ASTM B811-02(2007)
(Specification)Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding
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.
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Designation:B811 −02(Reapproved2007)
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.
1. Scope E8MTestMethodsforTensionTestingofMetallicMaterials
[Metric] (Withdrawn 2008)
1.1 This specification covers seamless wrought zirconium-
E21TestMethodsforElevatedTemperatureTensionTestsof
alloy tubes for nuclear fuel cladding application, in the outside
Metallic Materials
diameter (OD) size range of 0.200 in. (5.1 mm) to 0.650 in.
E29Practice for Using Significant Digits in Test Data to
(16.5 mm) and wall thickness range of 0.010 in. (0.25 mm) to
Determine Conformance with Specifications
0.035 in. (0.89 mm).
E112Test Methods for Determining Average Grain Size
1.2 Two grades of reactor grade zirconium alloys are
G2/G2MTest Method for Corrosion Testing of Products of
described.
Zirconium, Hafnium, and TheirAlloys in Water at 680°F
1.2.1 The present UNS numbers designated for the two
[360°C] or in Steam at 750°F [400°C]
grades are given in Table 1.
2.2 Other Document:
1.3 Unlessasingleunitisused,forexamplecorrosionmass ANSI B46.1Surface Texture (Surface Roughness)
gain in mg/dm , the values stated in either inch-pound or SI
3. Terminology
units are to be regarded separately as standard. The values
stated in each system are not exact equivalents; therefore each
3.1 Definitions of Terms Specific to This Standard:
system must be used independently of the other. SI values 3.1.1 dimensions, n—tube dimensions are outside diameter,
cannot be mixed with inch-pound values.
inside diameter, and wall thickness. Only two of these param-
eters may be specified in addition to length, except minimum
1.4 The following precautionary caveat pertains only to the
wallmaybespecifiedwithoutsideandinsidediameter.Ineach
test method portions of this specification: This standard does
case, ovality and wall thickness variation (WTV) may be
not purport to address all of the safety concerns, if any,
specified as additional requirements.
associated with its use. It is the responsibility of the user of this
standard to establish appropriate safety and health practices
3.1.2 hydride orientation fraction, Fn, n—the ratio of hy-
and determine the applicability of regulatory limitations prior
dride platelets oriented in the radial direction to the total
to use.
hydride platelets in the field examined.
3.1.3 lot size, n—a lot shall consist of all tubes of the same
2. Referenced Documents
size,shape,condition,andfinishproducedfromthesameingot
2.1 ASTM Standards:
by the same reduction schedule and heat treatment. The final
B350/B350MSpecification for Zirconium and Zirconium
heat treatment shall be in a single furnace charge.
Alloy Ingots for Nuclear Application
3.1.4 mill finish tubes, n—tubes that have received all
B353Specification for Wrought Zirconium and Zirconium
finishing operations subsequent to final anneal, which poten-
Alloy Seamless and Welded Tubes for Nuclear Service
tially affects tube mechanical, dimensional, or surface condi-
(Except Nuclear Fuel Cladding)
tion.These operations include, but are not limited to, pickling,
E8Test Methods for Tension Testing of Metallic Materials
cleaning, outer and inner surface abrasive conditioning, and
straightening.
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 Alloys and is the direct responsibility of
minimum diameter, either outer or inner, as determined at any
Subcommittee B10.02 on Zirconium and Hafnium.
one transverse cross-section of the tube.
Current edition approved May 1, 2007. Published May 2007. Originally
approved in 1990. Last previous edition approved in 2002 as B811–02. DOI:
10.1520/B0811-02R07.
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 service@astm.org. For Annual Book of ASTM www.astm.org.
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the ASTM website. Ave., NW, Suite 705, Washington, DC 20036, http://www.steel.org.
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B811−02(2007)
TABLE 1 ASTM and UNS Number Designation for Reactor Grade in. nominal ID by 0.032 in. minimum wall by 10 ft long with a maximum
Zirconium Alloys
OD ovality of 0.004 in. and maximum WTV of 0.005 in. in accordance
withB811–XX.Maximumsurfacefinishtobe50µin.RaODand50µin.
Grade UNS Number
Ra ID.
Zirconium-tin alloy R60802
Zirconium-tin alloy R60804
4.2 In addition to the information in 4.1, the following
points of agreement between the manufacturer and purchaser
should be specified in the purchase order as required:
4.2.1 Method of determining yield strength if other than
0.2% offset method (see Section 7),
3.1.6 wall thickness variation (WTV), n—the difference
4.2.2 Initial gage length of mechanical test samples for
between maximum and minimum wall thickness measured at
determining elongation after rupture if other than 2 in. (50
any one transverse cross-section of the tube.
mm),
NOTE1—MeasurementofovalityandWTVmadebyahelicalscanwith
4.2.3 Mechanical property requirements for tube other than
a pitch not exceeding 0.25 in. (6.5 mm) shall be considered as equivalent
fully recrystallization annealed (see Section 7),
to “at any one cross-section of the tube.”
4.2.4 Location of the inside diameter plugs in elevated
3.2 Lot Definitions:
temperature short-time tension test, when specified (see Sec-
3.2.1 castings, n—alotshallconsistofallcastingsproduced
tion 7.1.3),
from the same pour.
4.2.5 Specimen temperature(s) during mechanical testing if
3.2.2 ingot, n—no definition required. other than room temperature and properties and test require-
ments (see Section 7), and
3.2.3 rounds,flats,tubes,andwroughtpowdermetallurgical
4.2.6 Grain size requirements and specimen heat treatment
products (single definition, common to nuclear and non-
method for stress relief annealed tubes (see Section 8.1),
nuclear standards) , n—a lot shall consist of a material of the
4.2.7 Hydride orientation specimen heat treatment, if
samesize,shape,condition,andfinishproducedfromthesame
required,evaluationmethod,andmagnificationofphotomicro-
ingot or powder blend by the same reduction schedule and the
graph (see Annex A2),
same heat treatment parameters. Unless otherwise agreed
4.2.8 For hydride orientation, angle theta (θ) for determin-
between manufacturer and purchaser, a lot shall be limited to
ing radial platelets (see Section 8.3 and Annex A2).
the product of an 8 h period for final continuous anneal, or to
4.2.9 Burst property acceptance requirements, when speci-
a single furnace load for final batch anneal.
fied (see Section 8.4),
3.2.4 sponge, n—a lot shall consist of a single blend
4.2.10 Use of mandrel and post burst test measurement
produced at one time.
technique (see Annex A1).
3.2.5 weld fittings, n—definition is to be mutually agreed
4.2.11 Contractile strain ratio acceptance criteria, when
upon between manufacturer and the purchaser.
specified (see Section 7.3 and Annex A4).
4. Ordering Information
5. Materials and Manufacture
4.1 Purchase orders for tubes covered in this specification
5.1 Tubes covered by this specification shall be made from
shall include the following information to describe adequately
ingots produced by multiple vacuum arc or electron beam
the desired material:
melting in furnaces of a type conventionally used for reactive
4.1.1 Quantity,
materials.
4.1.2 Grade (see Table 1),
5.2 Tubes shall be made by a process approved by the
4.1.3 Condition (recrystallization annealed or stress relief
purchaser.
annealed),
4.1.4 Tube dimensions and tolerance,
6. Chemical Composition
4.1.5 ASTM designation and year of issue,
6.1 The tubes shall conform to the requirements for chemi-
4.1.6 Surface texture on (roughness) the inside and outside
cal composition prescribed in Table 2.
surfaces (R (micro-inches or micrometers)),
a
4.1.7 Surface condition on the inside diameter (ID) and
6.2 Chemical Analysis:
outside diameter (OD) surfaces (as pickled, blasted, abraded,
6.2.1 The ingot analysis made in accordance with Specifi-
etc.),
cation B350/B350M shall be considered the chemical analysis
4.1.8 Sample test conditions (if other than mill finish
for tubes produced to this specification except for oxygen,
condition) and standards for corrosion test (see Section 8.2),
hydrogen, and nitrogen content, which shall be determined on
4.1.9 General test requirements and test plan for lots (see
the mill finished tube. Alternatively, an intermediate or final
Section 10),
size product may be sampled during processing with the same
4.1.10 Number of tests and resampling plan and require-
frequency and in the same positions relative to the ingot as
ments (see Section 11), and
specified in Specification B350/B350M to determine the
4.1.11 Certification of test (see Section 16).
composition,exceptforhydrogen,oxygen,andnitrogen,which
shall be determined on the mill finished tube.
NOTE 2—Atypical order description may read as follows: 1500 pieces
6.2.2 Analysis shall be made using the manufacturer’s
of seamless zirconium-alloy fuel clad tubes OD abraded and ID pickled,
Grade R60804, recrystallization annealed 0.650 in. nominal OD by 0.580 standard methods. In the event of disagreement as to the
B811−02(2007)
TABLE 2 Chemical Requirements TABLE 4 Mechanical Properties of Recrystallization Annealed
A
Tubes Tested at Room Temperature
UNS Number UNS Number
Element
R60802 R60804 UNS Numbers
R60802 and R60804
Composition, Weight %:
Tension Test Properties (Longitudinal Direction):
Tin 1.20 to 1.70 1.20 to 1.70
Yield Strength (0.2 % Offset), min 35 ksi (240 MPa)
Iron 0.07 to 0.20 0.18 to 0.24
Tensile Strength, min 60 ksi (415 MPa)
Chromium 0.05 to 0.15 0.07 to 0.13
Elongation, min %, 2 in. (50 mm) initial gage length 20
Nickel 0.03 to 0.08 . . .
Oxygen 0.09 to 0.16 0.09 to 0.16
Burst Test Properties:
Iron plus chromium plus 0.18 to 0.38 . . .
Ultimate Hoop Strength, min 72.6 ksi (500 MPa)
Nickel
Percent Total Circumferential Elongation (% TCE), 20
Iron plus chromium . . . 0.28 to 0.37
min
A
Maximum Impurities, Weight %:
“RT” represents room temperature; Note 4 in Test Methods E8 and E8M
Aluminum 0.0075 0.0075 indicates that RT shall be considered to be 50 to 100°F (10 to 38°C) unless
Boron 0.00005 0.00005 otherwise specified. Paragraph 9.4.4 in Test Methods E21 states that for the
Cadmium 0.00005 0.00005 duration of the test, the difference between the indicated temperature and the
Calcium 0.0030 0.0030 nominaltesttemperatureisnottoexceed±5°F(3°C)fortestsat1800°F(1000°C)
Carbon 0.027 0.027 and lower, and ±10°F (6°C) for tests at higher temperatures.
Cobalt 0.0020 0.0020
Copper 0.0050 0.0050
Hafnium 0.010 0.010
Hydrogen 0.0025 0.0025
Magnesium 0.0020 0.0020
Manganese 0.0050 0.0050
7.1.2 When so specified by the purchaser, the tension
Molybdenum 0.0050 0.0050
propertiesshallalsobedeterminedattheelevatedtemperatures
Nickel . . . 0.0070
Niobium 0.0100 0.0100
and shall conform to the limits specified by the purchaser.
Nitrogen 0.0080 0.0080
7.1.3 Thetensiontestshallbeconductedinaccordancewith
Silicon 0.0120 0.0120
Tungsten 0.0100 0.0100 TestMethodsE8orE21.Yieldstrengthshallbedeterminedby
Titanium 0.0050 0.0050
the 0.2% offset method. The tension properties shall be
Uranium (Total) 0.00035 0.00035
determined using a strain rate of 0.003 to 0.007 in./in.-min
(mm/mm-min) through the yield strength. After the yield
strength has been exceeded, the cross head speed may be
chemicalcompositionofthemetal,thecomposition,forreferee
increased to approximately 0.05 in./in.-min (mm/mm-min) to
purposes, shall be determined by a mutually acceptable labo-
failure.
ratory.
7.2 Burst Testing:
6.2.3 Product Analysis—Product analysis is a check analy-
7.2.1 Burst testing, when specified, shall be performed at
sis made by the purchaser for the purpose of verifying the
room temperature on finished tubing. Recrystallization an-
compositionofthelot.Thepermissiblevariationintheproduct
nealed tubes shall conform to the requirements for burst
analysis from the specification range is as listed in Table 3.
properties at room temperature prescribed in Table 4. If burst
test is specified for cold worked and stress relief annealed
7. Mechanical Properties
tubes, the acceptance criteria shall be agreed upon between the
7.1 Tension Properties:
manufacturer and the purchaser.
7.1.1 Recrystallization annealed tubes shall conform to the
7.2.2 If elevated temperature burst test is specified, the test
requirements for mechanical properties at room temperature
method and acceptance criteria shall be agreed upon between
prescribed in Table 4. For tubes in the cold worked and stress
the manufacturer and purchaser.
relief annealed condition, tension property requirements are to
NOTE 3—Burst properties obtained at room temperature were the
be mutually agreed upon between the manufacturer and the
subject of a 1971 round robin conducted by ASTM subcommittee
purchaser.
B10.02. Variability in values was relatively large and should be consid-
ered in setting specific limits.
TABLE 3 Permissible Variation in Product Analysis
7.3 Contractile Strain Ratio (CSR):
Permissible Variation from 7.3.1 When so specified by the purchaser, the contractile
the Specification Range
strainratio(CSR)shallbedeterminedatroomtemperatureand
(Table 2), %
shall conform to limits that are mutually agreed upon between
Alloying Elements:
the manufacturer and purchaser.
Tin 0.050
Iron 0.020
7.3.2 Contractile strain ratio testing shall be conducted in
Chromium 0.010
accordance with Annex A4.
Nickel 0.010
Iron plus chromium 0.020
NOTE4—Contractilestrainratiotestingwasthesubjectofa1993round
Iron plus chromium plus nickel 0.020
robin conducted by ASTM Subcommittee B10.02 using specimens with
Oxygen 0.020
diameter approximately 0.4 in. (10 mm). The variability was relatively
Impurity Element:
Each 20 ppm or 20 %,
whichever is smaller
STP 551, “Zirconium in Nuclear Applications,” ASTM, 1974, pp. 14–28.
B811−02(2007)
large and should be considered in setting specific limits. The following
11. Number of Tests and Resampling
two-sigma li
...
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