ASTM C1065-93

Standard Specification for Nuclear-Grade Zirconium Oxide Powder (Withdrawn 1994)

SCOPE
1.1 This specification defines the physical and chemical requirements for zirconium oxide powder intended for fabrication into shapes, either entirely or partially of zirconia, for use in a nuclear reactor core.  
1.2 The material described herein shall be particulate in nature.  
1.3 The values stated in SI units are to be regarded as the standard.

General Information

• Status: Historical
• Publication Date: 31-Dec-1992
• 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

• Replaced By: ASTM C1065-08 - Standard Specification for Nuclear-Grade Zirconium Oxide Powder
• Effective Date: 01-Dec-2008
• Referred By: ASTM C1066-09(2022) - Standard Specification for Nuclear Grade Zirconium Oxide Pellets
• Effective Date: 01-Jan-1993

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NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.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: C 1065 – 93
Standard Specification for
Nuclear-Grade Zirconium Oxide Powder
This standard is issued under the fixed designation C 1065; 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 (e) indicates an editorial change since the last revision or reapproval.
1. Scope 3.4 powder lot—a specified quantity of zirconium oxide
powder (with stabilizing additive, if applicable) blended to-
1.1 This specification defines the physical and chemical
gether such that samples taken in accordance with the proce-
requirements for zirconium oxide powder intended for fabri-
dures of Section 8 can be considered as representative of the
cation into shapes, either entirely or partially of zirconia, for
entire specified quantity.
use in a nuclear reactor core.
3.5 seller—the zirconium oxide processor.
1.2 The material described herein shall be particulate in
3.6 stabilizing additive—a material which, when added in
nature.
sufficient quantity to the subject material exhibiting the phase
1.3 The values stated in SI units are to be regarded as the
transformation, produces a stabilized crystalline phase that
standard.
does not undergo a transformation at any temperature within
2. Referenced Documents the expected fabrication or usage regime of the manufactured
product; the potentially deleterious volume change is therefore
2.1 ASTM Standards:
avoided.
C 859 Terminology Relating to Nuclear Materials
E 11 Specification for Wire-Cloth Sieves for Testing Pur-
4. Ordering Information
poses
3 4.1 The buyer may specify the following information on the
E 105 Practice for Probability Sampling of Materials
order:
2.2 ANSI Standard:
4.1.1 Quantity (weight of delivered product).
ANSI/ASME NQA-1 Quality Assurance Program Require-
4.1.2 Nominal particle size range and applicable tolerances
ments for Nuclear Facilities
in accordance with U.S. Standard Sieve Series (Specification
2.3 U.S. Government Standard:
E 11). For particle sizes less than 280 mesh, the particle size
Code of Federal Regulations, Title 10, Part 50, Energy
distribution will be determined using a method agreed upon
(10 CFR 50) Domestic Licensing of Production and Uti-
between the buyer and the seller.
lization Facilities
4.1.3 Stabilizing Additive—The amount and types of stabi-
3. Terminology
lizing additives (if any, including limits).
4.1.4 Lot size.
3.1 Terms shall be defined in accordance with Terminology
4.1.5 Sampling requirements.
C 859 except for the following:
3.2 buyer—the organization issuing the purchase order.
5. Chemical Composition
3.3 phase transformation—the rearrangement of the atomic
5.1 A stabilizing additive may be used with the zirconium
ordering of a crystalline lattice as a material is cycled through
oxide. The recommended stabilizing additive is either calcium
a critical transformation or inversion temperature. The change
oxide (CaO) or yttrium oxide (Y O ). The recommended
from one crystalline phase to another may be accompanied by 2 3
additive concentration in the case of CaO stabilization is 4 to
a volume change that could lead to cracks or defects in
8 weight %. In the case of Y O stabilization, the recom-
products fabricated from such materials. 2 3
mended additive concentration is 14 to 20 weight %.
5.2 Use analytical chemistry methods as agreed upon be-
This specification is under the jurisdiction of ASTM Committee C-26 on
tween the buyer and the seller.
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C 26.03 on
5.3 Impurity Concentration—The impurity concentration
Neutron Absorber Materials Specifications.
excluding the stabilizing additives shall not exceed 0.5
Current edition approved April 15, 1993. Published June 1993. Originally
published as C 1065 – 87. Last previous edition C 1065 – 87.
weight %. Individual element limits are specified in Table 1.
Annual Book of ASTM Standards, Vol 12.01.
The buyer may specify additional limits for any other elements
Annual Book of ASTM Standards, Vol 14.02.
4 not listed in Table 1.
Available from theAmerican National Standards Institute, 11W. 42nd St., 13th
Floor, New York, NY 10036.
Available from Superintendent of Documents, U.S. Government Printing
Office, Washington, DC 20402.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
C 1065
TABLE 1 Impurity Concentration Limits
6. Physical Requirements
Maximum Concentration
Element 6.1 The particle size distribution shall be agreed upon
Limit (µg/g Powder)
between the buyer and the seller.
Hf 200
B 100
7. Cleanliness
Gd 50
Gd+Sm+Eu+Dy 200
7.1 The powder shall be handled in a manner to avoid
Co 100
contamination by foreign matter such as dust, cleaning agents
Si 2000
F30
and organics, and materials such as plastics and paper used in
F+Cl+Br+I 100
packaging. Cleaning solutions, if used, shall be free of halides
Fe 1000
A
or nonvolatile additives and shall be removed from the powder
Ca 3000
Mg 1200
prior to sampling and packaging.
Al 1500
Ti 100
8. Sampling
Th 400
A
8.1 Sampling plans to meet acceptance criteria and inspec-
This number will be higher if used as a stabilizing additive.
tion and measurement procedures that describe the method of
compliance with this specification shall be established by the
seller and submitted to the buyer for approval. The degree of
5.4 The total equivalent boron content (EBC) of those
sampling where not specified in this specification varies with
impuritieslistedinTable2shallnotexceed500µg/gonamass
the application and, for this r
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