ASTM C833-23

Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors

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 (U, Pu)O2 pellets for use in light water reactors. It applies to (U, Pu)O2 pellets containing a plutonium mass fraction up to 15 % (that is, mass of Pu divided by the sum of masses U, Pu, and Am yielding 0.15 or less).  
1.2 Pellets produced under this specification are available in four grades.  
1.2.1 Grade R—240Pu / (Pu + Am) isotope mass fraction is at least 19 %.  
1.2.2 Grade F—240Pu / (Pu + Am) isotope mass fraction is at least 7 % and less than 19 %.  
1.2.3 Grade N1—240Pu / (Pu + Am) isotope mass fraction is less than 7 %.  
1.2.4 Grade N2—240Pu /239Pu isotope mass fraction does not exceed 0.10 (10 %).  
1.3 There is no discussion of or provision for preventing criticality incidents, nor are health and safety requirements, the avoidance of hazards, or shipping precautions and controls discussed. 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.  
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.5 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technic...

General Information

• Status: Published
• Publication Date: 31-May-2023
• 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

Standards Content (Sample)

This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the
Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
Designation: C833 − 23
Standard Specification for
Sintered (Uranium-Plutonium) Dioxide Pellets for Light
1
Water Reactors
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 ((U, Pu)O ) pellets for light water reactor use. It recognizes the diversity
2
of manufacturing methods by which (U, Pu)O pellets are produced and the many special requirements
2
for chemical and physical characterization that may be imposed by the operating conditions to which
the pellets will be subjected in different light water reactors. 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 50—Domestic Licensing of Production and Utilization Facili-
ties; Code of Federal Regulations Title 10, Part 71—Packaging
1.1 This specification covers finished sintered and ground
and Transportation of Radioactive Material; and Code of
(U, Pu)O pellets for use in light water reactors. It applies to
2
Federal Regulations Title 49, Part 173—General Requirements
(U, Pu)O pellets containing a plutonium mass fraction up to
2
for Shipments and Packaging.
15 % (that is, mass of Pu divided by the sum of masses U, Pu,
and Am yielding 0.15 or less). 1.4 The values stated in SI units are to be regarded as
standard. No other units of measurement are included in this
1.2 Pellets produced under this specification are available in
standard.
four grades.
240
1.5 The following safety hazards caveat pertains only to the
1.2.1 Grade R— Pu / (Pu + Am) isotope mass fraction is
technical requirements portion, Section 4, of this specification:
at least 19 %.
240
This standard does not purport to address all of the safety
1.2.2 Grade F— Pu / (Pu + Am) isotope mass fraction is
concerns, if any, associated with its use. It is the responsibility
at least 7 % and less than 19 %.
240
of the user of this standard to establish appropriate safety,
1.2.3 Grade N1— Pu / (Pu + Am) isotope mass fraction is
health, and environmental practices and determine the appli-
less than 7 %.
240 239
cability of regulatory limitations prior to use.
1.2.4 Grade N2— Pu / Pu isotope mass fraction does
1.6 This international standard was developed in accor-
not exceed 0.10 (10 %).
dance with internationally recognized principles on standard-
1.3 There is no discussion of or provision for preventing
ization established in the Decision on Principles for the
criticality incidents, nor are health and safety requirements, the
Development of International Standards, Guides and Recom-
avoidance of hazards, or shipping precautions and controls
mendations issued by the World Trade Organization Technical
discussed. Observance of this specification does not relieve the
Barriers to Trade (TBT) Committee.
user of the obligation to be aware of and conform to all
applicable international, federal, state, and local regulations
2. Referenced Documents
pertaining to possessing, processing, shipping, or using source
2
2.1 ASTM Standards:
or special nuclear material. Examples of U.S. government
B243 Terminology of Powder Metallurgy
documents are Code of Federal Regulations Title 10, Part
C698 Test Methods for Chemical, Mass Spectrometric, and
Spectrochemical Analysis of Nuclear-Grade Mixed Ox-
ides ((U, Pu)O )
2
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
2
and Fertile Material Specifications. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved June 1, 2023. Published July 2023. Originally approved contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
in 1976. Last previous edition approved in 2017 as C833 – 17. DOI: 10.1520/ Standards volume information, refer to the standard’s Document Summary page on
C0833-23. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

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C833 − 23
A
TABLE 1 Impurity Elements and Maximum Concentration Limits
C753 Specification for Nuclear-Grade, Sinterable Urani
...

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: C833 − 17 C833 − 23
Standard Specification for
Sintered (Uranium-Plutonium) Dioxide Pellets for Light
1
Water Reactors
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 ((U, Pu)O ) pellets for light water reactor use. It recognizes the diversity
2
of manufacturing methods by which (U, Pu)O pellets are produced and the many special requirements
2
for chemical and physical characterization that may be imposed by the operating conditions to which
the pellets will be subjected in different light water reactors. 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 (U, Pu)O pellets for use in light water reactors. It applies to (U, Pu)O
2 2
pellets containing plutonium additions up to 15 weight % (wt%; that is, 0.15 g Pu / g (U + Pu + Am)). a plutonium mass fraction
up to 15 % (that is, mass of Pu divided by the sum of masses U, Pu, and Am yielding 0.15 or less).
1.2 Pellets produced under this specification are available in four grades.
240 240
1.2.1 Grade R— Pu content of / (Pu + Am) (that is, gisotope mass fraction Pu / g (Pu + Am)) is at least 19 %.19 %.
240
1.2.2 Grade F— Pu content of / (Pu + Am) isotope mass fraction is at least 7 % 7 % and less than 19 %.19 %.
240
1.2.3 Grade N1— Pu content of / (Pu + Am) isotope mass fraction is less than 7 %.7 %.
240 239
1.2.4 Grade N2— Pu / Pu isotope mass fraction does not exceed 0.10.0.10 (10 %).
1.3 There is no discussion of or provision for preventing criticality incidents, nor are health and safety requirements, the avoidance
of hazards, or shipping precautions and controls discussed. 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
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 Jan. 1, 2017June 1, 2023. Published January 2017July 2023. Originally approved in 1976. Last previous edition approved in 20132017 as
C833 – 13.C833 – 17. DOI: 10.1520/C0833-17.10.1520/C0833-23.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C833 − 23
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.5 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.
1.5 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, health, and environmental practices and determine the applicability of regulatory
limitations prior to use.
1.6 This international standard was developed in accordance with internationally recognized principles on standardization
established in t
...