ASTM C1793-15(2024) PDF
Standard Guide for Development of Specifications for Fiber Reinforced Silicon Carbide-Silicon Carbide Composite Structures for Nuclear Applications
Standard Guide for Development of Specifications for Fiber Reinforced Silicon Carbide-Silicon Carbide Composite Structures for Nuclear Applications
- Статус документа:
- Действующий
- Формат:
- Электронный (PDF)
- Количество страниц:
- 14
- Дата публикации:
- 1 января 2024 г.
- Издание:
- C1793
- ICS:
- 83.120
SIGNIFICANCE AND USE 4.1 Composite materials consist by definition of a reinforcement phase in a matrix phase. In addition, ceramic matrix composites (CMCs) often contain measurable porosity which interacts with the reinforcement and matrix. And SiC-SiC composites often use a fiber interface coating which has an important mechanical function. The composition and structure of these different constituents in the CMC are commonly tailored for a specific application with detailed performance requirements. The tailoring involves the selection of the reinforcement fibers (composition, properties, morphology, etc.), the matrix (composition, properties, and morphology), the composite structure (component fractions, reinforcement architecture, interface coatings, porosity structure, microstructure, etc.), and the fabrication conditions (forming, assembly, forming, densification, finishing, etc.). The final engineering properties (physical, mechanical, thermal, electrical, etc.) can be tailored across a broad range with major directional anisotropy in the properties. 4.2 Specifications for specific CMC components covering materials, material processing, and fabrication procedures are developed to provide a basis for fabricating reproducible and reliable structures. Designer/users/producers have to write CMC specifications for specific applications with well-defined composition, structure, properties and processing requirements. But with the extensive breadth of selection in composition, structure, and properties in CMCs, it is virtually impossible to write a "generic" CMC specification applicable to any and all CMC applications that has the same type of structure and details of the commonly-used specifications for metal alloys. This guide is written to assist the designer/user/producer in developing a comprehensive and detailed material specification for a specific CMC application/component with a specific focus on nuclear applications. 4.3 The purpose of this guide is to provide guidance o... SCOPE 1.1 This document is a guide to preparing material specifications for silicon carbide fiber/silicon carbide matrix (SiC-SiC) composite structures (flat plates, rectangular bars, round rods, and tubes) manufactured specifically for structural components and for fuel cladding in nuclear reactor core applications. The SiC-SiC composites consist of silicon carbide fibers in a silicon carbide matrix produced by liquid infiltration/pyrolysis and/or by chemical vapor infiltration. 1.2 This guide provides direction and guidance for the development of a material specification for a specific SiC-SiC composite component or product for nuclear reactor applications. The guide considers composite constituents and structure, physical and chemical properties, mechanical properties, thermal properties, performance durability, methods of testing, materials and fabrication processing, and quality assurance. The SiC-SiC composite materials considered here would be suitable for nuclear reactor core applications where neutron irradiation-induced damage and dimensional changes are significant design considerations. (1-8)2 1.3 The component material specification is to be developed by the designer/purchaser/user. The designer/purchaser/user shall define and specify in detail any and all application-specific requirements for design, manufacturing, performance, and quality assurance of the ceramic composite component. Additional specification items for a specific component, beyond those listed in this guide, may be required based on intended use, such as geometric tolerances, permeability, bonding, sealing, attachment, and system integration. 1.4 This guide is specifically focused on SiC-SiC composite components and structures with flat plate, solid rectangular bar, solid round rod, and tubular geometries. 1.5 This guide may also be applicable to the development of specifications for SiC-SiC composites used for other structural applic...
Abstract
Overview
ASTM C1793-15(2024), "Standard Guide for Development of Specifications for Fiber Reinforced Silicon Carbide-Silicon Carbide Composite Structures for Nuclear Applications," provides a comprehensive framework for drafting specifications for silicon carbide (SiC) fiber-reinforced SiC matrix composite components. Developed by ASTM International, this standard focuses on SiC-SiC composites used in nuclear reactor core structures, including flat plates, bars, rods, and tubular forms.
SiC-SiC composites are favored for nuclear settings due to their exceptional thermal stability, oxidation resistance, radiation tolerance, and mechanical robustness. The guide details how to define and document requirements for materials, processing, and quality control to ensure the reliable, repeatable production of these advanced composites.
Key Topics
-
Composite Constituents:
- SiC-SiC composites consist of silicon carbide fibers embedded within a silicon carbide matrix.
- The selection of fiber type, matrix structure, fiber architecture, and interface coating is tailored based on performance demands.
-
Specification Development:
- Guides the creation of detailed material specifications for SiC-SiC composites with nuclear applications in mind.
- Emphasizes the importance of defining composition, structure, properties, and processing requirements to match the intended use.
-
Physical and Mechanical Properties:
- Composites are engineered to specific requirements of density, porosity, thermal expansion, conductivity, electrical resistivity, and mechanical strength.
- Properties may be tailored with significant anisotropy, depending on fiber architecture and intended directionality of use.
-
Quality Assurance and Testing:
- Recommends methods for testing chemical purity, mechanical strength, and physical characteristics using ASTM standards.
- Includes direction on statistical sampling, quality assurance, and traceability for each production batch.
-
Nuclear Application Specifics:
- Outlines special considerations for controlling impurities to minimize neutron absorption and avoid undesired chemical reactivity.
- Specifications must address requirements unique to nuclear service, such as radiation-induced dimensional changes and elevated temperature performance.
Applications
-
Nuclear Reactor Core Structures:
- SiC-SiC composites are primarily used in structural components and fuel cladding for nuclear reactors, where performance under irradiation and high temperature is critical.
- Their low neutron absorption and high radiation tolerance make them suitable for advanced reactor designs.
-
Other Structural Uses:
- While focused on nuclear applications, the guide also supports the development of specifications for SiC-SiC composites in other high-temperature or corrosive environments, provided nuclear-specific factors are modified as required.
-
Component Geometry:
- Applicable to flat plates, solid bars (rectangular and round), and tubes; these shapes are common in nuclear reactor core construction and broader engineering applications.
Related Standards
To ensure consistency and accuracy in specification and testing, ASTM C1793-15(2024) references several related standards, including:
- ASTM C242: Terminology of Ceramic Whitewares and Related Products
- ASTM C559, C838, C1039: Testing of density and porosity in ceramic materials
- ASTM C1470, E228, E289: Methods for measuring thermal expansion and conductivity
- ASTM C1233: Determining equivalent boron content, important for nuclear-grade materials
- ASTM D3878, D4018: Terminology and properties for composite materials and fibers
- ASME B46.1: Surface texture (surface roughness) assessment
Consistent application of these standards ensures reliable characterization and repeatable quality for SiC-SiC composites used in demanding service environments such as nuclear reactors.
Keywords: ASTM C1793, SiC-SiC composites, silicon carbide fiber, ceramic matrix composites, nuclear reactor materials, material specification guide, mechanical testing ASTM, composite properties, fiber architecture, testing standards for composites, nuclear applications, ASTM standards for ceramics.
Технические детали
- Технический комитет
- C28 - Advanced Ceramics
- SKU
- ASTM C1793-15(2024)
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