ASTM B811-13e1

Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding

ABSTRACT
This specification covers seamless wrought zirconium-alloy tubes for nuclear reactor fuel cladding application. Two grades of reactor grade zirconium alloys are described. Tubes covered by this specification shall be made from ingots produced by multiple vacuum arc or electron beam melting in furnaces of a type conventionally used for reactive materials. The tubes shall conform to the requirements for chemical composition prescribed. Recrsytallisation annealed tubes shall conform to the requirements for mechanical properties at room temperature prescribed. The tension test shall be conducted. Yield strength and tension properties shall be determined. Burst testing, when specified, shall be performed at room temperature on finished tubing.
SCOPE
1.1 This specification covers seamless wrought zirconium-alloy tubes for nuclear fuel cladding application, in the outside diameter (OD) size range of 0.200 in. (5.1 mm) to 0.650 in. (16.5 mm) and wall thickness range of 0.010 in. (0.25 mm) to 0.035 in. (0.89 mm).  
1.2 Two grades of reactor grade zirconium alloys are described.  
1.2.1 The present UNS numbers designated for the two grades are given in Table 1.  
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.

General Information

• Status: Historical
• Publication Date: 30-Apr-2013
• ICS: 23.040.15 - Non-ferrous metal pipes
• Technical Committee: B10 - Reactive and Refractory Metals and Alloys
• Drafting Committee: B10.02 - Zirconium and Hafnium

Relations

• Replaces: ASTM B811-13 - Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding
• Effective Date: 01-May-2013
• Referred By: ASTM B353-12(2022)e1 - Standard Specification for Wrought Zirconium and Zirconium Alloy Seamless and Welded Tubes for Nuclear Service (Except Nuclear Fuel Cladding)
• Effective Date: 01-May-2013

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
´1
Designation:B811 −13
Standard Specification for
Wrought Zirconium Alloy Seamless Tubes for Nuclear
1
Reactor Fuel Cladding
This standard is issued under the fixed designation B811; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1
ε NOTE—Equations in Section A4.5 were corrected editorially in August 2014.
1. Scope (Except Nuclear Fuel Cladding)
E8Test Methods for Tension Testing of Metallic Materials
1.1 This specification covers seamless wrought zirconium-
E8MTestMethodsforTensionTestingofMetallicMaterials
alloy tubes for nuclear fuel cladding application, in the outside
3
[Metric] (Withdrawn 2008)
diameter (OD) size range of 0.200 in. (5.1 mm) to 0.650 in.
E21TestMethodsforElevatedTemperatureTensionTestsof
(16.5 mm) and wall thickness range of 0.010 in. (0.25 mm) to
Metallic Materials
0.035 in. (0.89 mm).
E29Practice for Using Significant Digits in Test Data to
1.2 Two grades of reactor grade zirconium alloys are
Determine Conformance with Specifications
described.
E112Test Methods for Determining Average Grain Size
1.2.1 The present UNS numbers designated for the two
G2/G2MTest Method for Corrosion Testing of Products of
grades are given in Table 1.
Zirconium, Hafnium, and Their Alloys in Water at 680°F
(360°C) or in Steam at 750°F (400°C)
1.3 Unlessasingleunitisused,forexamplecorrosionmass
2
gain in mg/dm , the values stated in either inch-pound or SI 2.2 Other Document:
4
ANSI B46.1Surface Texture (Surface Roughness)
units are to be regarded separately as standard. The values
stated in each system are not exact equivalents; therefore each
3. Terminology
system must be used independently of the other. SI values
3.1 Definitions of Terms Specific to This Standard:
cannot be mixed with inch-pound values.
3.1.1 dimensions, n—tube dimensions are outside diameter,
1.4 The following precautionary caveat pertains only to the
inside diameter, and wall thickness. Only two of these param-
test method portions of this specification: This standard does
eters may be specified in addition to length, except minimum
not purport to address all of the safety concerns, if any,
wallmaybespecifiedwithoutsideandinsidediameter.Ineach
associated with its use. It is the responsibility of the user of this
case, ovality and wall thickness variation (WTV) may be
standard to establish appropriate safety and health practices
specified as additional requirements.
and determine the applicability of regulatory limitations prior
3.1.2 hydride orientation fraction, Fn, n—the ratio of hy-
to use.
dride platelets oriented in the radial direction to the total
2. Referenced Documents
hydride platelets in the field examined.
2
2.1 ASTM Standards: 3.1.3 lot size, n—a lot shall consist of all tubes of the same
B350/B350MSpecification for Zirconium and Zirconium size,shape,condition,andfinishproducedfromthesameingot
Alloy Ingots for Nuclear Application by the same reduction schedule and heat treatment. The final
B353Specification for Wrought Zirconium and Zirconium heat treatment shall be in a single furnace charge.
Alloy Seamless and Welded Tubes for Nuclear Service
3.1.4 mill finish tubes, n—tubes that have received all
finishing operations subsequent to final anneal, which poten-
tially affects tube mechanical, dimensional, or surface condi-
1
This specification is under the jurisdiction of ASTM Committee B10 on
tion. These operations include, but are not limited to, pickling,
Reactive and Refractory Metals and Alloys and is the direct responsibility of
Subcommittee B10.02 on Zirconium and Hafnium. cleaning, outer and inner surface abrasive conditioning, and
Current edition approved May 1, 2013. Published May 2013. Originally
straightening.
approved in 1990. Last previous edition approved in 2007 as B811–02 (2007).
DOI: 10.1520/B0811-13E01.
2 3
For referenced ASTM standards, visit the ASTM website, www.astm.org, or The last approved version of this historical standard is referenced on
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM www.astm.org.
4
Standards volume information, refer to the standard’s Document Summary page on Available from American Iron and Steel Institute (AISI), 1140 Connecticut
the ASTM website. Ave., NW, Suite 705, Washington, DC 20036, http://www.steel.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
´1
B811−13
TABLE 1 ASTM and UNS Number Designation for Reactor Grade of seamless zirconium-alloy fuel clad tubes OD abraded and ID pickled,
Zirconium Alloys
Grade R60804, recryst
...

This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
´1
Designation: B811 − 13 B811 − 13
Standard Specification for
Wrought Zirconium Alloy Seamless Tubes for Nuclear
1
Reactor Fuel Cladding
This standard is issued under the fixed designation B811; 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 (´) indicates an editorial change since the last revision or reapproval.
1
ε NOTE—Equations in Section A4.5 were corrected editorially in August 2014.
1. Scope
1.1 This specification covers seamless wrought zirconium-alloy tubes for nuclear fuel cladding application, in the outside
diameter (OD) size range of 0.200 in. (5.1 mm) to 0.650 in. (16.5 mm) and wall thickness range of 0.010 in. (0.25 mm) to 0.035
in. (0.89 mm).
1.2 Two grades of reactor grade zirconium alloys are described.
1.2.1 The present UNS numbers designated for the two grades are given in Table 1.
2
1.3 Unless a single unit is used, for example corrosion mass gain in mg/dm , 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.
2. Referenced Documents
2
2.1 ASTM Standards:
B350/B350M Specification for Zirconium and Zirconium Alloy Ingots for Nuclear Application
B353 Specification for Wrought Zirconium and Zirconium Alloy Seamless and Welded Tubes for Nuclear Service (Except
Nuclear Fuel Cladding)
E8 Test Methods for Tension Testing of Metallic Materials
3
E8M Test Methods for Tension Testing of Metallic Materials [Metric] (Withdrawn 2008)
E21 Test Methods for Elevated Temperature Tension Tests of Metallic Materials
E29 Practice for Using Significant Digits in Test Data to Determine Conformance with Specifications
E112 Test Methods for Determining Average Grain Size
G2/G2M Test Method for Corrosion Testing of Products of Zirconium, Hafnium, and Their Alloys in Water at 680°F (360°C)
or in Steam at 750°F (400°C)
2.2 Other Document:
4
ANSI B46.1 Surface Texture (Surface Roughness)
3. Terminology
3.1 Definitions of Terms Specific to This Standard:
3.1.1 dimensions, n—tube dimensions are outside diameter, inside diameter, and wall thickness. Only two of these parameters
may be specified in addition to length, except minimum wall may be specified with outside and inside diameter. In each case,
ovality and wall thickness variation (WTV) may be specified as additional requirements.
1
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.
Current edition approved May 1, 2013. Published May 2013. Originally approved in 1990. Last previous edition approved in 2007 as B811 – 02 (2007). DOI:
10.1520/B0811-13.10.1520/B0811-13E01.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
3
The last approved version of this historical standard is referenced on www.astm.org.
4
Available from American Iron and Steel Institute (AISI), 1140 Connecticut Ave., NW, Suite 705, Washington, DC 20036, http://www.steel.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
´1
B811 − 13
TABLE 1 ASTM and UNS Number Designation for Reactor Grade
Zirconium Alloys
Grade UNS Number
Zirconium-tin alloy R60802
Zirconium-tin alloy R60804
3.1.2 hydride orientation fraction, Fn, n—the ratio of hydride platelets oriented in the radial direction to the total hydride
platelets in the field examined.
3.1.3 lot size, n—a lot shall consist of all tubes of the same size, shape, condition, and finish produced from the same ingot by
the same reduction schedule and heat treatment. The final heat treatment shall be in a sin
...