ASTM C757-16(2021)
(Specification)Standard Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors
Standard Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors
ABSTRACT
This specification covers sinterable nuclear-grade plutonium dioxide powders obtained by the oxalate precipitation route, calcination, or any other equivalent process acceptable to the buyer. Included is plutonium dioxide of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enriched uranium, or recycled plutonium mixed with uranium. The material shall conform to required chemical compositions of plutonium, uranium, americium, impurities (boron, cadmium, carbon, chlorine, chromium, fluorine, iron, gadolinium, nickel, nitride nitrogen, and thorium), equivalent boron, and gamma activity. Materials shall also adhere to physical property requirements as to cleanliness and workmanship, particle size, and surface area.
SCOPE
1.1 This specification covers nuclear grade PuO2 powder. It applies to PuO2 of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enriched uranium or by in-reactor neutron irradiation of recycled plutonium mixed with uranium.
1.2 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, national, or federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. For examples in the U.S. Government, relevant documents are Code of Federal Regulations, Title 10 Nuclear Safety Guide, U.S. Atomic Energy Commission Report TID-70162, and “Handbook of Nuclear Safety”, H. K. Clark, U.S. Atomic Energy Commission Report, DP-5322.
1.3 The PuO2 shall be produced by a qualified process and in accordance with a quality assurance program approved by the user.
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 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 Technical Barriers to Trade (TBT) Committee.
General Information
- Status
- Published
- Publication Date
- 30-Sep-2021
- Technical Committee
- C26 - Nuclear Fuel Cycle
- Drafting Committee
- C26.02 - Fuel and Fertile Material Specifications
Relations
- Effective Date
- 15-Jan-2024
- Effective Date
- 01-Jan-2024
- Effective Date
- 01-Apr-2020
- Effective Date
- 01-Oct-2018
- Effective Date
- 01-Jul-2016
- Effective Date
- 01-Jun-2016
- Effective Date
- 01-Jun-2015
- Effective Date
- 15-Jun-2014
- Effective Date
- 15-Jun-2014
- Effective Date
- 15-Jan-2014
- Effective Date
- 01-Nov-2013
- Effective Date
- 01-Jun-2013
- Effective Date
- 01-May-2013
- Effective Date
- 01-Aug-2012
- Effective Date
- 15-Jul-2012
Overview
ASTM C757-16(2021) is the internationally recognized standard specification developed by ASTM International for nuclear-grade plutonium dioxide (PuO₂) powder used in the fabrication of mixed oxide (MOX) fuel for light water reactors (LWRs). This specification outlines the minimum requirements for chemical composition, impurities, isotopic content, and physical properties of sinterable plutonium dioxide powders produced via oxalate precipitation, calcination, or any equivalent process. The standard ensures that PuO₂ powders meet stringent quality benchmarks, supporting safe and efficient use in nuclear fuel cycles.
Key Topics
- Scope and Application: Defines the requirements for nuclear-grade PuO₂ powders suitable for MOX fuel manufacturing processes in light water reactors. This standard accommodates a variety of isotopic compositions produced from irradiated uranium or recycled plutonium.
- Chemical Composition:
- Specifies minimum plutonium content and requirements for uranium and americium.
- Sets stringent impurity limits for elements such as boron, cadmium, iron, nickel, and others, to ensure reactor safety and fuel performance.
- Calls for reporting of uranium, thorium, and americium content and dates of analysis.
- Physical Properties:
- Details criteria for cleanliness and freedom from foreign matter.
- Requires agreement between buyer and seller on particle size, tap density, and specific surface area, which are crucial for MOX pellet production.
- Sampling and Quality Assurance:
- Emphasizes representative sampling from uniform lots, with clear identification and traceability.
- Requires quality assurance programs based on industry standards (e.g., ASME NQA-1).
- Mandates documentation and certification of compliance for each batch.
Applications
- MOX Fuel Fabrication: The principal application of this standard is in the quality control and specification of plutonium dioxide powder for MOX fuel pellet manufacturing, which is used in light water nuclear reactors.
- Nuclear Reactor Operations: Ensures the PuO₂ powders used in reactor fuel meet rigorous safety, reliability, and regulatory requirements, minimizing the risk of impurities that could impact reactor performance or safety.
- Nuclear Materials Management: Facilitates safe handling, processing, packaging, and shipment of nuclear-grade powders by providing guidelines for lot identification, sampling, and documentation.
- International Nuclear Trade and Compliance: Aligns with WTO TBT principles, supporting harmonized trade of nuclear materials and ensuring compliance with international and national regulations governing nuclear safety and transport.
Related Standards
- ASTM C697: Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Plutonium Dioxide Powders and Pellets
- ASTM C859: Terminology Relating to Nuclear Materials
- ASTM C1274: Test Method for Advanced Ceramic Specific Surface Area by Physical Adsorption
- ASTM C1233: Practice for Determining Equivalent Boron Contents of Nuclear Materials
- ASTM C1770: Test Method for Determination of Loose and Tapped Bulk Densities of Small Quantities of Plutonium Oxide
- ISO 8300: Determination of Pu Content in Plutonium Dioxide of Nuclear-Grade Quality
- ISO 9161: Uranium Dioxide Powder - Determination of Apparent Density and Tap Density
- ISO 13463: Nuclear-grade Plutonium Dioxide Powder for Light Water Reactor MOX Fuel - Guidelines for Defining Product Specification
- ASME NQA-1: Quality Assurance Requirements for Nuclear Facility Applications
Keywords: nuclear-grade plutonium dioxide, PuO₂ powder, MOX fuel, ASTM C757, light water reactors, nuclear fuel specification, impurity limits, pellet fabrication, quality assurance, nuclear materials.
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Frequently Asked Questions
ASTM C757-16(2021) is a technical specification published by ASTM International. Its full title is "Standard Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors". This standard covers: ABSTRACT This specification covers sinterable nuclear-grade plutonium dioxide powders obtained by the oxalate precipitation route, calcination, or any other equivalent process acceptable to the buyer. Included is plutonium dioxide of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enriched uranium, or recycled plutonium mixed with uranium. The material shall conform to required chemical compositions of plutonium, uranium, americium, impurities (boron, cadmium, carbon, chlorine, chromium, fluorine, iron, gadolinium, nickel, nitride nitrogen, and thorium), equivalent boron, and gamma activity. Materials shall also adhere to physical property requirements as to cleanliness and workmanship, particle size, and surface area. SCOPE 1.1 This specification covers nuclear grade PuO2 powder. It applies to PuO2 of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enriched uranium or by in-reactor neutron irradiation of recycled plutonium mixed with uranium. 1.2 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, national, or federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. For examples in the U.S. Government, relevant documents are Code of Federal Regulations, Title 10 Nuclear Safety Guide, U.S. Atomic Energy Commission Report TID-70162, and “Handbook of Nuclear Safety”, H. K. Clark, U.S. Atomic Energy Commission Report, DP-5322. 1.3 The PuO2 shall be produced by a qualified process and in accordance with a quality assurance program approved by the user. 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 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 Technical Barriers to Trade (TBT) Committee.
ABSTRACT This specification covers sinterable nuclear-grade plutonium dioxide powders obtained by the oxalate precipitation route, calcination, or any other equivalent process acceptable to the buyer. Included is plutonium dioxide of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enriched uranium, or recycled plutonium mixed with uranium. The material shall conform to required chemical compositions of plutonium, uranium, americium, impurities (boron, cadmium, carbon, chlorine, chromium, fluorine, iron, gadolinium, nickel, nitride nitrogen, and thorium), equivalent boron, and gamma activity. Materials shall also adhere to physical property requirements as to cleanliness and workmanship, particle size, and surface area. SCOPE 1.1 This specification covers nuclear grade PuO2 powder. It applies to PuO2 of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enriched uranium or by in-reactor neutron irradiation of recycled plutonium mixed with uranium. 1.2 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, national, or federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. For examples in the U.S. Government, relevant documents are Code of Federal Regulations, Title 10 Nuclear Safety Guide, U.S. Atomic Energy Commission Report TID-70162, and “Handbook of Nuclear Safety”, H. K. Clark, U.S. Atomic Energy Commission Report, DP-5322. 1.3 The PuO2 shall be produced by a qualified process and in accordance with a quality assurance program approved by the user. 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 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 Technical Barriers to Trade (TBT) Committee.
ASTM C757-16(2021) is classified under the following ICS (International Classification for Standards) categories: 27.120.30 - Fissile materials and nuclear fuel technology. The ICS classification helps identify the subject area and facilitates finding related standards.
ASTM C757-16(2021) has the following relationships with other standards: It is inter standard links to ASTM C1295-24, ASTM C859-24, ASTM C1274-12(2020), ASTM B243-18, ASTM B243-16, ASTM C697-16, ASTM C1295-15, ASTM C1295-14, ASTM C859-14a, ASTM C859-14, ASTM B243-13, ASTM C859-13a, ASTM C859-13, ASTM C1274-12, ASTM B243-12. Understanding these relationships helps ensure you are using the most current and applicable version of the standard.
ASTM C757-16(2021) is available in PDF format for immediate download after purchase. The document can be added to your cart and obtained through the secure checkout process. Digital delivery ensures instant access to the complete standard document.
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:C757 −16 (Reapproved 2021)
Standard Specification for
Nuclear-Grade Plutonium Dioxide Powder for Light Water
Reactors
This standard is issued under the fixed designation C757; 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 plutonium
dioxide (PuO ) powder. It recognizes the diversity of manufacturing methods by which PuO powders
2 2
are produced and the many special requirements for chemical and physical characterization that may
beapplicableforaparticularMixedOxide(MOX,thatis(U,Pu)O )fuelpelletmanufacturingprocess
or imposed by the end user of the powder in different light water reactors. It is, therefore, anticipated
that the buyer may supplement this specification with more stringent or additional requirements for
specific applications.
1. Scope 1.4 The values stated in SI units are to be regarded as
standard. No other units of measurement are included in this
1.1 This specification covers nuclear grade PuO powder. It
standard.
applies to PuO of various isotopic compositions as normally
1.5 This standard does not purport to address all of the
prepared by in-reactor neutron irradiation of natural or slightly
safety concerns, if any, associated with its use. It is the
enriched uranium or by in-reactor neutron irradiation of
responsibility of the user of this standard to establish appro-
recycled plutonium mixed with uranium.
priate safety, health, and environmental practices and deter-
1.2 There is no discussion of or provision for preventing mine the applicability of regulatory limitations prior to use.
criticality incidents, nor are health and safety requirements, the 1.6 This international standard was developed in accor-
avoidance of hazards, or shipping precautions and controls dance with internationally recognized principles on standard-
discussed. Observance of this specification does not relieve the ization established in the Decision on Principles for the
Development of International Standards, Guides and Recom-
user of the obligation to be aware of and conform to all
mendations issued by the World Trade Organization Technical
applicable international, national, or federal, state, and local
Barriers to Trade (TBT) Committee.
regulations pertaining to possessing, shipping, processing, or
using source or special nuclear material. For examples in the
2. Referenced Documents
U.S. Government, relevant documents are Code of Federal
2.1 ASTM Standards:
Regulations, Title 10 Nuclear Safety Guide, U.S. Atomic
B243 Terminology of Powder Metallurgy
Energy Commission Report TID-7016 , and “Handbook of
C697 Test Methods for Chemical, Mass Spectrometric, and
Nuclear Safety”, H. K. Clark, U.S. Atomic Energy Commis-
Spectrochemical Analysis of Nuclear-Grade Plutonium
sion Report, DP-532 .
Dioxide Powders and Pellets
1.3 The PuO shall be produced by a qualified process and
2 C859 Terminology Relating to Nuclear Materials
in accordance with a quality assurance program approved by
C1233 Practice for Determining Equivalent Boron Contents
the user.
of Nuclear Materials
C1274 Test Method forAdvanced Ceramic Specific Surface
Area by Physical Adsorption
1 C1295 Test Method for Gamma Energy Emission from
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 Fission and Decay Products in Uranium Hexafluoride and
and Fertile Material Specifications.
Current edition approved Oct. 1, 2021. Published October 2021. Originally
ɛ1
approved in 1974. Last previous edition approved in 2016 as C757 – 16 . DOI: For referenced ASTM standards, visit the ASTM website, www.astm.org, or
10.1520/C0757-16R21. contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Available from Superintendent of Documents, U.S. Government Printing Standards volume information, refer to the standard’s Document Summary page on
Office, 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20402. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
C757−16 (2021)
Uranyl Nitrate Solution 5.5 Impurity Content—The impurity content shall not ex-
C1770 Test Method for Determination of Loose and ceed the individual element limit specified in Table 1onaPu
Tapped Bulk Densities of Small Quantities of Plutonium basis. Total non-volatile oxide impurity content excluding Am
Oxide shall not exceed 6000 µg/g Pu. Some other elements such as
E105 Guide for Probability Sampling of Materials
thoselistedinTable2mayalsobeofconcernforthebuyerand
should be measured and reported if requested. If an element
2.2 ASME Standard:
analysis is reported as “less than” a given concentration, this
ASME NQA-1 QualityAssurance Requirements for Nuclear
“less than” value shall be used in the determination of total
Facility Applications
impurities. Impurity elements measured and their associated
2.3 U.S. Government Documents:
limits may differ from what is listed in this specification as
Code of Federal Regulations, Title 10, Nuclear Safety
agreed upon between the buyer and seller.
Guide, U.S. Atomic Energy Commission Report TID-
7016 5.6 Moisture Content—The moisture content shall be mea-
“Handbook of Nuclear Safety,” Clark, H. K., U.S. Atomic sured and reported on a Pu basis. The maximum acceptable
Energy Commission Report, DP-532 moisture content shall be agreed upon between the buyer and
the seller.
2.4 ISO Standard:
ISO 8300 Determination of Pu Content in Plutonium Diox-
5.7 Equivalent Boron Content—For thermal reactor use, the
ide (PuO ) of Nuclear Grade Quality, Gravimetric Method
2 total equivalent boron content (EBC) shall not exceed 20.0
ISO 9161 Uranium Dioxide Powder—Determination ofAp-
µg/g on a Pu basis. The method of performing the calculation
parent Density and Tap Density
shallbeasindicatedinPracticeC1233.Forfastreactoruse,the
ISO 13463 Nuclear-grade Plutonium Dioxide Powder for
above limitation on EBC does not apply.
Fabrication of Light Water Reactor MOX Fuel—
5.8 Gamma Activity—The gamma activity (Bq/g Pu) of the
Guidelines to Help in the Definition of a Product Speci-
gamma emitting fission products whose isotopes have half
fication
lives of 30 days or greater shall be measured. The gamma
radiation from fission products shall be less than 10
3. Terminology
MeV·Bq/g Pu.
3.1 Definitions—Definitions of terms are as given in Termi-
5.8.1 The list of nuclides and mean energies per disintegra-
nologies B243 and C859.
tion found in Test Method C1295 are to be used in the
calculations.
4. Isotopic Content
4.1 Concentrations and homogeneity ranges of the pluto-
nium (Pu) shall be as specified by the buyer.
4.2 The isotopic composition of the final product shall be TABLE 1 Impurity Elements and Maximum Concentration Limits
determined by a method to be agreed upon between the buyer
Maximum Concentration
C
Element Limit
and seller and shall be reported on a Pu basis including the
of Plutonium, µg/gPu
associated measurement uncertainties. The date of the deter-
Aluminum (Al) 300
mination will be indicated.
Boron (B) 3
Cadmium (Cd) 3
A
Carbon (C) 500
5. Chemical Composition
Chlorine (Cl) 300
5.1 Plutonium Content—The minimum Pu content shall be
Chromium (Cr) 200
Dysprosium (Dy) 0.5
86.0 weight % including measurement uncertainties as
Europium (Eu) 0.5
sampled on the date of sampling.
Fluorine (F) 200
Iron (Fe) 500
5.2 Uranium Content—The uranium content of the PuO
Gadolinium (Gd) 3
shall be measured and reported on a Pu basis.
Magnesium (Mg) 200
Molybdenum (Mo) 100
5.3 Americium Content—The americium (Am) content shall
Nickel (Ni) 200
be measured and reported on a Pu basis. The maximum
Nitrogen (N) 300
Samarium (Sm) 2
acceptableAm content shall be agreed upon between the buyer
Silicon (Si) 200
and seller.
Sodium (Na) 100
Titanium (Ti) 100
5.4 The dates of analyses of U, Th and Am shall be
B
Thorium (Th) 50
recorded.
Tungsten (W) 100
Z
...
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