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  • ASTM
    D7301-11 Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose
    Edition: 2011
    $103.58
    Unlimited Users per year

Description of ASTM-D7301 2011

ASTM D7301 - 11

Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose

Active Standard ASTM D7301 | Developed by Subcommittee: D02.F0

Book of Standards Volume: 05.05




ASTM D7301

1. Scope

1.1 This specification covers the classification, processing, and properties of nuclear grade graphite billets with dimensions sufficient to meet the designer s requirements for reflector blocks and core support structures, in a high temperature gas cooled reactor. The graphite classes specified here would be suitable for reactor core applications where neutron irradiation induced dimensional changes are not a significant design consideration.

1.2 The purpose of this specification is to document the minimum acceptable properties and levels of quality assurance and traceability for nuclear grade graphite suitable for components subjected to low irradiation dose. Nuclear graphites meeting the requirements of Specification D7219 are also suitable for components subjected to low neutron irradiation dose.

1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.


2. Referenced Documents (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.

ASTM Standards

C559 Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite Articles

C709 Terminology Relating to Manufactured Carbon and Graphite

C781 Practice for Testing Graphite and Boronated Graphite Materials for High-Temperature Gas-Cooled Nuclear Reactor Components

C838 Test Method for Bulk Density of As-Manufactured Carbon and Graphite Shapes

C1233 Practice for Determining Equivalent Boron Contents of Nuclear Materials

D346 Practice for Collection and Preparation of Coke Samples for Laboratory Analysis

D2638 Test Method for Real Density of Calcined Petroleum Coke by Helium Pycnometer

D7219 Specification for Isotropic and Near-isotropic Nuclear Graphites

ASME Standards

NQA-1 Quality Assurance Program Requirements for Nuclear Facilities

Keywords

chemical properties; mechanical properties; nuclear graphite; physical properties; processing;


ICS Code

ICS Number Code 27.120.20 (Nuclear power plants. Safety)


DOI: 10.1520/D7301-11

ASTM International is a member of CrossRef.

ASTM D7301

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About ASTM

ASTM International, formerly known as the American Society for Testing and Materials (ASTM), is a globally recognized leader in the development and delivery of international voluntary consensus standards. Today, some 12,000 ASTM standards are used around the world to improve product quality, enhance safety, facilitate market access and trade, and build consumer confidence. ASTM’s leadership in international standards development is driven by the contributions of its members: more than 30,000 of the world’s top technical experts and business professionals representing 150 countries. Working in an open and transparent process and using ASTM’s advanced electronic infrastructure, ASTM members deliver the test methods, specifications, guides, and practices that support industries and governments worldwide.
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