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ASTM B811-13
Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding
Automaticky přeložený název:
Standardní specifikace pro tvářených slitiny zirkonu bezešvých trubek pro jaderný reaktor paliva Obklady
NORMA vydána dne 1.5.2013
Informace o normě:
Označení normy: ASTM B811-13
Poznámka: NEPLATNÁ
Datum vydání normy: 1.5.2013
Kód zboží: NS-8235
Počet stran: 16
Přibližná hmotnost: 48 g (0.11 liber)
Země: Americká technická norma
Kategorie: Technické normy ASTM
Anotace textu normy ASTM B811-13 :
Keywords:
fuel cladding, nuclear fuel, nuclear reactor, seamless, tubing, zirconium alloy, ICS Number Code 23.040.15 (Non-ferrous metal pipes)
Doplňující informace
| 1. Scope | |
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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. Grade |
UNS Number |
|
Zirconium-tin alloy |
R60802 |
|
Zirconium-tin alloy |
R60804 |
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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Standard Test Method for Corrosion Testing of Products of Zirconium, Hafnium, and Their Alloys in Water at 680 ?F [360 ?C] or in Steam at 750 ?F [400 ?C] |
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Standard Practice for Using Significant Digits in Test Data to Determine Conformance with Specifications |
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Standard Specification for Wrought Zirconium and Zirconium Alloy Seamless and Welded Tubes for Nuclear Service (Except Nuclear Fuel Cladding) (Includes all amendments and changes 4/25/2022). |
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Standard Test Methods for Determining Average Grain Size |
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ANSI B46.1 |
Surface Texture (Surface Roughness) Available from American Iron and Steel Institute (AISI), 1140 Connecticut Ave., NW, Suite 705, Washington, DC 20036, http://www.steel.org. |
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Standard Test Methods for Tension Testing of Metallic Materials [Metric] (Withdrawn 2008) |
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Standard Test Methods for Tension Testing of Metallic Materials |
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Standard Specification for Zirconium and Zirconium Alloy Ingots for Nuclear Application |
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Standard Test Methods for Elevated Temperature Tension Tests of Metallic Materials |
