ASTM C1066-97(2004)
(Specification)Standard Specification for Nuclear Grade Zirconium Oxide Pellets
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.
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NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
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Designation: C 1066 – 97 (Reapproved 2004)
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 3.1.4 phase transformation—the rearrangement of the
atomic ordering of a crystalline lattice as a material is cycled
1.1 This specification applies to pellets of stabilized zirco-
through a critical transformation or inversion temperature. The
nium oxide used in nuclear reactors.
change from one crystalline phase to another may be accom-
1.2 The values stated in SI units are to be regarded as the
panied by a volume change that could lead to cracks or defects
standard. The values given in parentheses are for information
in articles fabricated from such materials.
only.
3.1.5 powder lot—a specified quantity of zirconium-oxide
2. Referenced Documents powder with stabilizing additive, blended together such that
samples taken in accordance with Section 7 can be considered
2.1 ASTM Standards:
as representative of the entire quantity.
C 559 Test Method for Bulk Density by Physical Measure-
3.1.6 seller—the zirconium oxide pellet supplier.
ments of Manufactured Carbon and Graphite Articles
3.1.7 stabilizing additive—A material which, when present
C 859 Terminology Relating to Nuclear Materials
in sufficient concentration in the subject material exhibiting the
C 1065 Specification for Nuclear Grade Zirconium Oxide
phase transformation, produces a stabilized crystalline phase
Powder
that does not undergo a transformation or inversion at any
E 105 Practice for Probability Sampling of Materials
temperature within the expected fabrication or usage regime of
2.2 ANSI Standard:
the manufactured pellet. The potentially deleterious volume
ANSI/ASME NQA-1 Quality Assurance Program Require-
change is therefore avoided.
ments for Nuclear Facility Applications
2.3 U.S. Government Document:
4. Chemical Composition
Code of Federal Regulations, Title 10, Part 50–Energy (10
4.1 The starting zirconium oxide powder shall be in accor-
CFR 50) Domestic Licensing of Production and Utiliza-
4 dance with Specification C 1065.
tion Facilities
4.2 A stabilizing additive shall be used with the zirconium
3. Terminology oxide. The recommended stabilizing additive is either calcium
oxide (CaO) or yttrium oxide (Y O ). The recommended
3.1 Terms shall be defined in accordance with Terminology 2 3
additive concentration in the case of CaO stabilization is 4 to
C 859, except for the following:
8 weight %. In the case of Y O stabilization, the recom-
3.1.1 buyer—the organization issuing the purchase order. 2 3
mended additive concentration is 14 to 20 weight %.
3.1.2 pellet—a fabricated geometric shape of zirconiumox-
4.3 Use analytical chemistry methods as agreed upon be-
ide having a chemical composition as described in Section 4.
tween the buyer and seller.
3.1.3 pellet lot—the pellets produced from one zirconium
4.4 The impurity concentration excluding the stabilizing
oxidepowderlotusingonesetofprocessparameters.Pelletlot
additives, shall not exceed 0.5 weight %. Individual element
size shall be agreed upon between the seller and the buyer.
limits are specified in Table 1. The buyer may specify addi-
tional limits for any other elements not listed in Table 1.
This specification is under the jurisdiction of ASTM Committee C26 on
4.5 The moisture concentration is included in the total
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C 26.03 on
hydrogen limit (see Table 1).
Neutron Absorber Materials Specifications.
Current edition approved May 10, 1997. Published May 1998. Originally
5. Physical Requirements
published as C 1066 – 86. Last previous edition C 1066 – 86.
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
5.1 Physical Dimensions:
contact ASTM Customer Sevice at service@astm.org. For Annual Book of ASTM
5.1.1 Dimensional requirements shall be in accordance with
Standardsvolume information, refer to the standard’s Document Summary page on
applicable drawings and purchase order documents.
the ASTM website.
Available from American National Standards Institute, 11 W. 42nd St., 13th
Floor, New York, NY 10036.
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.
C 1066 – 97 (2004)
TABLE 1 Impurity Concentration Limits
5.4.2 Circumferential Chips—Pellet circumferential sur-
Maximum Concentration faces shall not be chipped beyond 5 % of the circumferential
Element
Limit (µg/g pellet)
surface area. No single chip shall exceed a depth of 1.02 mm
Hf 200
(0.040 in.).
B 100
5.4.3 Cracks—Cracks not exceeding 90° of circumference
Gd 50
in length are acceptable provided other requirements of the
Gd+Sm+Eu+Dy 200
Co 100
specifications are met.
Si 2000
5.4.4 Fissures and other defects shall be evaluated with
Fe 1000
A
respect to the criteria of 5.4.1, 5.4.2, and 5.4.3.
Ca 3000
Mg 1200
Al 1500
6. Cleanliness
Ti 100
Th 400
6.1 The finished pellets shall be handled in a manner to
F30
avoid contamination by grinding fluids and dust, cleaning
F+Cl+Br+I 100
agents,andorganicmaterialssuchasplasticsandpaperusedin
H (total hydrogen from all sources) 2
A packaging. Cleaning solutions, if used, shall be free of halides
This number will be higher if used as a stabilizing addition.
or nonvolatile additives and shall be removed from the pellets
prior to sampling and packaging.
5.1.2 Pellet dimensions shall be measured to ensure com-
7. Sampling
pliance with the buyer’s requirements. Sampling plans to meet
7.1 Sampling plans to meet the acceptance criteria and
the acceptance criteria shall be agreed upon between the buyer
inspection and measurement procedures that describe the
and the seller to ensure that the pellets represented by the
methodofcompliancewiththisspecificationshallbeapproved
sample are within the required tolerance.
by the buyer. The degree of
...
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