ASTM C1066-97
(Specification)Standard Specification for Nuclear Grade Zirconium Oxide Pellets
Standard Specification for Nuclear Grade Zirconium Oxide Pellets
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.
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NOTICE: This standard has either been superceded and replaced by a new version or discontinued.
Contact ASTM International (www.astm.org) for the latest information.
Designation: C 1066 – 97
Standard Specification for
Nuclear Grade Zirconium Oxide Pellets
This standard is issued under the fixed designation C 1066; 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 through a critical transformation or inversion temperature. The
change from one crystalline phase to another may be accom-
1.1 This specification applies to pellets of stabilized zirco-
panied by a volume change that could lead to cracks or defects
nium oxide used in nuclear reactors.
in articles fabricated from such materials.
1.2 The values stated in SI units are to be regarded as the
3.1.5 powder lot—a specified quantity of zirconium-oxide
standard. The values given in parentheses are for information
powder with stabilizing additive, blended together such that
only.
samples taken in accordance with Section 7 can be considered
2. Referenced Documents as representative of the entire quantity.
3.1.6 seller—the zirconium oxide pellet supplier.
2.1 ASTM Standards:
3.1.7 stabilizing additive—A material which, when present
C 559 Test Method for Bulk Density by Physical Measure-
in sufficient concentration in the subject material exhibiting the
ments of Manufactured Carbon and Graphite Articles
phase transformation, produces a stabilized crystalline phase
C 859 Terminology Relating to Nuclear Materials
that does not undergo a transformation or inversion at any
C 1065 Specification for Nuclear Grade Zirconium Oxide
temperature within the expected fabrication or usage regime of
Powder
the manufactured pellet. The potentially deleterious volume
E 105 Practice for Probability Sampling of Materials
change is therefore avoided.
2.2 ANSI Standard:
ANSI/ASME NQA-1 Quality Assurance Program Require-
4. Chemical Composition
ments for Nuclear Facility Applications
4.1 The starting zirconium oxide powder shall be in accor-
2.3 U.S. Government Document:
dance with Specification C 1065.
Code of Federal Regulations, Title 10, Part 50–Energy (10
4.2 A stabilizing additive shall be used with the zirconium
CFR 50) Domestic Licensing of Production and Utiliza-
oxide. The recommended stabilizing additive is either calcium
tion Facilities
oxide (CaO) or yttrium oxide (Y O ). The recommended
2 3
3. Terminology additive concentration in the case of CaO stabilization is 4 to
8 weight %. In the case of Y O stabilization, the recom-
3.1 Terms shall be defined in accordance with Terminology 2 3
mended additive concentration is 14 to 20 weight %.
C 859, except for the following:
4.3 Use analytical chemistry methods as agreed upon be-
3.1.1 buyer—the organization issuing the purchase order.
tween the buyer and seller.
3.1.2 pellet—a fabricated geometric shape of zirconiumox-
4.4 The impurity concentration excluding the stabilizing
ide having a chemical composition as described in Section 4.
additives, shall not exceed 0.5 weight %. Individual element
3.1.3 pellet lot—the pellets produced from one zirconium
limits are specified in Table 1. The buyer may specify addi-
oxide powder lot using one set of process parameters. Pellet lot
tional limits for any other elements not listed in Table 1.
size shall be agreed upon between the seller and the buyer.
4.5 The moisture concentration is included in the total
3.1.4 phase transformation—the rearrangement of the
hydrogen limit (see Table 1).
atomic ordering of a crystalline lattice as a material is cycled
5. Physical Requirements
This specification is under the jurisdiction of ASTM Committee C-26 on
5.1 Physical Dimensions:
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C 26.03on
5.1.1 Dimensional requirements shall be in accordance with
Neutron Absorber Materials Specifications.
applicable drawings and purchase order documents.
Current edition approved May 10, 1997. Published May 1998. Originally
5.1.2 Pellet dimensions shall be measured to ensure com-
published as C 1066 – 86. Last previous edition C 1066 – 86.
Annual Book of ASTM Standards, Vol 15.01.
pliance with the buyer’s requirements. Sampling plans to meet
Annual Book of ASTM Standards, Vol 12.01.
the acceptance criteria shall be agreed upon between the buyer
Annual Book of ASTM Standards, Vol 14.02.
and the seller to ensure that the pellets represented by the
Available from American National Standards Institute, 11 W. 42nd St., 13th
Floor, New York, NY 10036. sample are within the required tolerance.
Available from 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.
NOTICE: This standard has either been superceded and replaced by a new version or discontinued.
Contact ASTM International (www.astm.org) for the latest information.
C 1066
TABLE 1 Impurity Concentration Limits
5.4.3 Cracks—Cracks not exceeding 90° of circumference
Maximum Concentration in length are acceptable provided other requirements of the
Element
Limit (μg/g pellet)
specifications are met.
Hf 200
5.4.4 Fissures and other defects shall be evaluated with
B 100
respect to the criteria of 5.4.1, 5.4.2, and 5.4.3.
Gd 50
Gd+Sm+Eu+Dy 200
Co 100 6. Cleanliness
Si 2000
6.1 The finished pellets shall be handled in a manner to
Fe 1000
A
Ca 3000
avoid contamination by grinding fluids and dust, cleaning
Mg 1200
agents, and organic materials such as plastics and paper used in
Al 1500
packaging. Cleaning solutions, if used, shall be free of halides
Ti 100
Th 400 or nonvolatile additives and shall be removed from the pellets
F30
prior to sampling and packaging.
F+Cl+Br+I 100
H (total hydrogen from all sources) 2
7. Sampling
A
This number will be higher if used as a stabilizing addition.
7.1 Sampling plans to meet the acceptance criteria and
inspection and measurement procedures that describe the
method of compliance with this specification shall be approved
5.2 Density:
by the buyer. The degree of sampling varies with the applica-
5.2.1 Pellet density limits shall be specified by the buyer.
tion and for this reason should be specified on the purchase
The incorporation of a stabilizing additive will introduce a
order. Practice E 105 is referenced as a guide.
change
...
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