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

SCOPE
1.1 This specification covers seamless and welded wrought zirconium and zirconium-alloy tubes for nuclear application. Nuclear fuel cladding is covered in Specification 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/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.

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09-Oct-2002
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ASTM B353-02 - Standard Specification for Wrought Zirconium and Zirconium Alloy Seamless and Welded Tubes for Nuclear Service (Except Nuclear Fuel Cladding)
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NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation: B 353 – 02
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 (e) indicates an editorial change since the last revision or reapproval.
TABLE 1 ASTM and UNS Number Designations for
1. Scope
Reactor Grade Zirconium and Zirconium Alloys
1.1 This specification covers seamless and welded wrought
Grade UNS Number
zirconium and zirconium-alloy tubes for nuclear application.
Reactor-grade zirconium R60001
Nuclear fuel cladding is covered in Specification B811.
Zirconium-tin alloy R60802
1.2 Five grades of reactor grade zirconium and zirconium
Zirconium-tin alloy R60804
alloys suitable for nuclear application are described. Zirconium-niobium alloy R60901
Zirconium-niobium alloy R60904
1.2.1 The present UNS numbers designated for the five
grades are given in Table 1.
1.3 Unlessasingleunitisused,forexamplecorrosionmass
2
gain in mg/dm , the values stated in either inch-pound or SI E112 Test Methods for Determining the Average Grain
3
units are to be regarded separately as standard. The values Size
stated in each system are not exact equivalents; therefore each G2 Test Method for Corrosion Testing of Products of
system must be used independently of the other. SI values Zirconium, Hafnium, and Their Alloys in Water at 680°F
5
cannot be mixed with inch-pound values. or in Steam at 750°F
1.4 Thefollowingprecautionarycaveatpertainsonlytothe G2M Test Method for Corrosion Testing of Products of
test method portions of this specification. This standard does Zirconium, Hafnium andTheirAlloys inWater at 633K or
5
not purport to address all of the safety concerns, if any, in Steam at 673K [Metric]
associated with its use. It is the responsibility of the user of this
3. Terminology
standard to establish appropriate safety and health practices
and determine the applicability of regulatory limitations prior 3.1 Definitions of Terms Specific to This Standard:
to use. 3.1.1 dimensions, n—tube dimensions are outside diameter,
inside diameter, and wall thickness. Only two of these param-
2. Referenced Documents
eters may be specified in addition to length, except minimum
2.1 ASTM Standards: wallmaybespecifiedwithoutsideandinsidediameter.Ineach
B350 Specification for Zirconium and Zirconium Alloy case, ovality and wall thickness variation (WTV) may be
2
Ingots for Nuclear Application specified as additional requirements.
B811 SpecificationforWroughtZirconiumAlloySeamless 3.1.2 hydride orientation fraction, Fn, n—the ratio of hy-
2
Tubes for Nuclear Reactor Fuel Cladding dride platelets oriented in the radial direction to the total
3
E8 TestMethodsforTensionTestingofMetallicMaterials hydride platelets in the field examined.
E21 Test Methods for Elevated Temperature Tension Tests 3.1.3 Lot Definitions:
3
of Metallic Materials 3.1.3.1 castings—alotshallconsistofallcastingsproduced
E29 Practice for Using Significant Digits in Test Data to from the same pour.
4
Determine Conformance with Specifications 3.1.3.2 ingot—no definition required.
3.1.3.3 rounds, flats, tubes, and wrought powder metallur-
gical products (single definition, common to nuclear and
non-nuclear standards)—alotshallconsistofamaterialofthe
1
This specification is under the jurisdiction of ASTM Committee B10 on
samesize,shape,condition,andfinishproducedfromthesame
Reactive and Refractory Metals and Alloysand is the direct responsibility of
ingot or powder blend by the same reduction schedule and the
Subcommittee B10.02on Zirconium and Hafnium.
Current edition approved Oct. 10, 2002. Published December 2002. Originally
same heat treatment parameters. Unless otherwise agreed
e1
published as B353–60T. Last previous edition B353–01 .
2
Annual Book of ASTM Standards, Vol 02.04.
3
Annual Book of ASTM Standards, Vol 03.01.
4 5
Annual Book of ASTM Standards, Vol 14.02. Annual Book of ASTM Standards, Vol 03.02.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
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B353–02
between manufacturer and purchaser, a lot shall be limited to 4.1.7 Surface finish on the inside (ID) and the outside (OD)
the product of an 8 h period for final continuous anneal, or to surfaces (Ra (in micro-inches or micrometres), unless other-
a single furnace load for final batch anneal. wise stated),
3.1.3.4 sponge—a lot shall consist of a single blend pro-
4.1.8 Surface condition on the inside (ID) and outside (OD)
duced at one time.
surfaces (as pickled, abraded, etc.
...

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