ASTM C833-17

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 plutonium additions up to 15 weight % (wt%; that is, 0.15 g Pu / g (U + Pu + Am)).  
1.2 Pellets produced under this specification are available in four grades.  
1.2.1 Grade R—240Pu content of (Pu + Am) (that is, g  240Pu / g (Pu + Am)) is at least 19 %.  
1.2.2 Grade F—240Pu content of (Pu + Am) is at least 7 % and less than 19 %.  
1.2.3 Grade N1—240Pu content of (Pu + Am) is less than 7 %.  
1.2.4 Grade N2—240Pu /239Pu does not exceed 0.10.  
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 and health practices and determine the applicability of regulatory limitations prior to use.

General Information

• Status: Historical
• Publication Date: 31-Dec-2016
• 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)

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 − 17
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 and Transportation of Radioactive Material; and Code of
Federal Regulations Title 49, Part 173—General Requirements
1.1 This specification covers finished sintered and ground
for Shipments and Packaging.
(U, Pu)O pellets for use in light water reactors. It applies to
2
(U, Pu)O pellets containing plutonium additions up to 1.4 The values stated in SI units are to be regarded as
2
15 weight % (wt%; that is, 0.15 g Pu / g (U + Pu + Am)). standard. No other units of measurement are included in this
standard.
1.2 Pellets produced under this specification are available in
four grades. 1.5 The following safety hazards caveat pertains only to the
240 240
1.2.1 Grade R— Pu content of (Pu + Am) (that is, g Pu technical requirements portion, Section 4, of this specification:
/ g (Pu + Am)) is at least 19 %. This standard does not purport to address all of the safety
240
1.2.2 Grade F— Pu content of (Pu + Am) is at least 7 % concerns, if any, associated with its use. It is the responsibility
and less than 19 %. of the user of this standard to establish appropriate safety and
240
1.2.3 Grade N1— Pu content of (Pu + Am) is less than 7 health practices and determine the applicability of regulatory
%. limitations prior to use.
240 239
1.2.4 Grade N2— Pu / Pu does not exceed 0.10.
2. Referenced Documents
1.3 There is no discussion of or provision for preventing
2
2.1 ASTM Standards:
criticality incidents, nor are health and safety requirements, the
B243 Terminology of Powder Metallurgy
avoidance of hazards, or shipping precautions and controls
C698 Test Methods for Chemical, Mass Spectrometric, and
discussed. Observance of this specification does not relieve the
Spectrochemical Analysis of Nuclear-Grade Mixed Ox-
user of the obligation to be aware of and conform to all
ides ((U, Pu)O )
applicable international, federal, state, and local regulations
2
C753 Specification for Nuclear-Grade, Sinterable Uranium
pertaining to possessing, processing, shipping, or using source
Dioxide Powder
or special nuclear material. Examples of U.S. government
C757 Specification for Nuclear-Grade Plutonium Dioxide
documents are Code of Federal Regulations Title 10, Part
Powder for Light Water Reactors
50—Domestic Licensing of Production and Utilization Facili-
C859 Terminology Relating to Nuclear Materials
ties; Code of Federal Regulations Title 10, Part 71—Packaging
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
2
and Fertile Material Specifications. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved Jan. 1, 2017. Published January 2017. Originally contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
approved in 1976. Last previous edition approved in 2013 as C833 – 13. DOI: Standards volume information, refer to the standard’s Document Summary page on
10.1520/C0833-17. 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 − 17
A
TABLE 1 Impurity Elements and Maximum Concentration Limits
E105 Practice for Probability Sampling of Materials
Maximum Concentration
E112 Test Methods for Determining Average Grain Size
B
Element Limit (µg/g of U + Pu +
3
2.2 ASME Standard:
Am)
ASME NQA-1 Quality Assurance Requirements for Nuclear
Aluminum (Al) 250
Facility Applications Carbon (C) 100
4 Calcium (Ca) 200
2.3 U.S. Government D
...

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 − 13 C833 − 17
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 thermal light water reactor use. It recognizes the
2
diversity of manufacturing methods by which uranium-plutonium dioxide(U, Pu)O pellets are
2
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.
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 (uranium-plutonium) dioxide(U, Pu)O pellets for use in thermal light
2
water reactors. It applies to uranium-plutonium dioxide(U, Pu)O pellets containing plutonium additions up to 15 % weight (that
2
15 weight % (wt%; that is, 0.15 g Pu / g (U+Pu+Am)). (U + Pu + Am)).
1.2 Pellets produced under this specification are available in four grades.
240 240
1.2.1 Grade R— Pu content of (Pu+Am) (Pu + Am) (that is, g Pu / g (Pu+Am)) (Pu + Am)) is at least 19 %.
240
1.2.2 Grade F— Pu content of (Pu+Am) (Pu + Am) is at least 7 % and less than 19 %.
240
1.2.3 Grade N1— Pu content of (Pu+Am) (Pu + Am) is less than 7 %.
240 239
1.2.4 Grade N2— Pu / Pu does not exceed 0.10.
1.3 This specification does not include (There is no discussion of or1) provisions provision for preventing criticality accidents
or (incidents, nor are2) requirements for health and safety. 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 44,, 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
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, 2013Jan. 1, 2017. Published January 2013January 2017. Originally approved in 1976. Last previous edition approved in 20082013 as
C833 – 01C833 – 13.(2008). DOI: 10.1520/C0833-13.10.1520/C0833-17.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C833 − 17
2. Referenced Documents
2
2.1 ASTM Standards:
B243 Terminology of Powder Metallurgy
C698 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U,
Pu)O )
2
C753 Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
C757 Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors
C859 Terminology Relating to Nuclear Materials
C1233 Practice for Determining Equivalent Boron Contents of Nuclear Materials
E105 Practice for Probabil
...