ASTM D7301-11(2015)

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

STANDARD published on 1.6.2015

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The information about the standard:

Designation standards: ASTM D7301-11(2015)
Note: WITHDRAWN
Publication date standards: 1.6.2015
SKU: NS-611373
The number of pages: 5
Approximate weight : 15 g (0.03 lbs)
Country: American technical standard
Category: Technical standards ASTM

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The category - similar standards:

Nuclear power plants. Safety

Annotation of standard text ASTM D7301-11(2015) :

Keywords:
chemical properties, mechanical properties, nuclear graphite, physical properties, processing,, ICS Number Code 27.120.20 (Nuclear power plants. Safety)

Additional information

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

D2638-21	Standard Test Method for Real Density of Calcined Petroleum Coke by Helium Pycnometer
D346-04	Standard Practice for Collection and Preparation of Coke Samples for Laboratory Analysis
C1233-15(2021)	Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials
C838-16(2023)	Standard Test Method for Bulk Density of As-Manufactured Carbon and Graphite Shapes

C709-09	Standard Terminology Relating to Manufactured Carbon and Graphite (Withdrawn 2017)
IEEE/ASTM SI 10	American National Standard for Use of the International System of Units (SI): The Modern Metric System
C559-16(2020)	Standard Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite Articles
D7219-19	Standard Specification for Isotropic and Near-isotropic Nuclear Graphites
C781-20	Standard Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components