ASTM B353-07
(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.
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 B 811.
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.
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 −07
StandardSpecification 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 Their Alloys 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
2 3.1.1 dimensions, n—tube dimensions are outside diameter,
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,
associated with its use. It is the responsibility of the user of this hydride platelets in the field examined.
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
2. Referenced Documents or powder blend by the same reduction schedule and the same
2
heat treatment parameters. Unless otherwise agreed between
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
Tubes for Nuclear Reactor Fuel Cladding
3.1.4 mill finish tubes, n—tubes that have received all
E8Test Methods for Tension Testing of Metallic Materials
finishing operations subsequent to final anneal, which poten-
E21TestMethodsforElevatedTemperatureTensionTestsof
tially affects tube mechanical, dimensional, or surface condi-
Metallic Materials
tion. These operations include, but are not limited to, pickling,
cleaning, outer and inner surface abrasive conditioning, and
1
This specification is under the jurisdiction of ASTM Committee B10 on
straightening.
Reactive and Refractory Metals and Alloysand is the direct responsibility of
Subcommittee B10.02 on Zirconium and Hafnium. 3.1.5 ovality, n—the difference between the maximum and
Current edition approved May 1, 2007. Published May 2007. Originally
minimum diameter, either outer or inner, as determined at any
approved in 1960. Last previous edition approved in 2002 as B353–02. DOI:
one transverse cross section of the tube.
10.1520/B0353-07.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
3.1.6 wall thickness variation (WTV), n—the difference
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
between maximum and minimum wall thickness measured at
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. any one transverse cross section of the tube.
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B353−07
TABLE 1 ASTM and UNS Number Designations for
4.1.9 Mutually agreed-upon inspection standards in accor-
Reactor Grade Zirconium and Zirconium Alloys
dance with 9.2
...
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