ASTM B811-13(2022)e1 PDF
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
- Статус документа:
- Действующий
- Формат:
- Электронный (PDF)
- Количество страниц:
- 17
- Дата публикации:
- 1 апреля 2022 г.
- Издание:
- B811
- ICS:
- 23.040.15
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, 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.
Abstract
Overview
ASTM B811-13(2022)e1 specifies the requirements for seamless wrought zirconium alloy tubes used in nuclear reactor fuel cladding. Developed by ASTM International, this standard provides comprehensive guidelines for manufacturing, testing, inspection, and certification of zirconium alloy tubing to ensure their suitability for nuclear fuel cladding applications. Two grades of reactor-grade zirconium alloys are covered, recognizing their widespread use for safety and performance in nuclear reactors. The specification establishes requirements for key mechanical and chemical properties, dimensional tolerances, surface finishes, and inspection procedures, ensuring that the tubes meet stringent nuclear industry standards.
Key Topics
- Scope and Size Range: This standard applies to seamless zirconium-alloy tubes for nuclear fuel cladding, with outside diameters from 0.200 in. (5.1 mm) to 0.650 in. (16.5 mm) and wall thicknesses from 0.010 in. (0.25 mm) to 0.035 in. (0.89 mm).
- Zirconium Alloy Grades: The standard describes two grades, identified by their respective UNS numbers (R60802 and R60804), each with specific chemical composition requirements.
- Manufacturing Requirements: Tubes must be produced from ingots melted in multiple vacuum arc or electron beam furnaces designed for reactive materials, following strict process controls.
- Chemical Composition: Detailed limits for alloying elements and impurities are specified to ensure corrosion resistance and material integrity in nuclear environments.
- Mechanical Properties: Requirements include yield strength, tensile strength, elongation, and burst properties for recrystallization annealed tubes, verified through standardized tension and burst tests.
- Inspection and Testing: Comprehensive inspection procedures include ultrasonic flaw detection, surface inspection, dimensional checks, and representative sampling for laboratory testing.
- Documentation and Certification: Manufacturers must provide certification reports confirming compliance with all aspects of the specification, including test results for chemical analysis and mechanical performance.
Applications
- Nuclear Reactor Fuel Cladding: The primary application of ASTM B811-compliant zirconium alloy tubes is as fuel cladding in nuclear reactors. These tubes act as a barrier between nuclear fuel and reactor coolant, contributing to the safety, integrity, and efficiency of the reactor core.
- Nuclear Fuel Assemblies: The material’s resistance to corrosion and high-temperature mechanical stability make it ideal for use in fuel rods within light water reactors and other modern reactor designs.
- Safety Compliance: Adherence to this standard is essential for manufacturers supplying components for nuclear facilities, ensuring compliance with national and international nuclear safety regulations.
Related Standards
The following standards are referenced within ASTM B811 and are relevant to the manufacture and testing of zirconium alloy tubes for nuclear applications:
- ASTM B350/B350M: Specification for zirconium and zirconium alloy ingots for nuclear applications.
- ASTM B353: Specification for wrought zirconium and zirconium alloy seamless and welded tubes for nuclear service (excluding fuel cladding).
- ASTM E8/E8M: Test methods for tension testing of metallic materials.
- ASTM E21: Test methods for elevated temperature tension tests of metallic materials.
- ASTM E112: Test methods for determining average grain size.
- ASTM G2/G2M: Test method for corrosion testing of zirconium products in water or steam at elevated temperatures.
- ANSI B46.1: Standard for surface texture (surface roughness).
Practical Value
Manufacturers, quality assurance professionals, and nuclear reactor operators benefit from the rigorous guidelines set in ASTM B811-13(2022)e1. Compliance ensures the production of high-quality zirconium alloy seamless tubes that meet the strict mechanical, chemical, and performance requirements demanded by nuclear fuel cladding applications. Following this internationally recognized standard supports nuclear safety, material traceability, and regulatory acceptance within the global nuclear industry.
Keywords: zirconium alloy tubes, nuclear reactor fuel cladding, ASTM B811, seamless tubing, corrosion resistance, nuclear safety, zirconium alloy specification, mechanical properties, inspection, certification.
Технические детали
- Технический комитет
- B10 - Reactive and Refractory Metals and Alloys
- SKU
- ASTM B811-13(2022)e1
Похожие стандарты
Другие стандарты ASTM
ASTM-TPT-47
Phase I & Phase II Environmental Site Assessment Processes
Phase I & Phase II Environmental Site Assessment Processes
ASTM-TPT-8
Phase I Environmental Site Assessment Practices For Commercial Real Estate: Phase I Site Assessment & Transac…
ASTM-TPT-1137
ASTM D975 Standard Specification for Diesel Fuel
ASTM D975 Standard Specification for Diesel Fuel
ASTM-TPT-1202
ASTM D8421 Standard Test Method for Determination of Per- and Polyfluoroalkyl Substances (PFAS) in Aqueous Ma…
ASTM D8421 Standard Test Method -- eLearning Course
ASTM-TPT-691
Microaprendizagem para D4057: Amostragem de ponto (PT)
D4057 Microlearning: Spot Sampling Portuguese
ASTM-TPT-1091
Metodo de prueba estandar D4052 de ASTM -- Curso de aprendizaje electrónico (ES)
Modulo eLearning para ASTM D4052 en espanol
ASTM ACEM20180086
Using Neutron Radiography to Quantify the Settlement of Fresh Concrete
Specifications have been implemented for concrete bridge decks in North America that restrict the use of higher slump concrete mixtures primarily because of concerns about differential settlement and…
ASTM ACEM20180041
Experimental Study of Competing Failure of Reinforced Concrete Based on the Weibull Distribution
To predict the failure lifetime of reinforced concrete, a current accelerating corrosion test was performed on concrete by simulating the environment in an area with saline soil. To study the concret…