ASTM C753-16
(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 UO2 powder. It applies to UO2 powder containing uranium (U) 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 U 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 U. 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 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 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
1.6 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 −16
StandardSpecification 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 standard for sinterable
uranium dioxide (UO ) powder. It recognizes the diversity of manufacturing methods by which UO
2 2
powders are produced and the many special requirements for chemical and physical characterization
that may be applicable for a particular fuel pellet manufacturing process or imposed by the end user
of the powder in a specific reactor system. It is, therefore, anticipated that the buyer may supplement
this specification with more stringent or additional requirements for specific applications.
1. Scope 1.5 The values stated in SI units are to be regarded as the
standard. The values given in parentheses are for information
1.1 This specification covers nuclear-grade, sinterable UO
2
only.
powder. It applies to UO powder containing uranium (U) of
2
235
1.6 This standard does not purport to address all of the
any U concentration in the production of nuclear fuel pellets
safety concerns, if any, associated with its use. It is the
for use in nuclear reactors.
responsibility of the user of this standard to establish appro-
1.2 This specification recognizes the presence of repro-
priate safety and health practices and determine the applica-
cessed U in the fuel cycle and consequently defines isotopic
bility of regulatory requirements prior to use.
limits for commercial grade UO . Such commercial grade UO
2 2
2. Referenced Documents
is defined so that, regarding fuel design and manufacture, the
2
product is essentially equivalent to that made from unrepro-
2.1 ASTM Standards:
cessed U. UO falling outside these limits cannot necessarily
2 B243 Terminology of Powder Metallurgy
beregardedasequivalentandmaythusneedspecialprovisions
B329 Test Method for Apparent Density of Metal Powders
at the fuel fabrication plant or in the fuel design.
and Compounds Using the Scott Volumeter
C696 Test Methods for Chemical, Mass Spectrometric, and
1.3 This specification does not include provisions for pre-
Spectrochemical Analysis of Nuclear-Grade Uranium Di-
venting criticality accidents or requirements for health and
oxide Powders and Pellets
safety. Observance of this specification does not relieve the
C859 Terminology Relating to Nuclear Materials
user of the obligation to be aware of and conform to all
C996 Specification for Uranium Hexafluoride Enriched to
international, national, or federal, state, and local regulations
235
Less Than 5 % U
pertaining to possessing, shipping, processing, or using source
C1233 Practice for Determining Equivalent Boron Contents
or special nuclear material.
of Nuclear Materials
1.4 This specification refers expressly to UO powder be-
2
E11 Specification for Woven Wire Test Sieve Cloth and Test
fore the addition of any die lubricant, binder, or pore former. If
Sieves
powder is sold with such additions or prepared as press feed,
E105 Practice for Probability Sampling of Materials
3
sampling procedures, allowable impurity contents, or powder
2.2 ASME Standard:
physical requirements may need to be modified by agreement
ASME NQA-1 QualityAssurance Requirements for Nuclear
between the buyer and the seller.
Facility Applications
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
1
This specification is under the jurisdiction of ASTM Committee C26 on contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel Standards volume information, refer to the standard’s Document Summary page on
and Fertile Material Specifications. the ASTM website.
3
Current edition approved Feb. 1, 2016. Published March 2016. Originally Available from American Society of Mechanical Engineers (ASME), ASME
approved in 1973. Last previous edition approved in 2009 as C753 – 04 (2009). International Headquarters, Two Park Ave., New York, NY 10016-5990, http://
DOI: 10.1520/C0753-16. www.asme.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
C753−16
4
TABLE 2 Additional Impurity Elements
2.3 Federal Regulation:
Code of Federal Regulations, Title 10, Chapter 1, Nuclear Element
Beryllium (Be) Manganese (Mn)
Regulatory Commission, Applicable Parts
Bismuth (Bi) Niobium (Nb)
Boron (B) Potassiu
...
This document is not an ASTM standard and is intended only to provide the user of an ASTM 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 − 04 (Reapproved 2009) C753 − 16
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 specificationstandard
for sinterable uranium dioxide (UO ) powder. It recognizes the diversity of manufacturing methods by
2
which uraniumUO dioxide powders are produced and the many special requirements for chemical
2
and physical characterization which may be that may be applicable for a particular fuel pellet
manufacturing process or imposed by the end useuser of the powder in a specific reactor system. It is,
therefore, anticipated that the buyer may supplement this specification with more stringent or
additional requirements for specific applications.
1. Scope
1.1 This specification covers nuclear-grade, sinterable uranium dioxide (UOUO ) powder. It applies to uraniumUO dioxide
2 2
235
powder containing uranium (U) of any U concentration in the production of nuclear fuel pellets for use in nuclear reactors.
1.2 This specification recognizes the presence of reprocessed uraniumU 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
2 2
product is essentially equivalent to that made from unreprocessed uranium.U. UO falling outside these limits cannot necessarily
2
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 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, allowable impurity contents, or powder
physical requirements may need to be modified by agreement between the buyer and the seller.
1.5 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
1.6 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.
2. Referenced Documents
2
2.1 ASTM Standards:
B243 Terminology of Powder Metallurgy
B329 Test Method for Apparent Density of Metal Powders and Compounds Using the Scott Volumeter
C696 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide
Powders and Pellets
C859 Terminology Relating to Nuclear Materials
235
C996 Specification for Uranium Hexafluoride Enriched to Less Than 5 % U
C1233 Practice for Determining Equivalent Boron Contents of Nuclear Materials
1
This specification is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel and Fertile
Material Specifications.
Current edition approved June 1, 2009Feb. 1, 2016. Published July 2009March 2016. Originally approved in 1973. Last previous edition approved in 20042009 as
C753 – 04.C753 – 04 (2009). DOI: 10.1520/C0753-04R09.10.1520/C0753-16.
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 the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
C753 − 16
E11 Specification for Woven Wire Test Sieve Cloth and Test Sieves
E105 Practice for Probability Sampling of Materials
3
2.2 ANSIASME Standard:
ANSI/ASMEA
...
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