ASTM B811-01

NOTICE: This standard has either been superseded and replaced by a new version or discontinued.
Contact ASTM International (www.astm.org) for the latest information.
Designation: B 811 – 01
Standard Specification for
Wrought Zirconium Alloy Seamless Tubes for Nuclear
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Reactor Fuel Cladding
This standard is issued under the fixed designation B 811; 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.
TABLE 1 ASTM and UNS Number Designation for Reactor Grade
1. Scope
Zirconium Alloys
1.1 This specification covers seamless wrought zirconium-
Grade UNS Number
alloy tubes for nuclear fuel cladding application, in the outside
Zirconium-tin alloy R60802
diameter (OD) size range of 0.200 in. (5.1 mm) to 0.650 in.
Zirconium-tin alloy R60804
(16.5 mm) and wall thickness range of 0.010 in. (0.25 mm) to
0.035 in. (0.89 mm).
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Determine Conformance with Specifications
1.2 Two grades of reactor grade zirconium alloys are
E 112 Test Methods for Determining the Average Grain
described.
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Size
1.2.1 The present UNS numbers designated for the two
G 2 Test Method for Corrosion Testing of Products of
grades are given in Table 1.
Zirconium, Hafnium and Their Alloys in Water at 680°F or
1.3 Unless a single unit is used, for example corrosion mass
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2 in Steam at 750°F
gain in mg/dm , the values stated in either inch-pound or SI
G 2M Test Method for Corrosion Testing of Products of
units are to be regarded separately as standard. The values
Zirconium, Hafnium and Their Alloys in Water at 633°K
stated in each system are not exact equivalents; therefore each
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or in Steam at 673°K (Metric)
system must be used independently of the other. SI values
2.2 Other Document:
cannot be mixed with inch-pound values.
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ANSI B46.1 Surface Texture (Surface Roughness)
1.4 The following precautionary caveat pertains only to the
test method portions of this specification: This standard does
3. Terminology
not purport to address all of the safety concerns, if any,
3.1 Definitions of Terms Specific to This Standard:
associated with its use. It is the responsibility of the user of this
3.1.1 dimensions—tube dimensions are outside diameter,
standard to establish appropriate safety and health practices
inside diameter, and wall thickness. Only two of these param-
and determine the applicability of regulatory limitations prior
eters may be specified in addition to length, except minimum
to use.
wall may be specified with outside and inside diameter. In each
case, ovality and wall thickness variation (WTV) may be
2. Referenced Documents
specified as additional requirements.
2.1 ASTM Standards:
3.1.2 hydride orientation fraction, Fn—the ratio of hydride
B 350 Specification for Zirconium and Zirconium Alloy
2 platelets oriented in the radial direction to the total hydride
Ingots for Nuclear Application
platelets in the field examined.
B 353 Specification for Wrought Zirconium and Zirconium
3.1.3 lot size—a lot shall consist of all tubes of the same
Alloy Seamless and Welded Tubes for Nuclear Service
size, shape, condition, and finish produced from the same ingot
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Except Nuclear Fuel Cladding
3 by the same reduction schedule and heat treatment. The final
E 8 Test Methods for Tension Testing of Metallic Materials
heat treatment shall be in a single furnace charge.
E 21 Test Methods for Elevated Temperature Tension Tests
3 3.1.4 mill finish tubes—tubes that have received all finish-
of Metallic Materials
ing operations subsequent to final anneal, which potentially
E 29 Practice for Using Significant Digits in Test Data to
affects tube mechanical, dimensional, or surface condition.
These operations include, but are not limited to, pickling,
cleaning, outer and inner surface abrasive conditioning, and
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straightening.
This specification is under the jurisdiction of ASTM Committee B10 on
Reactive and Refractory Metals and Alloys and is the direct responsibility of
Subcommittee B10.02 on Zirconium and Hafnium.
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Current edition approved Nov. 10, 2001. Published January 2002. Originally Annual Book of ASTM Standards, Vol 14.02.
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published as B 811 – 90. Last previous edition B 811 – 97. Annual Book of ASTM Standards, Vol 03.02.
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Annual Book of ASTM Standards, Vol 02.04. Available from American National Standards Institute, 11 W. 42nd St., 13th
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Annual Book of ASTM Standards, Vol 03.01. Floor, New York, NY 10036.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
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NOTICE: This standard has either been superseded and replaced by a new version or discontinued.
Contact ASTM International (www.astm.org) for the latest information.
B811
3.1.5 ovality—the difference between the maximum and 4.2 In addition to the i
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