ASTM C753-04(2009)

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
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
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
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.
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
2.1 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
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
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.
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 States.
C 753 – 04 (2009)
2.2 ANSI Standard:
ANSI/ASME NQA-1Quality Assurance Program Requirements for Nuclear Facilities
ANSI/ASME NQA-1 Quality Assurance Requirements for Nuclear Facility Applications
2.3 Federal Regulation:
Code of Federal Regulations, Title 10, Chapter 1, Nuclear Regulatory Commission, Applicable Parts
3. Terminology
3.1 Definitions—Definitions of terms are as given in Terminology C 859.
4. Chemical Requirements
4.1 Uranium Content— The uranium content shall be determined on a basis to be agreed upon between the buyer and seller.
4.2 Oxygen-to-Uranium Ratio (O/U) —The O/U ratio may be specified as agreed upon between the buyer and seller. The
determination of the O/U ratio shall be in accordance with Test Methods C 696 or a demonstrated equivalent.
4.3 Impurity Content— The impurity content shall not exceed the individual element limit specified in Table 1 on a uranium
weight basis. The summation of the contribution of each of the impurity elements listed in Table 1 shall not exceed 1500 µg/gU.
If an element analysis is reported as “less than” a given concentration, this “less than” value shall be used in the determination
of total impurities. If an element analysis is reported as “less than” a given concentration, this “less than” value shall be used in
the determination of total impurities.
4.4 Moisture Content— The moisture content shall not exceed 0.40 g/100 g uranium dioxide (UO ). — The moisture content
shall not exceed 0.40 weight percent of the powder.
4.5 Isotopic Content:
4.5.1 For UO powder with an isotopic content of U between that of natural uranium and 5 %, the isotopic limits of
Specification C 996 shall apply, unless otherwise agreed upon between the buyer and the seller. If the U content is greater than
enriched commercial grade UF requirements, the isotopic analysis requirements of
U content is greater than Enriched Commercial Grade UF
Specification C 996 shall apply.The specific isotopic measurements required by Specification C 996 may be waived, provided that
thesellercandemonstratecompliancewithSpecificationC 996,forinstance,throughtheseller’squalityassurancerecords.A U
content greater then onethan that specified in C 996 for Enriched Commercial gradeGrade UF may be agreed between the buyer
and the seller since it is not a safety concern.
Annual Book of ASTM Standards, Vol 12.01.
Available from American National Standards Institute (ANSI), 25 W. 43rd St., 4th Floor, New York, NY 10036, http://www.ansi.org.
Annual Book of ASTM Standards, Vol 14.02.
Available from Standardization Documents Order Desk, DODSSP, Bldg. 4, Section D, 700 Robbins Ave., Philadelphia, PA 19111-5098, http://www.dodssp.daps.mil.
Available from American National Standards Institute, 11 W. 42nd St., 13th Floor, New York, NY 10036.
5 236
The intent of the C 996 isotope limits is to indicate possible presence of reprocessed UF .Acceptance of UO pellets with U content above that specified for Enriched
6 2
Commercial Grade UF , shall be based on fuel performance evaluation.
TABLE 1 Impurity Elements and Maximum Concentration Limits
Maximum Concentration
Element
Limit of Uranium, µg/gU
Aluminum 250
Carbon 100
Calcium + magnesium 200
Chlorine 100
Chromium 200
Cobalt 100
Copper 250
Fluorine 100
Iron 250
Lead 250
Manganese 250
Molybdenum 250
Nickel 200
Nitrogen 200
Phosphorus 250
Silicon 300
Tantalum 250
A
Thorium 10
A
Thorium 10
Tin 250
Titanium 250
Tungsten 250
Vanadium 250
Zinc 250
A 233
Thorium is primarily of concern because of the reactor production of U.
C 753 – 04 (2009)
4.5.2 For UO powder, not having an assay in the range set forth in 4.5.1, the isotopic requirements shall be as agreed upon
between the buyer and the seller.
4.6 Equivalent Boron Content—For thermal reactor use, the total equivalent boron content (EBC) shall not exceed 4.0 µg/g on
a uranium weight basis. For purpose of EBC calculation B, Gd, Eu, Dy, Sm, and Cd shall be included in addition to elements listed
in Table 1. The method of performing the calculation shall be as indicated in Practice C 1233. For fast reactor use, the above
limitation on EBC does not apply.
4.7 Cleanliness and Workmanship—The powder shall be visually free of foreign material such as metallic particles and oil.
5. Physical Requirements
5.1 Particle Size— Based on visual observation, all of a representative sample of the UO shall pass through a 425-µm (No.
40)standardsieveconformingtoSpecificationE 11.Particlesizedistributionandmethodofdeterminationshallbeasagreedupon
between the buyer and seller. Alternatively, as agreed upon between the buyer and the seller, the fraction not passing through a
425-µm (No. 40) standard sieve shall be reported to the buyer.
5.2 Bulk Density— The bulk density of UO powder will depend on the processing method. Unless otherwise agreed upon
between the buyer and seller, the bulk density shall be a minimum of 0.625 kg/m as determined by Test Method B 329, or an
agreed upon alternative.
NOTE 1—For powder prepared as a press feed, a minimum bulk density of 1.8 g/cm is recommended.
5.3 Sinterability— Test pellets shall be produced and measured in accordance with a sintering performance test agreed upon
between the buyer and seller. A sinterability performance test described in Annex A1Appendix X1 is presented as a guide.
6.Lot Requirements
6. Sampling
6.1 Alot is defined as a quantity of UO powder that is uniform in isotopic, chemical, physical, and sinterability characteristics.
6.2The identity of a lot shall be retained throughout.
6.2 The identity of a lot shall be retained throughout its processing history.
6.3 A powder lot shall form the basis for defining sampling plans used to establish conformance to this specification.
6.4Sampling plans and procedures shall be mutually agreed upon by the buyer and the seller. A suggested sampling procedure
is given in Annex A2.
6.4 Sampling plans and procedures shall be mutually agreed upon by the buyer and the seller. Analytical confirmation of
sampling plans shall be documented as part of the manufacturer’s quality assurance and nuclear materials control and
accountability program.
6.5 UO maybehygroscopicandretainsufficientwaterafterexposuretoamoistatmospheretocausedetectableerrors.Sample,
weigh, and handle the sample under conditions that will ensure that the sample is representative of the lot.
7. Test Methods
7.1 The seller shall test the sample obtained perAnnexA2 to ensure conformance of the powder to the requirements of Sections
4 and 5.
7.1.1 All chemical analyses shall be performed on portions of the representative sample prepared in accordance with Annex
A2.sample. Analytical chemistry methods used shall be in accordance with Test Methods C 696 or demonstrated equivalent
methods agreed upon between the buyer and seller.
7.2 LotAcceptance—Acceptancetestingmaybeperformedbythebuyeroneitherthesampleprovidedbythesellerorasample
taken at the buyer’s plant by sampling one or more individual containers with a thief. Practice E 105 is referenced as a guide.
Acceptance shall be on a lot basis and shall be contingent upon the material properties meeting the requirements of Sections 4
through 6.
7.3 Referee Method—The buyer and seller shall agree to a third party as a referee in the event of a dispute in analytical results.
8. Certification
8.1 The seller shall provide to the buyer documents certifying:
8.1.1 The isotopic content and identity of the starting material lot and
8.1.2 That the powder meets all the requirements of Sections 4 through 6.
8.2 Test data on the following characteristics shall be supplied upon request:
8.2.1 Uranium isotopic content,
8.2.2 Uranium content,
8.2.3 Individual impurity levels,
8.2.4 Moisture content,
8.2.5 Sinterability test results,
8.2.6 O/U ratio,
C 753 – 04 (2009)
8.2.7 Particle size distribution, and
8.2.8 Bulk density.
9. Packaging and Package Marking
9.1 Uranium dioxide powder shall be packaged in sealed containers to prevent loss of material and undue contamination from
air or the container materials. The exact size and method of packaging shall be as agreed upon by the buyer and seller.
9.2 Each container shall bear, as a minimum, a label on the lid and side with the following information:
9.2.1 Seller’s name,
9.2.2 Material in container,
9.2.3 Lot number,
9.2.4 Uranium enrichment,
9.2.5 Gross, tare, net oxide weights,
9.2.6 Uranium weight,
9.2.7 Purchase order number, and
9.2.8 Container ( ) of ( ).
10. Quality Assurance
10.1 QualityAssurance requirements shall be as agreed upon between the buyer and seller when specified in the purchase order.
Code of Federal Regulations, Title 10, Part 50, Appendix B and ANSI/ASME NQA-1 are referenced as guides.
11. Keywords
11.1 nuclear fuel; powder; urania; uranium dioxide
ANNEXES
(Mandatory Information)
APPENDIX
(Nonmandatory Information)
A1.SINTERABILITY TEST X1. SINTERABILITY TEST
A1.1X1.1 Purpose
AX1.1.1 The purpose of the sinterability test is to verify the fabricability of each lot of UO powder. It is not intended to
simulate the buyer’s pellet fabrication process.Asuggested sinterability test follows. powder.Although not required, it is desirable
to simulate the buyer’s pellet fabrication process to improve the predictability of the powder.Asuggested sinterability test follows.
A1.2X1.2 Fabrication of Test Pellets
A1.2.1
X1.2.1 Preparation of Test Pellets —Cold press powder to produce at least four pellets with the addition of an agreed upon
quantity of lubricant or additive, or both, to green pellets within a predetermined density range. The density of each pellet shall
vary no more than 60.5% theoretical density (TD) from the average of the required test pellets. Report the type of pellet press,
density, pressing conditions, due taper, identification of any die lubricant (if used), pressing p
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