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Scope

1.1 This practice covers procedures for determining and reporting the neutron fluence rate and fluence for the correlation of radiation-induced changes in nuclear graphites.

1.2 The purpose of this practice is to achieve better correlation and interpretation of new data in the field of radiation effects testing of specimens of graphites to be used for moderator or reflector components of fission reactors.

1.3 Excluded from this practice are graphite test specimens containing fissionable materials and specimens containing materials having high neutron cross sections.

Keywords

Data analysis-recording/reporting results (nuclear); Dosimetry; Fluence; Graphite-nuclear; Neutron radiation; Nuclear graphite; Radiation exposure-nuclear materials/applications; Radioactivation-fast neutron flux; reporting dosimetry results on nuclear graphite, practice; ICS Number Code 71.060.10 (Chemical elements)

To find similar documents by ASTM Volume:

12.02 (Nuclear (II), Solar, and Geothermal Energy)

To find similar documents by classification:

71.060.10 (Chemical elements)

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