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ASTM-B811:2007 Edition

ASTM-B811:2007 Edition

$44.96

B811-02(2007) Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding

Published By Publication Date Number of Pages
ASTM 2007 16
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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/dm 2 , 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.

PDF Catalog

PDF Pages PDF Title
1 Scope
Referenced Documents
Terminology
TABLE 1
2 Ordering Information
Materials and Manufacture
Chemical Composition
3 Mechanical Properties
TABLE 2
TABLE 3
TABLE 4
4 Other Requirements
Permissible Variations in Dimensions
Sampling
Number of Tests and Resampling
Inspection
5 Significance of Numerical Limits
Rejection
Referee
Certification
Packaging and Package Marking
Keywords
6 A1. ROOM TEMPERATURE CLOSED-END BURST TESTING PROCEDURE FOR ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING TUBES
A1.1 Scope
A1.2 Apparatus
A1.3 Preparation of Specimen
A1.4 Procedure
A1.5 Report
7 A2. PROCEDURE FOR DETERMINATION OF RADIAL HYDRIDE ORIENTATION FRACTION IN ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING TUBES
A2.1 Scope
A2.2 Procedure
A2.3 Preparation of Micrograph
A2.4 Evaluation Method
A3. PROCEDURE FOR ULTRASONIC FLAW TESTING OF ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING TUBES
A3.1 Scope
A3.2. Terminology
A3.3 Surface Condition
A3.4 Apparatus
8 A3.5 Couplant
A3.6 Calibration Standards
FIG. A3.1
FIG. A3.2
9 A3.7 Calibration of the Apparatus
A3.8 Inspection Procedure
FIG. A3.3
FIG. A3.4
10 FIG. A3.5
11 A3.9 Interpretation of Results
A3.10 Report
A4. RECOMMENDED PROCEDURE FOR CONTRACTILE STRAIN RATIO TESTING OF ZIRCONIUM ALLOY TUBING
A4.1 Scope
A4.2 Apparatus
A4.3 Preparation of Specimen
A4.4 Procedure
FIG. A4.1
12 A4.5 Calculation
X1. AN ADVISORY GUIDE TO TRANSDUCER SELECTION
X1.1
X1.2
X1.3
X1.4 Transducers for Shear-Wave Inspection
FIG. X1.1
13 X1.5 Transducers for Lamb-Wave Inspection
X2. AN ADVISORY GUIDE TO TRANSDUCER POSITIONING
X2.1
X2.2 Transducer Positioning for Shear Wave Testing
FIG. X1.2
14 FIG. X2.1
15 X2.3 Transducer Positioning for Lamb Wave Inspection
X3. RATIONALE (COMMENTARY)
X3.1
X3.2
X3.3
X3.4
X3.5
X3.6
X3.7
FIG. X2.2
FIG. X2.3
16 X3.8
X3.9
X3.10
X3.11
X3.12
X3.13

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