ASTM B353-12
(Specification)Standard Specification for Wrought Zirconium and Zirconium Alloy Seamless and Welded Tubes for Nuclear Service (Except Nuclear Fuel Cladding)
Standard Specification for Wrought Zirconium and Zirconium Alloy Seamless and Welded Tubes for Nuclear Service (Except Nuclear Fuel Cladding)
ABSTRACT
This specification covers the standard requirements for wrought zirconium and zirconium alloy seamless and welded tubes for nuclear applications except for nuclear fuel cladding. Five grades of reactor grade zirconium and zirconium alloys with R60001, R60802, R60804, R60901, and R60904 UNS number designations are described. Material shall be made from ingots produced by vacuum arc melting, electron beam melting, or other melting process to be carried out in furnaces conventionally used for reactive metals. Seamless tubes may be made by billet extrusion with subsequent cold working, by drawing, swaging, or rocking, with intermediate annealing. Welded tubing shall be made from flat-rolled products by an automatic or semiautomatic welding process with no addition of filler metal and shall be cold reduced by drawing, swaging, or rocking. The products shall be in the recrystallized or cold-worked and stress-relieved conditions and shall be furnished by as-cold reducing, pickling, grounding, polishing, or end-saw cutting, machining, or shearing. Chemical and product analysis shall be performed on the materials which shall meet the chemical composition requirements for tin, iron, chromium, nickel, niobium, oxygen, and other impurity elements. The tensile properties shall be determined by a tensile test method and shall conform to the tensile strength, yield strength, and elongation limits. Steam and water corrosion tests and hydrostatic test shall be conducted to determine the acceptance criteria for corrosion and internal hydrostatic pressure, respectively. Burst properties, contractile strain ratio, grain size, and hydride orientation of the finished tubing shall also be determined.
SIGNIFICANCE AND USE
16.1 For the purpose of determining compliance with the specified limits of property requirements, an observed value or a calculated value shall be rounded in accordance with the rounding method of Practice E29.
Test
Rounded Units for Observed
or Calculated Value
Chemical composition, tolerance
(when expressed in decimals)
nearest unit in the last right hand place of figures of the specified limit
Tensile strength and yield strength
nearest 1000 psi (10 MPa)
Elongation
nearest 1 %
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 1.TABLE 1 ASTM and UNS Number Designations for Reactor Grade Zirconium and Zirconium Alloys
Grade
UNS Number
Reactor-grade zirconium
R60001
Zirconium-tin alloy
R60802
Zirconium-tin alloy
R60804
Zirconium-niobium alloy
R60901
Zirconium-niobium alloy
R60904
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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Designation:B353 −12
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 B353; 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. Scope E29Practice for Using Significant Digits in Test Data to
Determine Conformance with Specifications
1.1 This specification covers seamless and welded wrought
E112Test Methods for Determining Average Grain Size
zirconium and zirconium-alloy tubes for nuclear application.
G2/G2MTest Method for Corrosion Testing of Products of
Nuclear fuel cladding is covered in Specification B811.
Zirconium, Hafnium, and TheirAlloys in Water at 680°F
1.2 Five grades of reactor grade zirconium and zirconium
(360°C) or in Steam at 750°F (400°C)
alloys suitable for nuclear application are described.
1.2.1 The present UNS numbers designated for the five
3. Terminology
grades are given in Table 1.
3.1 Definitions of Terms Specific to This Standard:
1.3 Unlessasingleunitisused,forexamplecorrosionmass
3.1.1 dimensions, n—tube dimensions are outside diameter,
2
gain in mg/dm , the values stated in either inch-pound or SI
inside diameter, and wall thickness. Only two of these param-
units are to be regarded separately as standard. The values
eters may be specified in addition to length, except minimum
stated in each system are not exact equivalents; therefore each
wallmaybespecifiedwithoutsideandinsidediameter.Ineach
system must be used independently of the other. SI values
case, ovality and wall thickness variation (WTV) may be
cannot be mixed with inch-pound values.
specified as additional requirements (see 3.1.5 and 3.1.6).
1.4 The following precautionary caveat pertains only to the
3.1.2 hydride orientation fraction, Fn, n—the ratio of hy-
test method portions of this specification. This standard does
dride platelets oriented in the radial direction to the total
not purport to address all of the safety concerns, if any,
hydride platelets in the field examined.
associated with its use. It is the responsibility of the user of this
standard to establish appropriate safety and health practices 3.1.3 Lot Definitions:
and determine the applicability of regulatory limitations prior 3.1.3.1 tubes, n—alotshallconsistofamaterialofthesame
to use.
size,shape,condition,andfinishproducedfromthesameingot
or powder blend by the same reduction schedule and the same
2. Referenced Documents
heat treatment parameters. Unless otherwise agreed between
2
2.1 ASTM Standards: manufacturer and purchaser, a lot shall be limited to the
B350/B350MSpecification for Zirconium and Zirconium
product of an 8 h period for final continuous anneal, or to a
Alloy Ingots for Nuclear Application single furnace load for final batch anneal.
B811Specification for Wrought Zirconium Alloy Seamless
3.1.4 mill finish tubes, n—tubes that have received all
Tubes for Nuclear Reactor Fuel Cladding
finishing operations subsequent to final anneal, which poten-
E8Test Methods for Tension Testing of Metallic Materials
tially affects tube mechanical, dimensional, or surface condi-
E21TestMethodsforElevatedTemperatureTensionTestsof
tion.These operations include, but are not limited to, pickling,
Metallic Materials
cleaning, outer and inner surface abrasive conditioning, and
straightening.
1
This specification is under the jurisdiction of ASTM Committee B10 on
3.1.5 ovality, n—the difference between the maximum and
Reactive and Refractory Metals and Alloysand is the direct responsibility of
Subcommittee B10.02 on Zirconium and Hafnium. minimum diameter, either outer or inner, as determined at any
Current edition approved Nov. 1, 2012. Published January 2013. Originally
one transverse cross section of the tube.
approved in 1960. Last previous edition approved in 2007 as B353–07. DOI:
10.1520/B0353-12. 3.1.6 wall thickness variation (WTV), n—the difference
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
between maximum and minimum wall thickness measured at
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
any one transverse cross section of the tube.
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. 3.1.6.1 Discussion—Measurement of ovality and WTV
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
B353−12
TABLE 1 ASTM and UNS Number Designations for Reactor Grade
4.1.9 Mutually agreed-upon inspection standards i
...
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.
Designation: B353 − 07 B353 − 12
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 B353; 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. 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 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
B811 Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding
E8 Test Methods for Tension Testing of Metallic Materials
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]
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 (see 3.1.5 and 3.1.6).
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 Definitions:
3.1.3.1 tubes, n—a lot shall consist of a material of the same size, shape, condition, and finish produced from the same ingot
or powder blend by the same reduction schedule and the same heat treatment parameters. Unless otherwise agreed between
manufacturer and purchaser, a lot shall be limited to the product of an 8 h period for final continuous anneal, or to a single furnace
load for final batch anneal.
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, 2007Nov. 1, 2012. Published May 2007January 2013. Originally approved in 1960. Last previous edition approved in 20022007 as
B353 – 02.B353 – 07. DOI: 10.1520/B0353-07.10.1520/B0353-12.
2
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 Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
B353 − 12
TABLE 1 ASTM and UNS Number Designations for
Reactor Grade Zirconium and Zirconium Alloys
Grade UNS Number
Reactor-grade zirconium R60001
Zirconium-tin alloy R60802
Zirconium-tin alloy R60804
Zirconium-niobium alloy R60901
Zirconium-niobium alloy R60904
3.1.4 mill finish tubes, n—tubes that have received all finishing operations subsequent to final anneal, which potentially affects
tube mechanica
...
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