ASTM C753-04
(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 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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Standards Content (Sample)
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Designation: C 753 – 04
Standard Specification for
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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 (e) 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
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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.
1.2 This specification recognizes the presence of repro-
2. Referenced Documents
cessed uranium in the fuel cycle and consequently defines
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2.1 ASTM Standards:
isotopic limits for commercial grade UO . Such commercial
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B 329 Test Method forApparent Density of Metal Powders
grade UO is defined so that, regarding fuel design and
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and Compounds by the Scott Volumeter
manufacture, the product is essentially equivalent to that made
C 696 Test Methods for Chemical, Mass Spectrometric, and
from unreprocessed uranium. UO falling outside these limits
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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
C 859 Terminology Relating to Nuclear Materials
fuel design.
C 996 Specification for Uranium Hexafluoride Enriched to
1.3 This specification does not include provisions for pre-
235
Less than 5 % U
venting criticality accidents or requirements for health and
C 1233 Practice for Determining Equivalent Boron Con-
safety. Observance of this specification does not relieve the
tents of Nuclear Materials
user of the obligation to be aware of and conform to all
E 11 Specification for Wire-Cloth and Sieves for Testing
international, national, or federal, state, and local regulations
Purposes
pertaining to possessing, shipping, processing, or using source
E 105 Practice for Probability Sampling of Materials
or special nuclear material.
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2.2 ANSI Standard:
1.4 This specification refers expressly to calcined UO
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ANSI/ASME NQA-1 Quality Assurance Requirements for
powder before the addition of any die lubricant, binder, or pore
Nuclear Facility Applications
former. If powder is sold with such additions or prepared as
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2.3 Federal Regulation:
press feed, sampling procedures, allowable impurity contents,
or powder physical requirements may need to be modified by
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agreement between the buyer and the seller.
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
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This specification is under the jurisdiction of ASTM Committee C26 on the ASTM website.
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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.
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CurrenteditionapprovedJune1,2004.PublishedJuly2004.Originallyapproved Available from Standardization Documents Order Desk, DODSSP, Bldg. 4,
in 1973. Last previous edition approved in 1999 as C 753 – 99. Section D, 700 Robbins Ave., Philadelphia, PA 19111-5098.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
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C753–04
236
Code of Federal Regulations, Title 10, Chapter 1, Nuclear seller’s quality assurance records. A U content greater than
Regulatory Commission, Applicable Parts that specified in C 996 for Enriched Commercial Grade UF
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may be agreed between the buyer and the seller since it is not
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3. Terminology
a safety concern.
4.5.2 For UO powder, not having an assay in
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