ASTM C833-01(2008)

Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets

ABSTRACT
This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. The diversity of manufacturing methods shall be recognized by which uranium-plutonium dioxide pellets are produced and the many special requirements for chemical and physical characterization that may be imposed by the operating conditions to which the pellets will be subjected in specific reactor systems. The following are different chemical requirements that shall be determined: uranium content, plutonium content, impurity content, stoichiometry, moisture content, gas content, and americium-241 content. Nuclear requirements such as isotopic content, plutonium equivalent at a given date, equivalent boron content, and reactivity shall also be determined. Physical properties of the pellets like dimensions, density, grain size, pore morphology, plutonium-oxide homogeneity, plutonium-oxide particle size, plutonium-oxide particle distribution, integrity, and surface cracks shall be determined as well. The surfaces of finished pellets shall be visually free of loose chips, oil, macroscopic inclusions, and foreign materials. An estimate of the fuel pellet irradiation stability shall be obtained unless adequate allowance for such effects are factored into the fuel rod design. The estimate of the stability shall consist of either conformance to the thermal stability test as specified in the or by adequate correlation of manufacturing process or microstructure to in-reactor behavior, or both.
SCOPE
1.1 This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. This specification may not completely cover the requirements for pellets fabricated from weapons-derived plutonium.
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 50Domestic Licensing of Production and Utilization Facilities; Code of Federal Regulations Title 10, Part 71Packaging and Transportation of Radioactive Material; and Code of Federal Regulations Title 49, Part 173General Requirements for Shipments and Packaging.
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.4 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.

General Information

• Status: Historical
• Publication Date: 30-Nov-2008
• ICS: 27.120.30 - Fissile materials and nuclear fuel technology
• Technical Committee: C26 - Nuclear Fuel Cycle
• Drafting Committee: C26.02 - Fuel and Fertile Material Specifications

Relations

• Replaced By: ASTM C833-13 - Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets
• Effective Date: 01-Jan-2013

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation:C833 −01(Reapproved2008)
StandardSpecification for
Sintered (Uranium-Plutonium) Dioxide Pellets
This standard is issued under the fixed designation C833; 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
uranium-plutonium dioxide pellets for thermal reactor use. It recognizes the diversity of manufactur-
ing methods by which uranium-plutonium dioxide pellets are produced and the many special
requirements for chemical and physical characterization that may be imposed by the operating
conditions to which the pellets will be subjected in specific reactor systems. It does not recognize the
possible problems associated with the reprocessing of such pellets. It is, therefore, anticipated that the
purchaser may supplement this specification with additional requirements for specific applications.
1. Scope This standard does not purport to address all of the safety
concerns, if any, associated with its use. It is the responsibility
1.1 This specification covers finished sintered and ground
of the user of this standard to establish appropriate safety and
(uranium-plutonium) dioxide pellets for use in thermal reac-
health practices and determine the applicability of regulatory
tors.Itappliestouranium-plutoniumdioxidepelletscontaining
limitations prior to use.
plutonium additions up to 15 % weight.This specification may
not completely cover the requirements for pellets fabricated
2. Referenced Documents
from weapons-derived plutonium.
2.1 ASTM Standards:
1.2 This specification does not include (1) provisions for
C698 Test Methods for Chemical, Mass Spectrometric, and
preventing criticality accidents or (2) requirements for health
Spectrochemical Analysis of Nuclear-Grade Mixed Ox-
andsafety.Observanceofthisspecificationdoesnotrelievethe
ides ((U, Pu)O )
user of the obligation to be aware of and conform to all
C753 Specification for Nuclear-Grade, Sinterable Uranium
applicable international, federal, state, and local regulations
Dioxide Powder
pertaining to possessing, processing, shipping, or using source
C757 Specification for Nuclear-Grade Plutonium Dioxide
or special nuclear material. Examples of U.S. government
Powder, Sinterable
documents are Code of Federal Regulations Title 10, Part
C859 Terminology Relating to Nuclear Materials
50—Domestic Licensing of Production and Utilization Facili-
C1165 Test Method for Determining Plutonium by
ties; Code of Federal RegulationsTitle 10, Part 71—Packaging
Controlled-Potential Coulometry in H SO at a Platinum
2 4
and Transportation of Radioactive Material; and Code of
Working Electrode
Federal RegulationsTitle 49, Part 173—General Requirements
C1204 Test Method for Uranium in Presence of Plutonium
for Shipments and Packaging.
by Iron(II) Reduction in Phosphoric Acid Followed by
1.3 The values stated in SI units are to be regarded as
Chromium(VI) Titration
standard. No other units of measurement are included in this
C1206 Test Method for Plutonium by Iron (II)/Chromium
standard.
(VI) Amperometric Titration
C1233 Practice for Determining Equivalent Boron Contents
1.4 The following safety hazards caveat pertains only to the
of Nuclear Materials
technical requirements portion, Section 4, of this specification:
E105 Practice for Probability Sampling of Materials
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. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved Dec. 1, 2008. Published January 2009. Originally contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
approved in 1976. Last previous edition approved in 2001 as C833 – 01. DOI: Standards volume information, refer to the standard’s Document Summary page on
10.1520/C0833-01R08. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
C833−01(Reapproved2008)
2.2 ANSI Standard: The nominal value and allowable tolerance shall be agreed
ANSI/ASME NQA-1 Quality Assurance Requirements for upon between the buyer and seller.
Nuclear Facility Applications 4.1.4 Moisture Content—The moisture content limit is in-
cluded in the total hydrogen limit (see Table 1).
2.3 U.S. Government Documents:
4.1.5 Gas Content—The gas content, exclusive of moisture,
USNRC Regulatory Guide 1.126 An Acceptable Model and
shall not exceed, at Standard Temperature and Pressure (0°C
Related Statistical Methods for the Analysis of Fuel
and one atmosphere), 0.05 L/kg of the heavy metal content.
Densification
4.1.6 Americium-241 Content—The americium-241 content
Code of Federal Regulations Title 10, Part 50 Domestic
shall be measured by the seller and reported to the buyer. The
Licensing of Production and Utilization Facilities
americium-241 content or activity is important in the handling
Code of Federal RegulationsTitle 10, Part 71 Packaging and
of UO -PuO pellets and will vary with time. The maximum
2 2
Transportation of Radioactive Material
acceptable americium-241 content on a given date along with
Code of Federal Regulations Title 49, Part 173 General
thedateofanalysisshallbeagreeduponbetweenthebuyerand
Requirements for Shipments and Packaging
seller. The dates of separation of plutonium from this isotope
and the analysis dates shall be considered; methods of report-
3. Terminology
ing shall be agreed upon between the buyer and seller.
3.1 Definitions—Definitions shall be in accordance with
4.2 Nuclear Requirements:
Terminology C859.
4.2.1 Isotopic Content—The isotopic content of the ameri-
cium, uranium, and plutonium in the (uranium-plutonium)
4. Technical Requirements
dioxide pellets shall be determined and the date of the
4.1 Chemical Requirements—All chemical analyses shall be
234 235 236 238
determinationrecorded.The U, U, U,and Ucontent
performed on portions of the representative sample prepared in
of the uranium shall be reported as a mass percentage with
accordance with Section 6.Analytical chemistry methods shall
238 239 240 241
respect to total uranium, and the Pu, Pu, Pu, Pu, and
be as stated in Test Methods C698 (latest edition) or demon-
Pu content of the plutonium shall be reported on a Pu mass
strated equivalent as mutually agreed to between the buyer and
% or on (Pu + Am) mass % basis. The equivalent plutonium
the seller.
content based on uranium and plutonium isotopic concentra-
4.1.1 Uranium and Plutonium Content—Unless agreed
tions shall be as agreed upon between the buyer and seller.
uponbythebuyerandseller,individualpowdersshallmeetthe
4.2.2 Plutonium Equivalent at a Given Date—(uranium-
requirements of Specifications C753 and C757, which also
plutonium) dioxide fuel shall be considered as defined by the
reference Test Methods C1165, C1204, and C1206. The
plutonium content with adjustment (credit or debit) for the
uraniumandplutoniumcontentscombinedshallbeaminimum
actual isotopic composition of plutonium, americium, and
of 87.7 % weight on a dry weight basis compensated for the
uranium. The dates of isotopic analyses in support of these
Am-241 content. (Dry weight is defined as the sample weight
determinations shall be recorded by the seller and reported to
minus the moisture content). The plutonium content shall be
thebuyer.Theallowabletolerancestolerancesoftheplutonium
that specified by the buyer, up to the limits covered in this
equivalent content (either as uranium plus plutonium or as the
specification (15 %).
individualelements)shallbeasagreeduponbetweenthebuyer
4.1.2 Impurity Content—The impurity content shall not
and seller.
exceed the individual element limit specified in Table 1 based
4.2.3 Equivalent Boron Content—For thermal reactor use,
on the heavy metal content (uranium plus plutonium). The
the total equivalent boron content (EBC) shall not exceed 4.0
summationofthecontributionofeachoftheimpurityelements
µg/g on a heavy metal basis. The method of performing the
listed in Table 1 shall not exceed 1500 µg/g (U + P). If an
calculation shall be as indicated in Practice C1233. For the
element analysis is reported as “less than” a given concentra-
purposes of EBC calculation, B, Gd, Eu, Dy, Sm, and Cd shall
tion,this“lessthan”valueshallbeusedinthedeterminationof
be included.
total impurities.
NOTE 1—Higher impurity limits should be acceptable for restricted
burnups and linear power ratings if there is evidence to substantiate the
TABLE 1 Impurity Elements and Maximum Concentration Limits
relaxation. Higher impurity levels of 450 ppm aluminum, 250 ppm
Maximum Concentration
carbon, 250 ppm nitrogen, and 450 ppm silicon have been supported for Element
Limit (µg/g of U + Pu)
burnups of less than 35 000 MWd/t. The extension of the burnup limit
Aluminum 250
may be determined by agreement between the buyer and seller as
Carbon 100
supporting data are accumulated.
Calcium + magnesium 200
Chlorine 25
4.1.3 Stoichiometry—The oxygen-to-heavy metal ratio of
Chromium 250
sinteredfuelpelletsshallbewithintherangefrom1.98to2.02.
Cobalt 100
Fluorine 25
Hydrogen (total from all 1.3
sources)
Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
Iron 500
4th Floor, New York, NY 10036, http://www.ansi.org.
Nickel 250
AvailablefromU.S.GovernmentPrintingOfficeSuperintendentofDocuments,
Nitride/nitrogen 75
732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http:// Silicon 250
www.access.gpo.gov.
C833−01(Reapproved2008)
4.2.4 Reactivity—An integral test of reactivity may be (1) Axial Cracks, including those leading to pellet ends— ⁄2
performed and correlated to total EBC by a method agreed the pellet length.
upon between the buyer and the seller. If this is done, a total (2) Circumferential Cracks— ⁄23 of the pellet circumfer-
EBC need not be determined. ence.
4.3.5.2 Chips—Thelimitsforchips(missingmaterial)areas
4.3 Physical Characteristics:
follows:
4.3.1 Dimensions—The dimensions and their tolerances of
(1) Cylindrical Surface Chips
the pellet shall be specified by the buyer. These shall include
(a) Cylindrical Surface Area—the total area of all
diameter, length, perpendicularity, and, as required, other
chips shall be less than 5 % of the pellet cylindrical surface
geometric parameters including surface finish.
area.
4.3.2 Pellet Density—The density and tolerance of sintered
(b)
...

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:C833–95a Designation: C 833 – 01 (Reapproved 2008)
Standard Specification for
Sintered (Uranium-Plutonium) Dioxide Pellets
This standard is issued under the fixed designation C 833; 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
uranium-plutonium dioxide pellets for thermal reactor use. It recognizes the diversity of manufactur-
ing methods by which uranium-plutonium dioxide pellets are produced and the many special
requirements for chemical and physical characterization that may be imposed by the operating
conditions to which the pellets will be subjected in specific reactor systems. It does not recognize the
possible problems associated with the reprocessing of such pellets. It is, therefore, anticipated that the
purchaser may supplement this specification with additional requirements for specific applications.
1. Scope
1.1This specification covers finished sintered (uranium-plutonium) dioxide pellets. It applies to uranium-plutonium dioxide
pellets containing plutonium additions up to 10% weight. The isotopic composition of the diluent uranium shall be of any U
composition.The isotopic composition of the plutonium component shall be as normally prepared by in-reactor neutron irradiation
of uranium having less than 5% U.
1.1 This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It
applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. This specification may not
completely cover the requirements for pellets fabricated from weapons-derived plutonium.
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 international,
federal, state, and local regulations on possessing, shipping, processing, or using source or special nuclear materials. Guidance is
provided in CFR Title 10, TID-7016, and DP-532 (see 2.3).
1.3All terms used herein are as defined in Terminology C859.
1.4The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
) 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; Code of Federal Regulations Title 10, Part 71—Packaging and
Transportation of Radioactive Material; and Code of Federal RegulationsTitle 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.
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
2. Referenced Documents
2.1 ASTM Standards:
C 698 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U,
Pu)O )
This specification is under the jurisdiction of ASTM Committee C-26C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel and
Fertile Material Specifications.
Current edition approved Sept. 10, 1995.Dec. 1, 2008. Published November 1995.January 2009. Originally published as C833–76.approved in 1976. Last previous edition
C833–95.approved in 2001 as C 833 – 01.
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
, Vol 12.01.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 833 – 01 (2008)
C 753 Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
C 757 Specification for Nuclear-Grade Plutonium Dioxide Powder, Sinterable
C 859 Terminology Relating to Nuclear Materials
C 1165 Test Method for Determining Plutonium by Controlled-Potential Coulometry in H SO Atat a Platinum Working
2 4
Electrode
C 1204 Test Method for Uranium in the Presence of Plutonium by Iron(II) Reduction in Phosphoric Acid Followed by
Chromium(VI) Titration
C 1206 Test Method for Plutonium by Iron (II)/Chromium (VI) Amperometric Titration
C 1233 Practice for Determining Equivalent Boron Contents of Nuclear Material Materials
E 105 Practice for Probability Sampling ofOf Materials
2.2 ANSI Standard:
ANSI/ASME NQA-1 Quality Assurance Program Requirements for Nuclear Facility Appliecations
2.3 U.S. Government Documents:
CFR Title 10,Chapter 1 Nuclear Safety Guide (Title 49 Transportation, Chapter 1 Materials Transportation Bureau) Nuclear
Safety Guide, U.S. AEC Report TID-7016 Handbook of Nuclear Safety, AEC Report DP-532
CFR 10,Chapter 1, Regulatory Guide 1.126 An Acceptable Model and Related Statistical Methods for the Analysis of Fuel
DensificationUSNRCRegulatoryGuide1.126 AnAcceptableModelandRelatedStatisticalMethodsfortheAnalysisofFuel
Densification
Code of Federal Regulations Title 10, Part 50 Domestic Licensing of Production and Utilization Facilities
Code of Federal Regulations Title 10, Part 71 Packaging and Transportation of Radioactive Material
Code of Federal Regulations Title 49, Part 173 General Requirements for Shipments and Packaging
3. Terminology
3.1Definitions:
3.1.1For definitions of terms, refer to Terminology C859
3.1 Definitions—Definitions shall be in accordance with Terminology C 859.
4. Technical Requirements
4.1 Chemical Requirements—All chemical analyses shall be performed on portions of the representative sample prepared in
accordance with Section 6.Analytical chemistry methods shall be as stated in Test Methods C 698 (latest edition) or demonstrated
equivalent as mutually agreed to between the buyer and the seller.
4.1.1 Uranium and Plutonium Content —Individual powders may be specified as in Specifications C753 and C757—Unless
agreeduponbythebuyerandseller,individualpowdersshallmeettherequirementsofSpecificationsC 753andC 757,whichalso
reference Test Methods C 1165, C 1204, and C 1206. The uranium and plutonium contents combined shall be a minimum of
87.7 % weight on a dry weight basis compensated for theAm-241 content. (Dry weight is defined as the sample weight minus the
moisture content). The plutonium content shall be that specified by the buyer, up to the limits covered in this specification (15%).
4.1.2 Impurity Content— The impurity content shall not exceed the individual element limit specified in Table 1 based on the
Annual Book of ASTM Standards, Vol 14.02.
Available from American National Standards Institute (ANSI), 25 W. 43rd St., 4th Floor, New York, NY 10036, http://www.ansi.org.
Available from American National Standards Institute, 11 West 42nd St., 13th Floor, New York, NY 10036.
Available from U.S. Government Printing Office Superintendent of Documents, 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http://
www.access.gpo.gov.
TABLE 1 Impurity Elements and Maximum Concentration Limits
Maximum Concentration
Element
Limit (µg/g of U + Pu)
Aluminum 250
Carbon 100
Calcium + magnesium 200
Chlorine 25
Chromium 250
Cobalt 100
Fluorine 15
Fluorine 25
Hydrogen (total from all 1.3
sources)
Iron 500
Nickel 250
Nitride/nitrogen 75
Silicon 250Thorium 10
C 833 – 01 (2008)
heavy metal content (uranium plus plutonium).The summation of the contribution of each of the impurity elements listed inTable
1 shall not exceed 1500 µg/g (U + P). 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.
NOTE 1—Higher impurity limits should be acceptable for restricted burnups and linear power ratings if there is evidence to substantiate the relaxation.
Higher impurity levels of 450 ppm aluminum, 250 ppm carbon, 250 ppm nitrogen, and 450 ppm silicon have been supported for burnups of less than
35 000 MWd/t. The extension of the burnup limit may be determined by agreement between the buyer and seller as supporting data are accumulated.
4.1.3 Stoichiometry—The oxygen-to-heavy metal ratio of sintered fuel pellets shall be within the range from 1.98 to 2.02. —
The oxygen-to-heavy metal ratio of sintered fuel pellets shall be within the range from 1.98 to 2.02. The nominal value and
allowable tolerance shall be agreed upon between the buyer and seller.
4.1.4 Moisture Content— The moisture content limit is included in the total hydrogen limit (see Table 1).
4.1.5 Gas Content—The gas content, exclusive of moisture, shall not exceed, at standard temperature and pressure, 0.05 L/kg
oftheheavymetalcontent.—Thegascontent,exclusiveofmoisture,shallnotexceed,atStandardTemperatureandPressure(0°C
and one atmosphere), 0.05 L/kg of the heavy metal content.
4.1.6 Americium-241 Content—The americium-241 content shall be measured by the seller and reported to the buyer. The
americium-241 content or activity is important in the handling of UO -PuO pellets and will vary with time. The maximum
acceptable americium-241 content on a given date along with the date of analysis shall be agreed upon between the buyer and
seller.The dates of separation of plutonium from this isotope and the analysis dates shall be considered; methods of reporting shall
be agreed upon between the buyer and seller.
4.2 Nuclear Requirements:
4.2.1 Isotopic Content— The isotopic content of the americium, uranium, and of the plutonium in the (uranium-plutonium)
234 235 236
dioxide pellets shall be measureddetermined and the date of measurementthe determination recorded. The U, U, U, and
U content of the uranium shall be reported as a mass percentage with
238U content of the uranium shall be reported on a U% weight basis, and the
239 240 241 242
respect to total uranium, and the Pu, Pu, Pu, Pu, and Pu content of the plutonium shall be reported on a Pu mass % weight or
on (Pu + Am) mass % weight basis. The plutonium equivalent plutonium content based on uranium, plutonium, uranium and
americiumplutonium isotopic concentrations shall be as specified by agreed upon between the buyer and seller.
4.2.2 Plutonium Equivalent—The Plutonium equivalent content of the (uranium-plutonium) dioxide fuel shall be considered as
defined by the plutonium content with adjustment (credit or debit) for the actual isotopic composition of plutonium, americium,
and uranium as of a “reference date.” The permissible tolerances of the equivalent plutonium content (either as uranium plus
plutoniumorastheindividualelements)shallbeasagreeduponbetweenthebuyerandtheseller.PlutoniumEquivalentataGiven
Date—(uranium-plutonium) dioxide fuel shall be considered as defined by the plutonium content with adjustment (credit or debit)
for the actual isotopic composition of plutonium, americium, and uranium. The dates of isotopic analyses in support of these
determinations shall be recorded by the seller and reported to the buyer. The allowable tolerances tolerances of the plutonium
equivalent content (either as uranium plus plutonium or as the individual elements) shall be as agreed upon between the buyer and
seller.
4.2.3 Equivalent Boron Content—For thermal reactor use, the total equivalent boron content (EBC) shall not exceed 4.0 µg/g
on a heavy metal basis. The total EBC is the sum of the individual EBC values. Practice C1233 contains a list of elements to be
considered in calculating the total EBC. The specific elements to be used in calculating the total EBC as well as the values of the
cross sections will depend on individual reactor characteristics. Practice C1233 should be considered as an example only. Specific
elements and their EBC factors shall be determined by agreement between the buyer and the seller.The EBC of each element shall
be calculated individually using the following equation:
EBCofElement5~EBCfactor!3~µgelement/gheavymetal! (1)
—For thermal reactor use, the total equivalent boron content (EBC) shall not exceed 4.0 µg/g on a heavy metal basis. The method of performing the
calculation shall be as indicated in Practice C 1233. For the purposes of EBC calculation, B, Gd, Eu, Dy, Sm, and Cd shall be included.
4.2.4 Reactivity—AnintegraltestofreactivitymaybeperformedandcorrelatedtototalEBCbyamethodagreeduponbetween
the buyer and the seller. If this is done, a total EBC need not be determined.
4.3 Physical Characteristics:
4.3.1 Dimensions—The dimensions and their tolerances of the pellet shall be specified by the buyer. These shall include
diameter, length, perpendicularity, and, as required, other geometric parameters including surface finish.
4.3.2 Pellet Density— The density and tolerance of sintered pellets shall be as specified by the buyer. The theoretical density
3 3
for UO shall be considered to be 10.96 g/cm . The theoretical density for PuO shall be considered to be 11.46 g/cm . The
2 2
theoreticaldensityforthe(U,Pu)O pelletsshallbecalculatedbylinearinterpolationbetweenthesevalues.Densitymeasurements
shall be made by the method stated in Specification C 753 (for the geometric method) by an immersion density technique, or by
demonstrated equivalent method as mutually agreed upon between the buyer and the seller.
4.3.3 Grain Size and Pore Morphology —Because there is no unique structure for ensuring satisfactory performance, the pellet
grain size and pore morphology shall be mutually agreed upon between the buyer and the seller.
4.3.4 Plutonium-Oxide Homogeneity
...

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:C833–01 Designation: C 833 – 01 (Reapproved 2008)
Standard Specification for
Sintered (Uranium-Plutonium) Dioxide Pellets
This standard is issued under the fixed designation C 833; 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
uranium-plutonium dioxide pellets for thermal reactor use. It recognizes the diversity of manufactur-
ing methods by which uranium-plutonium dioxide pellets are produced and the many special
requirements for chemical and physical characterization that may be imposed by the operating
conditions to which the pellets will be subjected in specific reactor systems. It does not recognize the
possible problems associated with the reprocessing of such pellets. It is, therefore, anticipated that the
purchaser may supplement this specification with additional requirements for specific applications.
1. Scope
1.1 This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It
applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. This specification may not
completely cover the requirements for pellets fabricated from weapons-derived plutonium.
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; Code of Federal Regulations Title 10, Part 71–—Packaging and Transportation of
Radioactive Material; and Code of Federal Regulations 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.
1.4The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
2. Referenced Documents
2.1 ASTM Standards:
C 698 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U,
Pu)O )
C 753 Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
C 757 Specification for Nuclear-Grade Plutonium Dioxide Powder, Sinterable
C 859 Terminology Relating to Nuclear Materials
C 1165 Test Method for Determining Plutonium by Controlled-Potential Coulometry in H SO Atat a Platinum Working
2 4
Electrode
C 1204 Test Method for Uranium in the Presence of Plutonium by Iron(II) Reduction in Phosphoric Acid Followed by
Chromium(VI) Titration
C 1206 Test Method for Plutonium by Iron (II)/Chromium (VI) Amperometric Titration
C 1233 Practice for Determining Equivalent Boron Contents of Nuclear Material Materials
This specification is under the jurisdiction ofASTM 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 10, 2001. Published October 2001. Originally published as C833–76. Last previous edition C833–95a.
Current edition approved Dec. 1, 2008. Published January 2009. Originally approved in 1976. Last previous edition approved in 2001 as C 833 – 01.
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
, Vol 12.01.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 833 – 01 (2008)
E 105 Practice for Probability Sampling ofOf Materials
2.2 ANSI Standard:
ANSI/ASME NQA-1 Quality Assurance Requirements for Nuclear Facility Applications
2.3 U.S. Government Documents:
USNRC Regulatory Guide 1.126 AnAcceptable Model and Related Statistical Methods for theAnalysis of Fuel Densification
Code of Federal Regulations Title 10, Part 50 Domestic Licensing of Production and Utilization Facilities
Code of Federal Regulations Title 10, Part 71 Packaging and Transportation of Radioactive Material
Code of Federal Regulations Title 49, Part 173 General Requirements for Shipments and Packaging
3. Terminology
3.1 Definitions—Definitions shall be in accordance with Terminology C 859.
4. Technical Requirements
4.1 Chemical Requirements—All chemical analyses shall be performed on portions of the representative sample prepared in
accordance with Section 6.Analytical chemistry methods shall be as stated in Test Methods C 698 (latest edition) or demonstrated
equivalent as mutually agreed to between the buyer and the seller.
4.1.1 Uranium and Plutonium Content —Unless agreed upon by the buyer and seller, individual powders shall meet the
requirements of Specifications C 753 and C 757, which also reference Test Methods C 1165, C 1204, and C 1206. The uranium
and plutonium contents combined shall be a minimum of 87.7 % weight on a dry weight basis compensated for the Am-241
content. (Dry weight is defined as the sample weight minus the moisture content). The plutonium content shall be that specified
by the buyer, up to the limits covered in this specification (15%).
4.1.2 Impurity Content— The impurity content shall not exceed the individual element limit specified in Table 1 based on the
heavy metal content (uranium plus plutonium).The summation of the contribution of each of the impurity elements listed inTable
1 shall not exceed 1500 µg/g (U + P). 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.
NOTE 1—Higher impurity limits should be acceptable for restricted burnups and linear power ratings if there is evidence to substantiate the relaxation.
Higher impurity levels of 450 ppm aluminum, 250 ppm carbon, 250 ppm nitrogen, and 450 ppm silicon have been supported for burnups of less than
35 000 MWd/t. The extension of the burnup limit may be determined by agreement between the buyer and seller as supporting data are accumulated.
4.1.3 Stoichiometry— The oxygen-to-heavy metal ratio of sintered fuel pellets shall be within the range from 1.98 to 2.02. The
nominal value and allowable tolerance shall be agreed upon between the buyer and seller.
4.1.4 Moisture Content— The moisture content limit is included in the total hydrogen limit (see Table 1).
4.1.5 Gas Content— The gas content, exclusive of moisture, shall not exceed, at Standard Temperature and Pressure (0°C and
one atmosphere), 0.05 L/kg of the heavy metal content.
4.1.6 Americium-241 Content—The americium-241 content shall be measured by the seller and reported to the buyer. The
americium-241 content or activity is important in the handling of UO -PuO pellets and will vary with time. The maximum
2 2
acceptable americium-241 content on a given date along with the date of analysis shall be agreed upon between the buyer and
Annual Book of ASTM Standards, Vol 14.02.
Available from American National Standards Institute (ANSI), 25 W. 43rd St., 4th Floor, New York, NY 10036, http://www.ansi.org.
Available from American National Standards Institute, 25 West 43rd St., 4th Floor, New York, NY 10036.
Available from U.S. Government Printing Office Superintendent of Documents, 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http://
www.access.gpo.gov.
TABLE 1 Impurity Elements and Maximum Concentration Limits
Maximum Concentration
Element
Limit (µg/g of U + Pu)
Aluminum 250
Carbon 100
Calcium + magnesium 200
Chlorine 25
Chromium 250
Cobalt 100
Fluorine 25
Hydrogen (total from all 1.3
sources)
Iron 500
Nickel 250
Nitride/nitrogen 75
Silicon 250
C 833 – 01 (2008)
seller.The dates of separation of plutonium from this isotope and the analysis dates shall be considered; methods of reporting shall
be agreed upon between the buyer and seller.
4.2 Nuclear Requirements:
4.2.1 Isotopic Content— The isotopic content of the americium, uranium, and plutonium in the (uranium-plutonium) dioxide
234 235 236 238
pellets shall be determined and the date of the determination recorded.The U, U, U, and U content of the uranium shall
238 239 240 241 242
be reported as a mass percentage with respect to total uranium, and the Pu, Pu, Pu, Pu, and Pu content of the
plutonium shall be reported on a Pu mass % or on (Pu + Am) mass % basis. The equivalent plutonium content based on uranium
and plutonium isotopic concentrations shall be as agreed upon between the buyer and seller.
4.2.2 Plutonium Equivalent at a Given Date—(uranium-plutonium)dioxidefuelshallbeconsideredasdefinedbytheplutonium
content with adjustment (credit or debit) for the actual isotopic composition of plutonium, americium, and uranium. The dates of
isotopic analyses in support of these determinations shall be recorded by the seller and reported to the buyer. The allowable
tolerances tolerances of the plutonium equivalent content (either as uranium plus plutonium or as the individual elements) shall
be as agreed upon between the buyer and seller.
4.2.3 Equivalent Boron Content—For thermal reactor use, the total equivalent boron content (EBC) shall not exceed 4.0 µg/g
on a heavy metal basis. The method of performing the calculation shall be as indicated in Practice C 1233. For the purposes of
EBC calculation, B, Gd, Eu, Dy, Sm, and Cd shall be included.
4.2.4 Reactivity—AnintegraltestofreactivitymaybeperformedandcorrelatedtototalEBCbyamethodagreeduponbetween
the buyer and the seller. If this is done, a total EBC need not be determined.
4.3 Physical Characteristics:
4.3.1 Dimensions—The dimensions and their tolerances of the pellet shall be specified by the buyer. These shall include
diameter, length, perpendicularity, and, as required, other geometric parameters including surface finish.
4.3.2 Pellet Density— The density and tolerance of sintered pellets shall be as specified by the buyer. The theoretical density
3 3
for UO shall be considered to be 10.96 g/cm . The theoretical density for PuO shall be considered to be 11.46 g/cm . The
2 2
theoreticaldensityforthe(U,Pu)O pelletsshallbecalculatedbylinearinterpolationbetweenthesevalues.Densitymeasurements
shall be made by the method stated in Specification C 753 (for the geometric method) by an immersion density technique, or by
demonstrated equivalent method as mutually agreed upon between the buyer and the seller.
4.3.3 Grain Size and Pore Morphology —Because there is no unique structure for ensuring satisfactory performance, the pellet
grain size and pore morphology shall be mutually agreed upon between the buyer and the seller.
4.3.4 Plutonium-Oxide Homogeneity and Size:
4.3.4.1 Plutonium Homogeneity Within a Pellet Lot—Homogeneity of the Pu content shall be demonstrated through analyses
of multiple pellets. Each sample for analysis should be one pellet or a fragment thereof. The range of the equivalent Pu content
shall not exceed 65.0% relative or 60.2% absolute, whichever is less restrictive. Alternative methods and criteria that may be
agreed upon between the buyer and the seller are possible for evaluation of plutonium homogeneity within a lot.
4.3.4.2 Plutonium-Oxide Particle Size and Distribution Within a Pellet—ThemaximumequivalentdiameterofPu-richparticles
shall be less than 400 µm. The distribution of Pu-rich particles shall satisfy either of the following requirements: (a) No more than
5 % of the nominal PuO shall be present in Pu-rich particles with equivalent diameters of 200 µm or greater, or (b) No more than
5 % of the Pu-rich particles shall be greater than 100 µm in diameter and the average diameter of Pu-rich particles will be less than
50 µm. The method for determining the Pu homogeneity and what constitutes a Pu-rich particle shall be agreed upon between the
buyer and seller. The area percentage and the volume percentage shall be regarded as equivalent provided the homogeneity
requirements of 4.3.4.1 4.3.4.1 are satisfied.
NOTE 2—These limits are based on PuO that has a nominal 65% fissle plutonium content. Smaller particle size may be required for greater fissle
plutonium content.
4.3.5 Pellet Integrity— Pellets shall be inspected according to criteria which maintain adequate fuel performance and ensure
that excessive breakage will not occur during fuel rod loading. Acceptable test methods include a visual (1X) comparison with
pellet standards or other methods, for example, loadability tests, approved by both the buyer and the seller.
4.3.5.1 Surface Cracks— The limits for surface cracks are as follows:
(1) Axial Cracks, including those leading to pellet ends— ⁄2 the pellet length.
(2) Circumferential Cracks— ⁄23 of the pellet circumference.
4.3.5.2 Chips—The limits for chips (missing material) are as follows:
(1) Cylindrical Surface Chips
(a) Cylindrical Surface Area—the total area of all chips shall be less than 5 % of the pellet cylindrical surface area.
(b) Maximum Linear Dimension—30 % of the pellet length.
(2) Pellet Ends—1/3 of the pellet end surfaces (may be inspected as 1/3 of the missing circumference at the pellet end).
4.3.6 Cleanliness and Workmanship —The surfaces of finished pellets shall be visually (1X) free of loose chips, oil,
macroscopic inclusions, and foreign materials.
4.4 Identification— It shall be possible to identify pellets as to total fissile and total plutonium content by, for example, marking
or coding or other administrative controls. Other identifi
...