
characterization which may be imposed by the end use of the powder in a specific reactor system. It
is,therefore,anticipatedthatthebuyermaysupplementthisspecificationwithadditionalrequirements
for specific applications.
1. Scope
1.1 This specification covers nuclear-grade, sinterable uranium dioxide (UO ) powder. It applies to uranium dioxide powder
2
235
containing uranium of any U concentration for use in nuclear reactors. U 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 UO . Such commercial grade UO is defined so that, regarding fuel design and manufacture, the product is
2 2
essentially equivalent to that made from unreprocessed uranium. UO falling outside these limits cannot necessarily be regarded
2
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.
Observanceofthisspecificationdoesnotrelievetheuseroftheobligationtobeawareofandconformtoallinternational,national,
or federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material.
1.4Special tests and procedures are given in Annex A1.
1.5This specification refers expressly to UO
1.4 This specification refers expressly to calcined UO powder before the addition of any die lubricant, binder, or pore former.
2
If powder is sold with such additions or prepared as press feed, sampling procedures or, allowable impurity contents, or both,
powder physical requirements may need to be modified by agreement between the buyer and the seller.
1.61.5 The following safety hazards caveat pertains to the test methods portion in the annexes 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 limitationsre-
quirements prior to use.
2. Referenced Documents
2
2.1 ASTM Standards:
B 329 Test Method forApparent Density of Metal Powders of Refractory Metals and Compounds byUsing the ScottVolumeter
C 696 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide
Powders and Pellets
C 859 Terminology Relating to Nuclear Materials
235
C 996 Specification for Uranium Hexafluoride Enriched to Less than 5% Than 5 % U
C 1233 Practice for Determining Equivalent Boron Contents of Nuclear Materials
E11 Specification for Wire-Cloth Sieves for Testing Purposes Specification for Woven Wire Test Sieve Cloth and Test Sieves
E 105 Practice for Probability Sampling ofOf Materials
1
This specification is under the jurisdiction of ASTM Committee C-26 C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel and
Fertile Material Specifications.
Current edition approved June 10, 1999. Published September 1999. Originally published as C753–73. Last previous edition C753–94.
Current edition approved June 1, 2009. Published July 2009. Originally approved in 1973. Last previous edition approved in 2004 as C 753 – 04.
2
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
, Vol 02.05.volume information, refer to the standard’s Document Summary page on the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United St
...
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