Logo

ASTM B811-13(2022)e1

Historical Reaffirmation

Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding

$76.00

$76.00

$136.80


Sub Total (1 Item(s))

$ 0.00

Estimated Shipping

$ 0.00

Total (Pre-Tax)

$ 0.00


Stay effortlessly up-to-date with the latest standard revisions. When new versions are released, they're automatically charged and delivered to you, ensuring seamless compliance.

Document Preview Not Available...

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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.

1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.


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.


SDO ASTM: ASTM International
Document Number B811
Publication Date April 1, 2022
Language en - English
Page Count 17
Revision Level 13(2022)e1
Supercedes
Committee B10.02
Publish Date Document Id Type View
May 1, 2013 B0811-13E01 Revision
May 1, 2013 B0811-13 Revision
Oct. 10, 2002 B0811-02 Revision
Nov. 10, 2001 B0811-97 Revision
Nov. 10, 2001 B0811-01 Revision
April 1, 2022 B0811-13R22E01 Reaffirmation
Nov. 1, 2017 B0811-13R17 Reaffirmation
May 1, 2007 B0811-02R07 Reaffirmation