ASTM C1066-09(2022)

Standard Specification for Nuclear Grade Zirconium Oxide Pellets

ABSTRACT
This specification applies to pellets of stabilized zirconium oxide used in nuclear reactors. The chemical composition requirements such as the stabilizing additive (calcium oxide or yttrium oxide), analytical chemistry methods, impurity concentration (including hafnium, boron, gadolinium, samarium, europium, dysprosium, cobalt, silicon, iron, calcium, magnesium, aluminum, titanium, thorium, fluorine, chlorine, bromine, iodine, and hydrogen), and moisture concentration are prescribed. The nuclear grade pellets shall conform to the specified physical requirements which includes the following: physical dimensions, density, mechanical properties and test methods such as compressive test and thermal cycling test, and visual appearance such as end chips, circumferential chips, cracks, and fissures. The requirements for cleanliness before and after sampling and packaging are given.
SCOPE
1.1 This specification applies to pellets of stabilized zirconium oxide used in nuclear reactors.  
1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.  
1.3 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-Jun-2022
• ICS: 27.120.30 - Fissile materials and nuclear fuel technology
• ICS: 71.060.20 - Oxides
• Technical Committee: C26 - Nuclear Fuel Cycle
• Drafting Committee: C26.03 - Neutron Absorber Materials Specifications

Relations

• Refers: ASTM C859-24 - Standard Terminology Relating to Nuclear Materials
• Effective Date: 01-Jan-2024
• Refers: ASTM C559-16(2020) - Standard Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite Articles
• Effective Date: 01-May-2020
• Refers: ASTM C559-16 - Standard Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite Articles
• Effective Date: 01-Jan-2016
• Refers: ASTM C859-14a - Standard Terminology Relating to Nuclear Materials
• Effective Date: 15-Jun-2014
• Refers: ASTM C859-14 - Standard Terminology Relating to Nuclear Materials
• Effective Date: 15-Jan-2014
• Refers: ASTM C859-13a - Standard Terminology Relating to Nuclear Materials
• Effective Date: 01-Jun-2013
• Refers: ASTM C859-13 - Standard Terminology Relating to Nuclear Materials
• Effective Date: 01-May-2013
• Refers: ASTM C859-10b - Standard Terminology Relating to Nuclear Materials
• Effective Date: 01-Nov-2010
• Refers: ASTM E105-10 - Standard Practice for Probability Sampling Of Materials
• Effective Date: 01-Oct-2010
• Refers: ASTM C859-10a - Standard Terminology Relating to Nuclear Materials
• Effective Date: 01-Aug-2010
• Refers: ASTM C559-90(2010) - Standard Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite Articles
• Effective Date: 01-May-2010
• Refers: ASTM C859-10 - Standard Terminology Relating to Nuclear Materials
• Effective Date: 01-Feb-2010
• Refers: ASTM C859-09 - Standard Terminology Relating to Nuclear Materials
• Effective Date: 15-Feb-2009
• Refers: ASTM C1065-08 - Standard Specification for Nuclear-Grade Zirconium Oxide Powder
• Effective Date: 01-Dec-2008
• Refers: ASTM C859-08 - Standard Terminology Relating to Nuclear Materials
• Effective Date: 15-Sep-2008

Overview

ASTM C1066-09(2022) - Standard Specification for Nuclear Grade Zirconium Oxide Pellets sets out requirements for pellets of stabilized zirconium oxide designed for use in nuclear reactors. This ASTM standard specifies chemical composition, physical properties, impurity limits, and testing methods to ensure that zirconium oxide pellets meet the strict criteria necessary for nuclear applications. The standard supports quality assurance across the nuclear fuel cycle, minimizing impurities and defects, and lays out standards for packaging, cleanliness, and certification.

Key Topics

• Chemical Composition:

  • Pellets must be made from zirconium oxide powder stabilized with calcium oxide (CaO) or yttrium oxide (Y₂O₃).
  • Specifies recommended additive concentrations and maximum permissible impurity levels, including elements such as hafnium, boron, gadolinium, samarium, cobalt, iron, and more.
  • Analytical chemistry methods for composition assessment must be agreed upon between buyer and supplier.

• Physical Properties and Testing:

  • Requirements for pellet dimensions, density, appearance, and mechanical integrity.
  • Mechanical property validation through compression and, where required, thermal cycling tests.
  • Visual standards define permissible defects, including chips and cracks.

• Cleanliness and Sampling:

  • Finished pellets must be free from contamination due to handling, packaging, or cleaning processes.
  • Sampling plans for quality verification, acceptance, and archiving must be agreed upon and documented.

• Inspection, Certification, and Packaging:

  • The supplier must certify that each pellet lot complies with the standard, provide test results, and ensure packaging prevents contamination or damage during shipping.
  • Each package must be clearly marked with critical identification details.

Applications

• Nuclear Reactor Fuel Fabrication:
  Nuclear grade zirconium oxide pellets are primarily used as a structural or functional ceramic in nuclear reactors, ensuring reliable performance under high-temperatures and radiation exposure.

• Quality Assurance in Nuclear Supply Chains:
  By adhering to ASTM C1066-09(2022), suppliers and manufacturers maintain consistency, traceability, and safety in the production-and procurement-of zirconium oxide pellets for nuclear facilities.

• Regulatory Compliance:
  This standard supports compliance with international and federal regulations, including those laid out in 10 CFR 50 (Code of Federal Regulations - Energy) and guides on quality assurance such as ANSI/ASME NQA-1.

Related Standards

• ASTM C1065:
  Specification for Nuclear-Grade Zirconium Oxide Powder, which outlines requirements for the starting powder in pellet manufacture.

• ASTM C559:
  Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite Articles, referenced for density determination.

• ASTM C859:
  Terminology Relating to Nuclear Materials, providing definitions used across related documents.

• ANSI/ASME NQA-1:
  Quality Assurance Program Requirements for Nuclear Facility Applications, used as a reference guide for quality control processes.

• 10 CFR 50:
  US Code of Federal Regulations for Domestic Licensing of Production and Utilization Facilities, essential for legal compliance in nuclear operations.

Practical Value

Adhering to ASTM C1066-09(2022) ensures that zirconium oxide pellets used in nuclear reactors meet stringent safety, quality, and performance expectations. The standard is vital for nuclear materials manufacturers, reactor operators, and supply chain partners concerned with product consistency, regulatory compliance, and end-use safety. By specifying chemical, physical, and procedural requirements for nuclear grade zirconium oxide pellets, this standard supports reliable and efficient operation within the nuclear industry.

Keywords: nuclear grade zirconium oxide pellets, ASTM C1066, stabilized zirconium oxide, nuclear reactor materials, impurity limits, density, mechanical properties, quality assurance, nuclear standards.

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:C1066 −09 (Reapproved 2022)
Standard Specification for
Nuclear Grade Zirconium Oxide Pellets
This standard is issued under the fixed designation C1066; 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.
1. Scope 3. Terminology
1.1 This specification applies to pellets of stabilized zirco- 3.1 Terms shall be defined in accordance with Terminology
nium oxide used in nuclear reactors. C859, except for the following:
3.2 buyer—the organization issuing the purchase order.
1.2 The values stated in SI units are to be regarded as the
standard. The values given in parentheses are for information
3.3 pellet—a fabricated geometric shape of zirconiumoxide
only.
having a chemical composition as described in Section 4.
1.3 This international standard was developed in accor-
3.4 pellet lot—the pellets produced from one zirconium
dance with internationally recognized principles on standard-
oxide powder lot using one set of process parameters. Pellet lot
ization established in the Decision on Principles for the
size shall be agreed upon between the seller and the buyer.
Development of International Standards, Guides and Recom-
3.5 phase transformation—the rearrangement of the atomic
mendations issued by the World Trade Organization Technical
ordering of a crystalline lattice as a material is cycled through
Barriers to Trade (TBT) Committee.
a critical transformation or inversion temperature. The change
from one crystalline phase to another may be accompanied by
2. Referenced Documents
a volume change that could lead to cracks or defects in articles
2.1 ASTM Standards:
fabricated from such materials.
C559 Test Method for Bulk Density by Physical Measure-
3.6 powder lot—a specified quantity of zirconium-oxide
ments of Manufactured Carbon and Graphite Articles
powder with stabilizing additive, blended together such that
C859 Terminology Relating to Nuclear Materials
samples taken in accordance with Section 7 can be considered
C1065 Specification for Nuclear-Grade Zirconium Oxide
as representative of the entire quantity.
Powder
3.7 seller—the zirconium oxide pellet supplier.
E105 Guide for Probability Sampling of Materials
3.8 stabilizing additive—A material which, when present in
2.2 ANSI Standard:
sufficient concentration in the subject material exhibiting the
ANSI/ASME NQA-1 Quality Assurance Program Require-
phase transformation, produces a stabilized crystalline phase
ments for Nuclear Facility Applications
that does not undergo a transformation or inversion at any
2.3 U.S. Government Document:
temperature within the expected fabrication or usage regime of
Code of Federal Regulations, Title 10, Part 50–Energy (10
the manufactured pellet. The potentially deleterious volume
CFR 50) Domestic Licensing of Production and Utiliza-
change is therefore avoided.
tion Facilities
4. Chemical Composition
4.1 The starting zirconium oxide powder shall be in accor-
dance with Specification C1065.
This specification is under the jurisdiction of ASTM Committee C26 on
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.03 on
4.2 A stabilizing additive shall be used with the zirconium
Neutron Absorber Materials Specifications.
oxide. The recommended stabilizing additive is either calcium
Current edition approved July 1, 2022. Published July 2022. Originally approved
in 1986. Last previous edition approved in 2015 as C1066 – 09 (2015). DOI:
oxide (CaO) or yttrium oxide (Y O ). The recommended
2 3
10.1520/C1066-09R22.
additive concentration in the case of CaO stabilization is 4 to
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
8 weight %. In the case of Y O stabilization, the recom-
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM 2 3
Standards volume information, refer to the standard’s Document Summary page on mended additive concentration is 14 to 20 weight %.
the ASTM website.
3 4.3 Use analytical chemistry methods as agreed upon be-
Available from American National Standards Institute (ANSI), 25 W. 43rd St.,
4th Floor, New York, NY 10036, http://www.ansi.org. tween the buyer and seller.
AvailablefromU.S.GovernmentPrintingOfficeSuperintendentofDocuments,
4.4 The impurity concentration excluding the stabilizing
732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http://
www.access.gpo.gov. additives, shall not exceed 0.5 weight %. Individual element
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
C1066−09 (2022)
limits are specified in Table 1. The buyer may specify Sampling. The seller and the buyer shall agree on visual
additional limits for any other elements not listed in Table 1. standards as representing the requirements of 5.4.1, 5.4.2, and
5.4.3.Thesestandardsshallbeusedasacceptancestandardsfor
4.5 The moisture concentration is included in the total
the visual examination of the pellets. In the event of a dispute,
hydrogen limit (see Table 1).
the method of defect measurement shall be approved by the
buyerpriortouse.Maximumpermissibledefectsaredefinedas
5. Physical Requirements
follows:
5.1 Physical Dimensions:
5.4.1 End Chips—Pellet end surface shall not be chipped
5.1.1 Dimensional requirements shall be in accordance with
beyond 10 % of the end-face surface area, and no chip shall
applicable drawings and purchase order documents.
exceed 1.02 mm (0.040 in.) in depth.
5.1.2 Pellet dimensions shall be measured to ensure com-
5.4.2 Circumferential Chips—Pellet circumferential sur-
pliance with the buyer’s requirements. Sampling plans to meet
faces shall not be chipped beyond 5 % of the circumferential
the acceptance criteria shall be agreed upon between the buyer
surface area. No single chip shall exceed a depth of 1.02 mm
and the seller to ensure that the pellets represented by the
(0.040 in.).
sample are within the required tolerance.
5.4.3 Cracks—Cracks are acceptable, providing the total
5.2 Density:
length of all cracks does not exceed 90 degrees of
5.2.1 Pellet density limits shall be specified by the buyer.
circumference, and other requirements of the specification are
The incorporation of a stabilizing additive will int
...