Standard Specification for Wrought Zirconium and Zirconium Alloy Seamless and Welded Tubes for Nuclear Service (Except Nuclear Fuel Cladding)

SCOPE
1.1 This specification covers seamless and welded wrought zirconium and zirconium-alloy tubes for nuclear application. Nuclear fuel cladding is covered in Specification B811.  
1.2 Five grades of reactor grade zirconium and zirconium alloys suitable for nuclear application are described.  
1.2.1 The present UNS numbers designated for the five grades are given in Table 2.
1.3 Unless a single unit is used, for example corrosion mass gain in mg/dm2, the values stated in either inch-pound or SI units are to be regarded separately as standard. The values stated in each system are not exact equivalents; therefore each system must be used independently of the other. SI values cannot be mixed with inch-pound values.
1.4 The following precautionary caveat pertains only to the test method portions of this specification.  This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

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Publication Date
09-Nov-2001
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ASTM B353-01 - Standard Specification for Wrought Zirconium and Zirconium Alloy Seamless and Welded Tubes for Nuclear Service (Except Nuclear Fuel Cladding)
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NOTICE: This standard has either been superseded and replaced by a new version or discontinued.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.
Designation: B 353 – 01
Standard Specification for
Wrought Zirconium and Zirconium Alloy Seamless and
Welded Tubes for Nuclear Service (Except Nuclear Fuel
1
Cladding)
This standard is issued under the fixed designation B 353; 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 Designations for
1. Scope
Reactor Grade Zirconium and Zirconium Alloys
1.1 This specification covers seamless and welded wrought
Grade UNS Number
zirconium and zirconium-alloy tubes for nuclear application.
Reactor-grade zirconium R60001
Nuclear fuel cladding is covered in Specification B 811.
Zirconium-tin alloy R60802
1.2 Five grades of reactor grade zirconium and zirconium
Zirconium-tin alloy R60804
Zirconium-niobium alloy R60901
alloys suitable for nuclear application are described.
Zirconium-niobium alloy R60904
1.2.1 The present UNS numbers designated for the five
grades are given in Table 1.
1.3 Unless a single unit is used, for example corrosion mass
2
E 112 Test Methods for Determining the Average Grain
gain in mg/dm , the values stated in either inch-pound or SI
3
Size
units are to be regarded separately as standard. The values
G 2 Test Method for Corrosion Testing of Products of
stated in each system are not exact equivalents; therefore each
Zirconium, Hafnium, and Their Alloys in Water at 680°F
system must be used independently of the other. SI values
5
or in Steam at 750°F
cannot be mixed with inch-pound values.
G 2M Test Method for Corrosion Testing of Products of
1.4 The following precautionary caveat pertains only to the
Zirconium, Hafnium and Their Alloys in Water at 633K or
test method portions of this specification. This standard does
5
in Steam at 673K [Metric]
not purport to address all of the safety concerns, if any,
2.2 ANSI Standard:
associated with its use. It is the responsibility of the user of this
6
ANSI B46.1 Surface Texture (Surface Roughness)
standard to establish appropriate safety and health practices
and determine the applicability of regulatory limitations prior
3. Terminology
to use.
3.1 Definitions of Terms Specific to This Standard:
3.1.1 dimensions, n—tube dimensions are outside diameter,
2. Referenced Documents
inside diameter, and wall thickness. Only two of these param-
2.1 ASTM Standards:
eters may be specified in addition to length, except minimum
B 350 Specification for Zirconium and Zirconium Alloy
2
wall may be specified with outside and inside diameter. In each
Ingots for Nuclear Application
case, ovality and wall thickness variation (WTV) may be
B 811 Specification for Wrought Zirconium Alloy Seamless
2
specified as additional requirements.
Tubes for Nuclear Reactor Fuel Cladding
3 3.1.2 hydride orientation fraction, Fn, n—the ratio of hy-
E 8 Test Methods for Tension Testing of Metallic Materials
dride platelets oriented in the radial direction to the total
E 21 Test Methods for Elevated Temperature Tension Tests
3 hydride platelets in the field examined.
of Metallic Materials
3.1.3 Lot Definitions:
E 29 Practice for Using Significant Digits in Test Data to
4 3.1.3.1 castings—a lot shall consist of all castings produced
Determine Conformance with Specifications
from the same pour.
3.1.3.2 ingot—no definition required.
3.1.3.3 rounds, flats, tubes, and wrought powder metallur-
1
This specification is under the jurisdiction of ASTM Committee B10 on
gical products (single definition, common to nuclear and
Reactive and Refractory Metals and Alloysand is the direct responsibility of
non-nuclear standards)—a lot shall consist of a material of the
Subcommittee B10.02on Zirconium and Hafnium.
Current edition approved Nov. 10, 2001. Published January 2002. Originally
published as B 353 – 60 T. Last previous edition B 353 – 00.
2 5
Annual Book of ASTM Standards, Vol 02.04. Annual Book of ASTM Standards, Vol 03.02.
3 6
Annual Book of ASTM Standards, Vol 03.01. Available from American National Standards Institute, 11 W. 42nd St., 13th
4
Annual Book of ASTM Standards, Vol 14.02. Floor, New York, NY 10036.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

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B 353
same size, shape, condition, and finish produced from the same 4.1.5 Method of manufacture (seamless or welded),
ingot or powder blend by the same reduction schedule and the
4.1.6 ASTM designation and year of issue,
same heat treatment parameters. Unless otherwise agreed
4.1.7 Surface finish on the inside (ID) and the outside (OD)
between manufacturer and purchaser, a lot shall be limited to
surfaces
...

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