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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

General Information

Status
Published
Publication Date
31-Mar-2022

Relations

Effective Date
01-Jan-2019
Effective Date
01-Oct-2016
Effective Date
15-Nov-2012
Effective Date
01-Nov-2012
Effective Date
01-Sep-2011
Effective Date
01-Sep-2011
Effective Date
01-Apr-2011
Effective Date
01-Nov-2010
Effective Date
01-Apr-2009
Effective Date
01-Oct-2008
Effective Date
01-May-2007
Effective Date
15-Nov-2006
Effective Date
23-Oct-2006
Effective Date
15-Sep-2006
Effective Date
01-Sep-2006

Overview

ASTM B811-13(2022)e1 specifies the requirements for seamless wrought zirconium alloy tubes used in nuclear reactor fuel cladding. Developed by ASTM International, this standard provides comprehensive guidelines for manufacturing, testing, inspection, and certification of zirconium alloy tubing to ensure their suitability for nuclear fuel cladding applications. Two grades of reactor-grade zirconium alloys are covered, recognizing their widespread use for safety and performance in nuclear reactors. The specification establishes requirements for key mechanical and chemical properties, dimensional tolerances, surface finishes, and inspection procedures, ensuring that the tubes meet stringent nuclear industry standards.

Key Topics

  • Scope and Size Range: This standard applies to seamless zirconium-alloy tubes for nuclear fuel cladding, with outside diameters from 0.200 in. (5.1 mm) to 0.650 in. (16.5 mm) and wall thicknesses from 0.010 in. (0.25 mm) to 0.035 in. (0.89 mm).
  • Zirconium Alloy Grades: The standard describes two grades, identified by their respective UNS numbers (R60802 and R60804), each with specific chemical composition requirements.
  • Manufacturing Requirements: Tubes must be produced from ingots melted in multiple vacuum arc or electron beam furnaces designed for reactive materials, following strict process controls.
  • Chemical Composition: Detailed limits for alloying elements and impurities are specified to ensure corrosion resistance and material integrity in nuclear environments.
  • Mechanical Properties: Requirements include yield strength, tensile strength, elongation, and burst properties for recrystallization annealed tubes, verified through standardized tension and burst tests.
  • Inspection and Testing: Comprehensive inspection procedures include ultrasonic flaw detection, surface inspection, dimensional checks, and representative sampling for laboratory testing.
  • Documentation and Certification: Manufacturers must provide certification reports confirming compliance with all aspects of the specification, including test results for chemical analysis and mechanical performance.

Applications

  • Nuclear Reactor Fuel Cladding: The primary application of ASTM B811-compliant zirconium alloy tubes is as fuel cladding in nuclear reactors. These tubes act as a barrier between nuclear fuel and reactor coolant, contributing to the safety, integrity, and efficiency of the reactor core.
  • Nuclear Fuel Assemblies: The material’s resistance to corrosion and high-temperature mechanical stability make it ideal for use in fuel rods within light water reactors and other modern reactor designs.
  • Safety Compliance: Adherence to this standard is essential for manufacturers supplying components for nuclear facilities, ensuring compliance with national and international nuclear safety regulations.

Related Standards

The following standards are referenced within ASTM B811 and are relevant to the manufacture and testing of zirconium alloy tubes for nuclear applications:

  • ASTM B350/B350M: Specification for zirconium and zirconium alloy ingots for nuclear applications.
  • ASTM B353: Specification for wrought zirconium and zirconium alloy seamless and welded tubes for nuclear service (excluding fuel cladding).
  • ASTM E8/E8M: Test methods for tension testing of metallic materials.
  • ASTM E21: Test methods for elevated temperature tension tests of metallic materials.
  • ASTM E112: Test methods for determining average grain size.
  • ASTM G2/G2M: Test method for corrosion testing of zirconium products in water or steam at elevated temperatures.
  • ANSI B46.1: Standard for surface texture (surface roughness).

Practical Value

Manufacturers, quality assurance professionals, and nuclear reactor operators benefit from the rigorous guidelines set in ASTM B811-13(2022)e1. Compliance ensures the production of high-quality zirconium alloy seamless tubes that meet the strict mechanical, chemical, and performance requirements demanded by nuclear fuel cladding applications. Following this internationally recognized standard supports nuclear safety, material traceability, and regulatory acceptance within the global nuclear industry.

Keywords: zirconium alloy tubes, nuclear reactor fuel cladding, ASTM B811, seamless tubing, corrosion resistance, nuclear safety, zirconium alloy specification, mechanical properties, inspection, certification.

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Frequently Asked Questions

ASTM B811-13(2022)e1 is a technical specification published by ASTM International. Its full title is "Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding". This standard covers: 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

ASTM B811-13(2022)e1 is classified under the following ICS (International Classification for Standards) categories: 23.040.15 - Non-ferrous metal pipes. The ICS classification helps identify the subject area and facilitates finding related standards.

ASTM B811-13(2022)e1 has the following relationships with other standards: It is inter standard links to ASTM G2/G2M-19, ASTM B350/B350M-11(2016), ASTM E112-12, ASTM B353-12, ASTM G2/G2M-06(2011)e1, ASTM G2/G2M-06(2011), ASTM B350/B350M-11, ASTM E112-10, ASTM E21-09, ASTM E29-08, ASTM B353-07, ASTM E29-06b, ASTM E112-96(2004)e2, ASTM E29-06a, ASTM B350/B350M-02(2006). Understanding these relationships helps ensure you are using the most current and applicable version of the standard.

ASTM B811-13(2022)e1 is available in PDF format for immediate download after purchase. The document can be added to your cart and obtained through the secure checkout process. Digital delivery ensures instant access to the complete standard document.

Standards Content (Sample)


This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the
Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
´1
Designation:B811 −13 (Reapproved 2022)
Standard Specification for
Wrought Zirconium Alloy Seamless Tubes for Nuclear
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.
ε NOTE—Editorial changes were made to Table 3 in April 2022.
1. Scope 2. Referenced Documents
2.1 ASTM Standards:
1.1 This specification covers seamless wrought zirconium-
B350/B350MSpecification for Zirconium and Zirconium
alloy tubes for nuclear fuel cladding application, in the outside
Alloy Ingots for Nuclear Application
diameter (OD) size range of 0.200 in. (5.1 mm) to 0.650 in.
B353Specification for Wrought Zirconium and Zirconium
(16.5 mm) and wall thickness range of 0.010 in. (0.25 mm) to
Alloy Seamless and Welded Tubes for Nuclear Service
0.035 in. (0.89 mm).
(Except Nuclear Fuel Cladding)
1.2 Two grades of reactor grade zirconium alloys are
E8Test Methods for Tension Testing of Metallic Materials
described.
[Metric] E0008_E0008M
1.2.1 The present UNS numbers designated for the two
E8MTestMethodsforTensionTestingofMetallicMaterials
grades are given in Table 1.
[Metric] (Withdrawn 2008)
E21TestMethodsforElevatedTemperatureTensionTestsof
1.3 Unlessasingleunitisused,forexamplecorrosionmass
Metallic Materials
gain in mg/dm , the values stated in either inch-pound or SI
E29Practice for Using Significant Digits in Test Data to
units are to be regarded separately as standard. The values
Determine Conformance with Specifications
stated in each system are not exact equivalents; therefore each
E112Test Methods for Determining Average Grain Size
system must be used independently of the other. SI values
G2/G2MTest Method for Corrosion Testing of Products of
cannot be mixed with inch-pound values.
Zirconium, Hafnium, and TheirAlloys in Water at 680°F
1.4 The following precautionary caveat pertains only to the
(360°C) or in Steam at 750°F (400°C)
test method portions of this specification: This standard does
2.2 Other Document:
not purport to address all of the safety concerns, if any,
ANSI B46.1Surface Texture (Surface Roughness)
associated with its use. It is the responsibility of the user of this
standard to establish appropriate safety, health, and environ-
3. Terminology
mental practices and determine the applicability of regulatory
3.1 Definitions of Terms Specific to This Standard:
limitations prior to use.
3.1.1 dimensions, n—tube dimensions are outside diameter,
1.5 This international standard was developed in accor-
inside diameter, and wall thickness. Only two of these param-
dance with internationally recognized principles on standard-
eters may be specified in addition to length, except minimum
ization established in the Decision on Principles for the
wallmaybespecifiedwithoutsideandinsidediameter.Ineach
Development of International Standards, Guides and Recom-
case, ovality and wall thickness variation (WTV) may be
mendations issued by the World Trade Organization Technical
specified as additional requirements.
Barriers to Trade (TBT) Committee.
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
This specification is under the jurisdiction of ASTM Committee B10 on Standards volume information, refer to the standard’s Document Summary page on
Reactive and Refractory Metals and Alloys and is the direct responsibility of the ASTM website.
Subcommittee B10.02 on Zirconium and Hafnium. The last approved version of this historical standard is referenced on
Current edition approved April 1, 2022. Published April 2022. Originally www.astm.org.
approved in 1990. Last previous edition approved in 2017 as B811–13 (2017). Available from American Iron and Steel Institute (AISI), 1140 Connecticut
DOI: 10.1520/B0811-13R22E01. 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
B811−13 (2022)
TABLE 1 ASTM and UNS Number Designation for Reactor Grade
4.1.6 Surface texture on (roughness) the inside and outside
Zirconium Alloys
surfaces (R (micro-inches or micrometers)),
a
Grade UNS Number
4.1.7 Surface condition on the inside diameter (ID) and
Zirconium-tin alloy R60802
outside diameter (OD) surfaces (as pickled, blasted, abraded,
Zirconium-tin alloy R60804
etc.),
4.1.8 Sample test conditions (if other than mill finish
condition) and standards for corrosion test (see Section 8.2),
3.1.2 hydride orientation fraction, Fn, n—the ratio of hy-
dride platelets oriented in the radial direction to the total 4.1.9 General test requirements and test plan for lots (see
hydride platelets in the field examined. Section 10),
4.1.10 Number of tests and resampling plan and require-
3.1.3 lot size, n—a lot shall consist of all tubes of the same
ments (see Section 11), and
size,shape,condition,andfinishproducedfromthesameingot
by the same reduction schedule and heat treatment. The final 4.1.11 Certification of test (see Section 16).
heat treatment shall be in a single furnace charge.
NOTE 2—Atypical order description may read as follows: 1500 pieces
3.1.4 mill finish tubes, n—tubes that have received all
of seamless zirconium-alloy fuel clad tubes OD abraded and ID pickled,
Grade R60804, recrystallization annealed 0.650 in. nominal OD by 0.580
finishing operations subsequent to final anneal, which poten-
in. nominal ID by 0.032 in. minimum wall by 10 ft long with a maximum
tially affects tube mechanical, dimensional, or surface condi-
OD ovality of 0.004 in. and maximum WTV of 0.005 in. in accordance
tion.These operations include, but are not limited to, pickling,
withB811–XX.Maximumsurfacefinishtobe50µin.RaODand50µin.
cleaning, outer and inner surface abrasive conditioning, and
Ra ID.
straightening.
4.2 In addition to the information in 4.1, the following
3.1.5 ovality, n—the difference between the maximum and
points of agreement between the manufacturer and purchaser
minimum diameter, either outer or inner, as determined at any
should be specified in the purchase order as required:
one transverse cross-section of the tube.
4.2.1 Method of determining yield strength if other than
3.1.6 wall thickness variation (WTV), n—the difference
0.2% offset method (see Section 7),
between maximum and minimum wall thickness measured at
4.2.2 Initial gauge length of mechanical test samples for
any one transverse cross-section of the tube.
determining elongation after rupture if other than 2 in. (50
mm),
NOTE1—MeasurementofovalityandWTVmadebyahelicalscanwith
a pitch not exceeding 0.25 in. (6.5 mm) shall be considered as equivalent
4.2.3 Mechanical property requirements for tube other than
to “at any one cross-section of the tube.”
fully recrystallization annealed (see Section 7),
3.2 Lot Definitions:
4.2.4 Location of the inside diameter plugs in elevated
3.2.1 castings, n—alotshallconsistofallcastingsproduced
temperature short-time tension test, when specified (see Sec-
from the same pour.
tion 7.1.3),
3.2.2 ingot, n—no definition required.
4.2.5 Specimen temperature(s) during mechanical testing if
other than room temperature and properties and test require-
3.2.3 rounds,flats,tubes,andwroughtpowdermetallurgical
ments (see Section 7), and
products (single definition, common to nuclear and non-
nuclear standards), n—a lot shall consist of a material of the 4.2.6 Grain size requirements and specimen heat treatment
method for stress relief annealed tubes (see Section 8.1),
samesize,shape,condition,andfinishproducedfromthesame
ingot or powder blend by the same reduction schedule and the
4.2.7 Hydride orientation specimen heat treatment, if
same heat treatment parameters. Unless otherwise agreed
required,evaluationmethod,andmagnificationofphotomicro-
between manufacturer and purchaser, a lot shall be limited to
graph (see Annex A2),
the product of an 8 h period for final continuous anneal, or to
4.2.8 For hydride orientation, angle theta (θ) for determin-
a single furnace load for final batch anneal.
ing radial platelets (see Section 8.3 and Annex A2).
3.2.4 sponge, n—a lot shall consist of a single blend
4.2.9 Burst property acceptance requirements, when speci-
produced at one time.
fied (see Section 8.4),
4.2.10 Use of mandrel and post burst test measurement
3.2.5 weld fittings, n—definition is to be mutually agreed
technique (see Annex A1).
upon between manufacturer and the purchaser.
4.2.11 Contractile strain ratio acceptance criteria, when
4. Ordering Information
specified (see Section 7.3 and Annex A4).
4.1 Purchase orders for tubes covered in this specification
shall include the following information to describe adequately 5. Materials and Manufacture
the desired material:
5.1 Materials covered by this specification shall be pro-
4.1.1 Quantity,
duced in accordance with Specification B350/B350M; all
4.1.2 Grade (see Table 1),
processes to be done in furnaces usually used for reactive
4.1.3 Condition (recrystallization annealed or stress relief
metals.
annealed),
4.1.4 Tube dimensions and tolerance, 5.2 Tubes shall be made by a process approved by the
4.1.5 ASTM designation and year of issue, purchaser.
´1
B811−13 (2022)
TABLE 3 Permissible Variation in Product Analysis
6. Chemical Composition
Permissible Variation from
6.1 The tubes shall conform to the requirements for chemi-
the Specification Range
cal composition prescribed in Table 2.
(Table 2), %
Alloying Elements:
6.2 Chemical Analysis:
Tin 0.050
6.2.1 The analysis of the material produced to this specifi-
Iron 0.020
cation shall be the one made by the manufacturer on the ingot Chromium 0.010
Nickel 0.010
in accordance with Specification B350/B350M. This analysis
Iron plus chromium 0.020
canbeperformedbythemanufacturerontheingotitself,oron
Iron plus chromium plus nickel 0.020
intermediate or final products with the same frequency and in Oxygen 0.020
the same positions relative to the ingot as required in Specifi-
Impurity Element:
cation B350/B350M. The chemical analysis of hydrogen, †
Each impurity element 20 ppm or 20 % of the
specified limit, whichever is
oxygen and nitrogen shall be determined on the finished

smaller
product.
† Editorial changes made.
6.2.2 Analysis shall be made using the manufacturer’s
standard methods. In the event of disagreement as to the
chemicalcompositionofthemetal,thecomposition,forreferee
TABLE 4 Mechanical Properties of Recrystallization Annealed
A
purposes, shall be determined by a mutually acceptable labo- Tubes Tested at Room Temperature
ratory. UNS Numbers
R60802 and R60804
6.2.3 Product Analysis—Product analysis is a check analy-
Tension Test Properties (Longitudinal Direction):
sis made by the purchaser for the purpose of verifying the
Yield Strength (0.2 % Offset), min 35 ksi (240 MPa)
compositionofthelot.Thepermissiblevariationintheproduct
Tensile Strength, min 60 ksi (415 MPa)
analysis from the specification range is as listed in Table 3. Elongation, min %, 2 in. (50 mm) initial gauge length 20
Burst Test Properties:
7. Mechanical Properties
Ultimate Hoop Strength, min 72.6 ksi (500 MPa)
Percent Total Circumferential Elongation (% TCE), min 20
7.1 Tension Properties:
A
7.1.1 Recrystallization annealed tubes shall conform to the
“RT” represents room temperature; Note 4 in Test Methods E8 and E8M
indicates that RT shall be considered to be 50 to 100 °F (10 to 38 °C) unless
requirements for mechanical properties at room temperature
otherwise specified. Paragraph 9.4.4 in Test Methods E21 states that for the
prescribed in Table 4. For tubes in the cold worked and stress
duration of the test, the difference between the indicated temperature and the
relief annealed condition, tension property requirements are to nominal test temperature is not to exceed ±5 °F (3 °C) for tests at 1800 °F
(1000 °C) and lower, and ±10 °F (6 °C) for tests at higher temperatures.
be mutually agreed upon between the manufacturer and the
purchaser.
TABLE 2 Chemical Requirements
UNS Number UNS Number
Element
7.1.2 When so specified by the purchaser, the tension
R60802 R60804
propertiesshallalsobedeterminedattheelevatedtemperatures
Composition, Weight %:
Tin 1.20 to 1.70 1.20 to 1.70 and shall conform to the limits specified by the purchaser.
Iron 0.07 to 0.20 0.18 to 0.24
7.1.3 Thetensiontestshallbeconductedinaccordancewith
Chromium 0.05 to 0.15 0.07 to 0.13
TestMethodsE8orE21.Yieldstrengthshallbedeterminedby
Nickel 0.03 to 0.08 . . .
Oxygen 0.09 to 0.16 0.09 to 0.16
the 0.2% offset method. The tension properties shall be
Iron plus chromium plus 0.18 to 0.38 . . .
determined using a strain rate of 0.003 to 0.007 in./in.-min
Nickel
(mm/mm-min) through the yield strength. After the yield
Iron plus chromium . . . 0.28 to 0.37
strength has been exceeded, the cross head speed may be
Maximum Impurities, Weight %:
increased to approximately 0.05 in./in.-min (mm/mm-min) to
Aluminum 0.0075 0.0075
failure.
Boron 0.00005 0.00005
Cadmium 0.00005 0.00005
7.2 Burst Testing:
Calcium 0.0030 0.0030
7.2.1 Burst testing, when specified, shall be performed at
Carbon 0.027 0.027
Cobalt 0.0020 0.0020
room temperature on finished tubing. Recrystallization an-
Copper 0.0050 0.0050
nealed tubes shall conform to the requirements for burst
Hafnium 0.010 0.010
properties at room temperature prescribed in Table 4. If burst
Hydrogen 0.0025 0.0025
Magnesium 0.0020 0.0020
test is specified for cold worked and stress relief annealed
Manganese 0.0050 0.0050
tubes, the acceptance criteria shall be agreed upon between the
Molybdenum 0.0050 0.0050
Nickel . . . 0.0070 manufacturer and the purchaser.
Niobium 0.0100 0.0100
7.2.2 If elevated temperature burst test is specified, the test
Nitrogen 0.0080 0.0080
method and acceptance criteria shall be agreed upon between
Silicon 0.0120 0.0120
Tungsten 0.0100 0.0100 the manufacturer and purchaser.
Titanium 0.0050 0.0050
Uranium (Total) 0.00035 0.00035 NOTE 3—Burst properties obtained at room temperature were the
subject of a 1971 round robin conducted by ASTM subcommittee
´1
B811−13 (2022)
B10.02. Variability in values was relatively large and should be consid-
9. Permissible Variations in Dimensions
ered in setting specific limits.
9.1 Diameter—The permissible variations in outside or
7.3 Contractile Strain Ratio (CSR):
inside diameter shall be 60.002 in. (60.05 mm).
7.3.1 When so specified by the purchaser, the contractile
9.2 Wall Thickness—The permissible variations in wall
strainratio(CSR)shallbedeterminedatroomtemperatureand
thickness shall be 60.003 in. (60.08 mm).
shall conform to limits that are mutually agreed upon between
the manufacturer and purchaser. 9.3 Length—The permissible variation in length shall be
60.030 in. (60.76 mm).
7.3.2 Contractile strain ratio testing shall be conducted in
accordance with Annex A4.
10. Sampling
NOTE4—Contractilestrainratiotestingwasthesubjectofa1993round
10.1 For certification purposes, a minimum of two random
robin conducted by ASTM Subcommittee B10.02 using specimens with
sample tubes shall be taken from each lot for laboratory tests.
diameter approximately 0.4 in. (10 mm). The variability was relatively
large and should be considered in setting specific limits. The following
All tubes in a lot shall have been inspected for each inspection
two-sigma limits were determined as an estimate of the test precision:
characteristic given in Section 12.
60.16forsampleswithaCSRof1.68,and 60.22forsampleswithaCSR
of 2.53.
11. Number of Tests and Resampling
11.1 Specimens cut from each sample tube, chosen in
8. Other Requirements
accordance with Section 10 for laboratory testing, shall be
8.1 Grain Size—The average grain size of recrystallization
tested as follows: (1) tube chemical analysis (see Section 6),
annealed tubes in the longitudinal section shall be equal to
(2) tension test (see 7.1), (3) burst test (see 7.2), (4) contractile
ASTM micrograin Size No. 7 or finer when determined in
strain ratio test (see 7.3), (5) grain size (see 8.1), (6) corrosion
accordancewithTestMethodsE112.Whenspecifiedper4.2.6,
test (see 8.2), (7) hydride orientation (see 8.3), and (8) surface
theaveragegrainsizeofstressreliefannealedtubesshallmeet
texture (see 8.4).
the requirements as agreed upon between manufacturer and
11.2 Resampling:
purchaser.
11.2.1 If any specimen exhibits obvious surface contamina-
8.2 Corrosion Properties:
tion or improper preparation disqualifying it as a truly repre-
8.2.1 A corrosion test in steam shall be performed in
sentativespecimen,itshallbediscardedandreplacedbyanew
accordance with Test Method G2/G2M. The specimens tested
specimen.
shall be representative of the mill finish condition unless
11.2.2 If the results of the tube inspection of a lot are not in
otherwise stated by the purchaser.
conformancewiththerequirementsofthisspecification,thelot
8.2.2 Acceptance Criteria:
may be reworked at the option of the manufacturer, provided
8.2.2.1 Mass Gain—Specimens shall exhibit a mass gain of
the rework steps are within the previously approved process.
2 2
notmorethan2.2g/m ina72-htestor3.8g/m ina336-htest.
11.2.2.1 The reworked tubes shall be inspected for confor-
8.2.2.2 Post-Test Visual Appearance—Millfinishspecimens
mance to this specification.
shall be free of white or brown corrosion products in excess of
11.2.2.2 Reworked lot shall be resampled for tests affected
the acceptance standards mutually agreed between the manu-
by the rework in accordance with Section 10.
facturer and the purchaser. Specimens etched per Test Method
11.2.3 If any sample fails to conform to the specification
G2/G2M (if stated by the purchaser) shall exhibit a continuous
requirement, the test for the nonconforming attribute shall be
black lustrous oxide film and shall be free of white or brown
performed on specimens taken from twice as many random
corrosion products in excess of standards.
sample tubes as originally used.
11.2.3.1 All test results, including the original test results,
8.3 Hydride Orientation Fraction:
shall be reported to the purchaser.
8.3.1 Hydride orientation fraction, Fn, shall be determined
11.2.3.2 Only one set of resampling is permitted, and all
on samples taken from mill finished tubes.
resultsofresamplingshallconformtothespecificationrequire-
8.3.2 The hydride orientation shall be determined in accor-
ments for the characteristic tested.
dance with Annex A2.
8.3.3 Acceptance Criteria—Stress relief annealed speci-
12. Inspection
mens shall have an Fn value not more than 0.30. Recrystalli-
12.1 The manufacturer shall inspect the entire length of the
zation annealed specimens shall have an Fn value not greater
mill finished tubes covered by this specification, prior to
than 0.50.
shipment, for dimensions, outer and inner surfaces,
8.4 Outer and Inner Surface Texture (Roughness)—Outer
straightness, and surface and internal flaws as follows:
and inner surface texture (roughness) shall be determined in
12.1.1 Surface and Internal Flaw Inspection:
accordance with ANSI B46.1 or its national or international
12.1.1.1 Ultrasonic Inspection Test Methods—Each tube
equivalent for conformance to purchase order surface texture
shall be inspected by the ultrasonic test method in accordance
(roughness) requirements.
with Annex A3 of this specification.
12.1.1.2 Ultrasonic Reference Standard—The test equip-
ment shall be calibrated with an artificially defected standard
STP 551, “Zirconium in Nuclear Applications,” ASTM, 1974, pp. 14–28. tube of the same nominal material, diameter, wall thickness,
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B811−13 (2022)
surface finish, fabrication process, and final thermal treatment inspection shall be so conducted as not to interfere unneces-
as the lot being tested.The standard shall contain not less than sarily with production operations.
fourdefectsorientedasfollows:(1)outertubesurface,parallel
to tube axis, (2) outer tube surface, transverse to tube axis, (3) 13. Significance of Numerical Limits
inner tube surface, parallel to tube axis, and (4) inner tube
13.1 For the purpose of determining compliance with the
surface, transverse to tube axis. The defects shall be notches
specified limits of property requirements, an observed value or
withadepthequalto10%ofthenominalwallthickness.Inno
a calculated value shall be rounded in accordance with the
case, however, shall the artificial defect be deeper than 0.002
rounding method of Practice E29.
in. (0.05 mm) or longer than 0.065 in. (1.65 mm).
13.1.1 All observed and calculated values, except those
12.1.1.3 Rejection—Any tube showing an ultrasonic indica-
listed below, are to be rounded to the nearest unit in the right
tion equal to or greater than the standard set forth in 12.1.1.2
hand place of figures of the specified limit:
shall be rejected.
Rounded Unit for Observed
Test
12.1.2 Outer and Inner Surfaces:
or Calculated Value
12.1.2.1 Test Method—Each tube shall be inspected over its
Tensile strength, yield strength, and burst nearest 1000 psi (10 MPa)
entire length. The outside surface shall be inspected on a table
strength
underaminimumlightintensityof100fc(10761x).Theinner
surface shall be inspected from each end against a suitable
14. Rejection
fluorescent light background.
14.1 Tubes that fail to conform to the requirements of this
12.1.2.2 Acceptance Criteria—The tubes shall not contain
specification may be rejected. Rejection should be reported to
oxides, cracks, seams, slivers, blisters, pits, laps, foreign
the manufacturer promptly and in writing. The reporting must
particles, or scratches exceeding the mutually agreed-upon
be done according to the agreement between the manufacturer
inspection standard.
and the purchaser; if not, the reporting will be done not later
12.1.3 Straightness:
than 60 calendar days from the receipt of the material by the
12.1.3.1 Test Method—Each tube shall be inspected for
purchaser. In case of dissatisfaction with the results of the test,
straightness on a surface plate by rolling and observing for the
the manufacturer may claim for referee in accordance with
maximum deflection (bow) in the vertical plane between two
Section 15.
points of contact, or by another method acceptable to the
purchaser.
15. Referee
12.1.3.2 Acceptance Criteria—The tubes shall be free of
15.1 Intheeventofdisagreementbetweenthemanufacturer
bends or kinks. The maximum deflection (bow) in the vertical
and the purchaser on the conformance of the tubes to the
plane shall not exceed 0.01 in. (0.25 mm) between any two
requirements of this specification or any special test specified
adjacentpointsofcontact.Innocaseshallthebowexceed0.01
by the purchaser, a mutually acceptable referee shall perform
in. (0.25 mm) per foot (305 mm) of the span length, irrespec-
thetestsinquestion.Theresultsofthereferee’stestingshallbe
tive of the tube diameter.
used in determining conformance of the material to this
12.1.4 Dimensional Inspection:
specification.
12.1.4.1 Test Method—Each tube shall be inspected over its
entire length by using a helix of measurement with the pitch
16. Certification
not exceeding 2 in. (50.8 mm).
16.1 The manufacturer shall supply at least one copy of the
12.1.4.2 Acceptance Criteria—The tubes shall meet the
report certifying that the material supplied has been
permissible variations specified in Section 9.
manufactured, inspected, sampled, and tested in accordance
12.1.5 Purchaser Inspection:
with the requirements of this specification and that the results
12.1.5.1 The manufacturer shall inspect tubes covered by
of chemical analysis, tensile, and other tests meet the require-
this specification prior to shipment and, on request, shall
ments of this specification for the grade specified. The report
furnishthepurchaserwithcertificatesoftest.Ifsospecifiedon
shall include results of all chemical analysis, tensile tests, and
the purchase order, the purchaser or his representative may
all other tests required by the specification.
witness the testing and inspection of the tubes at the place of
manufacture. In such cases, the purchaser shall state in his
17. Packaging and Package Marking
purchase order which tests he desired to witness. The manu-
facturer shall give ample notice to the purchaser as to the time
17.1 Each bundle, box, or carton shall be legibly and
and place of the designated tests. If the purchaser’s represen- conspicuously marked or tagged with the following informa-
tative is not present at the time agreed upon for the testing and
tion:
if no new date is agreed upon, the manufacturer shall consider
17.1.1 Purchase order or contract number,
the requirement for purchaser’s inspection at place of manu-
17.1.2 Name of manufacturer,
facture to be waived.
17.1.3 Grade,
12.1.5.2 When the inspector representing the purchaser 17.1.4 Size,
appearsattheappointedtimeandplace,themanufacturershall 17.1.5 Lot or ingot number,
afford him all reasonable facilities to see that the material is 17.1.6 Gross, net and tare weights, and
being furnished in accordance with this specification. This 17.1.7 ASTM designation.
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17.2 Alltubesshallbepackedinsuchamannerastoensure 18. Keywords
safe delivery to its destination when properly transported by
18.1 fuel cladding; nuclear fuel; nuclear reactor; seamless;
any common carrier. Any special requirements or instructions
tubing; zirconium alloy
must be specified by the purchaser.
ANNEXES
(Mandatory Information)
A1. ROOM TEMPERATURE CLOSED-END BURST TESTING PROCEDURE FOR ZIRCONIUM ALLOY NUCLEAR FUEL
CLADDING TUBES
A1.1 Scope
A1.1.1 This annex covers the determination of burst test A1.3.5 Mandrels (if agreed upon) shall meet the following
mechanical properties at room temperature of zirconium alloy requirements:
nuclear fuel cladding tubes. A1.3.5.1 The mandrel outside diameter shall be 0.010 6
0.002 in. (0.25 6 0.05 mm) less than the average inside
A1.1.2 Burst test results are affected by very small changes
diameter of the tube, except an axial relief groove may be cut
in procedure.The following items are identified and defined to
in the mandrel to facilitate movement of the fluid within the
minimize variation in testing procedures and to obtain repro-
specimen.
ducibility of test results.
A1.3.5.2 The ends of the mandrel shall be tapered or
A1.1.3 This procedure is not appropriate for testing at
otherwise shaped so as not to restrict axial deformation of the
elevated temperatures.
specimen during test.
A1.3.6 All free gases shall be vented from the specimen
A1.2 Apparatus
prior to test.
A1.2.1 The test system shall be designed with adequate
capacity to test at the stress levels and temperatures needed. A1.4 Procedure
Special consideration should be given to the following items:
A1.4.1 Measurementsshallbemadeoftheoutsidediameter
and wall thickness of the specimen such that the mean average
NOTE A1.1—If elevated temperature tests are to be performed on the
sameequipmentusedforroomtemperaturetests,itisessentialthatspecial
diameter and minimum wall thickness can be determined to an
fluids be used which are stable at the elevated test temperatures.
accuracy of 0.0005 in. (0.013 mm). Recommended measure-
A1.2.1.1 Pump, capable of increasing system pressure at a ments are as follows:
steady rate.The pressurization rate during elastic loading shall A1.4.1.1 Pretest measurements of the outside diameter at
be 2000 6 200 psi/min (13.8 6 1.4 MPa/min) and the same three equally spaced locations around the circumference at
initial fluid volume pumping rate shall be maintained for the each end of the specimen and at the center. Pretest measure-
duration of the test. The pump should not produce a pressure ments of the wall thickness at six equally spaced locations at
surge with each stroke. The system should be stiff, that is, its each end of the specimen.
stored energy should be as low as practical.
A1.4.1.2 Individual pretest measurements shall be to an
A1.2.1.2 Valves, shall be included for the following func- accuracy of 60.0002 in. (0.005 mm).
tions: control, regulation, and safety. A1.4.1.3 Post test circumferential elongation shall be deter-
A1.2.1.3 Gauges, of adequate capacity, shall be used to mined at the point of maximum bulge, excluding the opening
monitor system pressure and to record the maximum fluid of the rupture, and to an accuracy of 60.005 in. (0.13 mm).
pressure attained. The measurement technique is to be mutually agreed upon
between the manufacturer and the purchaser.
A1.3 Preparation of Specimen
A1.5 Report
A1.3.1 The sample shall be selected and tested in the mill
A1.5.1 Report the following data:
finished condition.
A1.5.1.1 Measurements taken from test specimens,
A1.3.2 Minimum unsupported length shall be ten times the
A1.5.1.2 Maximum fluid pressure,
average outside diameter.
A1.5.1.3 Ultimate hoop strength, calculated as follows:
A1.3.3 End fittings must be such as to produce a 2:1
PD
s 5 (A1.1)
circumferential to axial stress ratio.
2t
A1.3.4 Useofamandrelinsidethetestspecimenshallbeon
where:
agreement between the manufacturer and the purchaser and
s = ultimate hoop strength, psi or MPa,
shall be noted on test reports.
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A1.5.1.4 Percent total circumferential elongation (% TCE):
P = maximum fluid pressure, psi or MPa,
D = average outside diameter minus average wall thickness,
C 2 C
2 1
% TCE 5 3100 (A1.2)
in. or mm, and
C
t = minimum pretest wall thickness, in. or mm; and
where:
C = pretest circumference, and
C = post test circumference excluding burst opening.
A2. PROCEDURE FOR DETERMINATION OF RADIAL HYDRIDE ORIENTATION FRACTION IN ZIRCONIUM ALLOY
NUCLEAR FUEL CLADDING TUBES
A2.1 Scope
A2.1.1 This annex covers the determination of radial hy- chemical polish shall be capable of delineating the hydride
dride orientation fraction, Fn, of zirconium alloy nuclear fuel platelets. An anodizing procedure is recommended following
cladding tubes. the etch or polish.
A2.3.2 Divide each transverse tube wall section into three
A2.1.2 The radial hydride orientation fraction, Fn, shall be
equal layers covering the entire wall thickness (outer, middle,
evaluatedbyeitherthemeasurementmethodorthemicrograph
and inner wall sections) and make determinations per Section
comparison method given in Section A2.4, as specified by the
A2.4 on each layer.Asuitable magnification in the range 100×
purchaser.
to 500× (as specified by the purchaser) shall be used for the
measurement, and the measured area shall be typical of the
A2.2 Procedure
hydride microstructure in the entire specimen cross section.
A2.2.1 Inoculate specimen with sufficient hydrogen to pro-
A2.4 Evaluation Method
duce uniformly distributed hydride platelets as follows:
A2.2.1.1 Introduce hydrogen into the specimen by methods
A2.4.1 Measurement Method:
such as autoclaving in steam or lithium hydroxide, electrolytic
A2.4.1.1 From the micrograph of each layer, count all
deposition, or absorption of hydrogen gas. The treatment
hydride platelets equal to or longer than 0.000625 in. (0.015
temperature shall not exceed 775°F (414°C). The method of 1
mm) at 1× magnification ( ⁄16 in. or 1.5 mm at 100× magnifi-
hydridingshallnotresultinexcessivehydrideconcentrationon
cation). Also count each platelet segment that extends in a
the surface. Such concentration would obscure the determina-
secondarydirectionlongerthan0.000625in.(0.015mm)at1×
tionofhydrideorientation.Nosurfaceremovalisallowedafter
magnification as a separate platelet.
hydriding.
A2.4.1.2 Count all radial platelets for each layer. A radial
A2.2.1.2 When agreed upon, heat treat the specimen at 750
platelet is defined as one oriented within theta (θ) degrees of
6 25°F (399 6 14°C) for 5 6 1 h in an inert atmosphere
theradialdirectionofthetubeandmeetingtherequirementsof
either during or after hydriding. If vacuum heat treatment is
A2.4.1.1.
–5
used,thepressureshallnotbelessthan10 torr(1.33mPa)to
A2.4.1.3 Calculate the value of the radial hydride fraction,
prevent dehydriding. The cooling rate from temperature shall
Fn.
be less than 25°F⁄min (14°C⁄min).
A2.4.2 Micrograph Comparison Method:
A2.4.2.1 Compare the specimen micrograph against the
A2.3 Preparation of Micrograph
purchaser-approved micrograph standard with an assigned
A2.3.1 Cut transverse metallographic sections from each value of Fn. The specimen Fn is acceptable if the fraction of
hydridedspecimenandprepareformicroscopicalexamination. radial hydrides in the specimen micrograph is equal to or less
Do not use heat or pressure in preparation. The final etch or than the purchaser-approved standard.
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A3. PROCEDURE FOR ULTRASONIC FLAW TESTING OF ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING TUBES
A3.1 Scope
A3.1.1 This annex covers procedures for detecting discon-
tinuitiesinzirconiumalloynuclearfuelcladdingtubes.Guides
for the selection and positioning of transducers for shear-wave
and Lamb-wave procedures are included in Appendix X1 and
Appendix X2.
A3.1.2 The immersed ultrasonic pulse-echo technique is
employed.
A3.1.3 Artificial longitudinal and transverse reference
notchesareemployedasthemeansofcalibratingtheultrasonic
system.
A3.2 Terminology
A3.2.1 Definitions:
A3.2.1.1 relevant indication of a discontinuity, n—a repeat-
(a) Transducer set up for Longitudinal Defect; Offset ' 0.233 × Outer Diameter,
for 45 deg Shear Wave in Zircaloy.
able electronic signal in excess of rejection criteria.
A3.2.1.2 Definitions of additional terms and formulae are
given in A3.8.2.3.
A3.3 Surface Condition
A3.3.1 All mill finished tubes shall have surfaces that are
clean and free of scale, dirt, grease, paint, or other foreign
material that will interfere with the interpretation of the test
results. The methods used for cleaning and preparing the
surfacesforultrasonicinspectionshallnotbedetrimentaltothe
base metal or the surface finish. (b) Transducer set up for Transverse Defect; Incident Angle φ ' 28 deg, or 45
deg Shear Wave in Zircaloy.
NOTE A3.1—Excessive surface roughness or scratches provide signals
(noise) that interfere with the test. FIG. A3.1Shear Wave Test for Longitudinal and Transverse
Defects
A3.3.2 The tubes shall be within the requirements of this
specification for dimensions at time of test.
A3.4 Apparatus A3.4.3 The ultrasonic test shall be monitored automatically
by one or more of the following: (1) a chart recorder, (2)
A3.4.1 Theinstrumentsandaccessoryequipmentshallbeof
magnetic tape, (3) electronically shutting down and stopping
the pulse-echo type and shall be capable of distinguishing the
the handling equipment, or (4) a paint or ink marking system.
reference notches to the extent required in the calibration
A3.4.3.1 The test-monitoring system shall have the capabil-
procedure. Fig. A3.1(a) illustrates the characteristic oblique
ity to pick up the standard notch and defect indications.
entry of sound into the tube wall and the circumferential
A3.4.3.2 The automatic gating system must be equipped
direction of ultrasonic energy propagation used to detect
with an electronic circuit that will make it impossible for more
longitudinal notches. Fig. A3.1(b) illustrates the characteristic
than one pulse to remain unrecorded. The system used shall
oblique angle and the longitudinal direction of ultrasonic
contain one of the following: (1) pulse stretcher, (2) a one-shot
energy propagation used to detect circumferential notches.
multivibrator, (3) a pulse counter-recorder combination, or (4)
A3.4.1.1 The practice for a refracted shear wave in a tube
equivalent devices.
wall is with the effective beam width of the transducer within
1 1
the tube wall in the range of ⁄2 to 1 ⁄2 the tube wall thickness. A3.4.4 Anadvisoryguidetotransducerselectionisgivenin
Appendix X1. Transducers other than those described in
A3.4.2 Thetestsystemshallconsistoftwo-orfour-channel
Appendix X1 that produce the response required in Section
pulse-echo flaw detection equipment, one or two 2-channel
A3.7 may be used, provided their use is mutually agreed upon
strip chart recorders or equivalent, tube transport system
between the manufacturer and the purchaser.
(handling equipment), immersion tank, two to four search
units, and assorted coaxial cables and connectors. The test A3.4.5 Types of Transducers:
system may have a water heater and water filter as optional A3.4.5.1 Line Focus Transducer (or Cylindrically Focus
equipment. Commercially available electronic equipment, Transducer)—This type of transducer transmits a wedge of
when used with applicable search units, shall be capable of energy that is distributed along a line. To calculate the
producing ultrasonic test frequencies of at least 5 MHz. maximum revolutions per minute (r/min), two dimensions will
´1
B811−13 (2022)
be required: (1) the effective beam length (EBL), and (2) the
effective beam width (EBW), at the focal point (sometimes
referred to as the Y + point). See Fig. A3.2.
o
A3.4.5.2 Spot Focus Transducer—This type of transducer
transmits a cone of energy. To calculate the maximum r/min,
only one dimension (EBW) will be required; the diameter of
thebeam(orthebeamwidthorthefocaldiameter)orthefocal
point (Y +). See Fig. A3.3.
o
A3.5 Couplant
A3.5.1 Water shall be used as the couplant conducting
ultrasonic energy between the transducer and the tube. Rust
andalgaeinhibitors,softeners,andwettingagentsapprovedby
the purchaser may be added to the water.The couplant with all
additives shall wet the tube’s outside surface to provide
adequate coupling efficiency.
FIG. A3.3Description of EBW for a Spot Focus Transducer
A3.5.2 The inside surface of the tube must be kept dry and
free of couplant to avoid misleading signals.
A3.5.3 The water must be kept free of debris and visible air
(axial) direction; and one each on the inner and outer surfaces
bubbles that interfere with the ultrasonic inspection.
aligned in the transverse (circumferential) direction.
A3.6.4 Reference notches shall be sufficiently distant from
A3.6 Calibration Standards
one another and from the end of the tube to avoid interference
A3.6.1 This section describes the size, shape, preparation,
or interpretation difficulty during the test.
and positioning of artificial defects to be employed as calibra-
A3.6.5 The notch dimensions, which are length, depth,
tion standards for use in testing with this procedure.
width (and for V-notches, the included angle) and the relation-
A3.6.2 A calibration (reference) standard of a convenient
ship to sound beam dimensions shall be mutually agreed upon
length shall be prepared from a length of tube of the same
between the purchaser and the manufacturer. Fig. A3.4 illus-
nominal material, diameter, wall thickness, surface finish,
trates the common notch configurations and the dimension to
fabrication process, and final thermal treatment as the tubes to
be measured (Note A3.2). References from V-, buttress-, and
be inspected. The calibration tube shall be carefully examined
U-shaped notches of equal dimensions may vary widely
prior to manufacture of notches to ensure freedom from
depending on the angle and vibrational mode of the interro-
discontinuities or other conditions producing indications that
gating beam.
can interfere with or be confused with detection of the
NOTEA3.2—In Fig.A3.4(a) and Fig.A3.4(d), the sharp corners are for
reference notches.
ease of illustration. It is recognized that in normal machining practice, a
A3.6.3 Four notches, minimum, shall be required; one each
radiuswillbegenerated.Notchesproducedbyelectro-machiningtypically
on the inner and outer surfaces aligned in the longitudinal will have a radius at the bottom of the notch that increases with the depth
of the notch. For example, a 0.001 in. (0.025 mm) deep notch will have a
0.0002 in. (0.005 mm) radius, while a 0.002 in. (0.05 mm) deep notch
might have a 0.0003 in. (0.0075 mm) radius.
NOTEA3.3—The length of the calibration notch should be chosen with
somecare,especiallywhenlinefocustransducersareemployed.Ifanotch
is short with respect to the transducer beam length along the notch’s long
axis, the test will be unnecessarily sensitive to long, shallow defects.
Conversely, if the calibration standard is long compared with the beam
length, then the test will be insensitive to defects that are short compared
with the beam length.The best compromise is a notch length/beam length
ratio between 0.3 and 1.
FIG. A3.2Description of EBL and EBW for a Line Focus
Transducer FIG. A3.4Common Notch Shapes
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A3.6.6 All upset metal and burrs associated with the refer- A3.8.2.2 PurchasetransducerscertifiedastoEBWandEBL
ence notches shall be removed. and use the certified values in the formulae.
A3.8.2.3 Establishtheeffectivebeamwidth(EBW)(andthe
A3.6.7 The notch depth shall be an average measured from
effectivebeamlength(EBL),ifitisalinefocustransducer)by
the tube surface to the maximum and minimum penetration of
passing the ultrasonic beam over a standard or reference notch
the notch. Measurements may be made by optical, replicating,
with the notch 90° to the beam while maintaining a signal
or other mutually agreed upon techniques. Destructive means
strength of 70% of the maximum signal and a minimum
may be used on duplicate notches that produce identical
overlap of 25%. This measurement should be performed from
(within 5%) ultrasonic response. Notch depth shall be within
a longitudinal notch if the transducer is used to detect longi-
60.0005 in. (0.013 mm) of the specified value.
tudinal (L) defects, and it should be performed on a transverse
A3.6.8 The width of the notches should be as small as
notch if the transducer is used for transverse (T) defects, as
possible, but shall not exceed 0.005 in. (0.13 mm).
shown in Fig. A3.5. EBL measurement should be performed
from a longitudinal notch if the transducer is used to detect
A3.6.9 Other types of orientations of reference discontinui-
transverse defects (T), and it should be performed on a
ties may be specified under contractual agreement between the
transverse notch if the transducer is used to detect longitudinal
purchaser and the manufacturer.
(L) defects.
A3.6.10 All calibration notch standards shall be given a
A3.8.2.4 The surface speed, r/min, feed rate, and test time
permanent identification marking and shall be traceable as to
are given by the following equations:
material composition, heat treatment, location and positioning
SurfaceSpeed mm/s 5 1 2 y 3PRR 3 EBW (A3.1)
~ ! ~ ! ~ !
of notches, and methods and results of each notch measure-
ment.
where:
EBW = effective beam width, mm,
A3.7 Calibration of the Apparatus
PRR = pulse repetition rate of ultrasonic equipment,
pulses/s, and
A3.7.1 Static Calibration—Using the calibration standard
y = fraction of overlap required, for y = o the surface
specified in Section A3.6, adjust the equipment statically to
speed is maximum.
produceclearlyidentifiableindicationsfromboththeinnerand
outer surface notches. An advisory guide to transducer posi-
19 3 ~EBW!
RevolutionPerMinute r/min 5 3PRR 1 2 y
~ ! ~ !
tioning is given in Appendix X2. The relative response from
OD
the inner and outer surface notches shall be as nearly equal as
(A3.2)
possible. If the responses are not equal, the smaller response
Feed Rate (mm/min)
shall be the reject level. It is recommended that the smaller
response be not less than 80% of the larger response. The = (EBL)(1 – y) × r/min, for line focus transducer
actual rejection level as a percent of standard notch amplitude = (EBW)(1 – y) × r/min, for spot focus transducer
response can be mutually agreed upon between the manufac-
tubelength
TotalInspectionTime 5 (A3.3)
turer and the purchaser.
feed
A3.7.1.1 The amplitude of the indication from the inside
NOTE A3.4—If a line focus transducer is used for the detection of
transverse flaws, EBL should be used in the equation for determining
surface and outside surface notches must be between 50 to
revolutions per minute (r/min).
90% of the full screen amplitude.
A3.8.2.5 In the Lamb-wave technique test, the revolution
A3.7.2 Dynamically calibrate the system with the reference
speed shall allow for a minimum of 120 pulses per revolution.
...

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