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Significance and Use
The purpose of this practice is to identify sample and test parameters that may influence graphite irradiation test results. This practice should not be construed as a requirement or recommendation that proprietary information be disclosed.
Irradiation results on graphite include dimensional changes and changes in properties that are used in reactor design. The irradiation data are reported in government documents, open literature publications, and are assembled into data manuals for use by reactor designers.
1.1 This practice covers information recommended for inclusion in reports giving graphite irradiation results.
2. Referenced Documents (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.
E261 Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
E525 Practice for Reporting Dosimetry Results on Nuclear Graphite (Discontinued 2001)
ICS Number Code 71.060.10 (Chemical elements)
UNSPSC Code 11101507(Graphite )
ASTM C625-95(2010), Standard Practice for Reporting Irradiation Results on Graphite, ASTM International, West Conshohocken, PA, 2010, www.astm.orgBack to Top