Reporting dosimetry results on nuclear graphite
Journal Article
·
· Annu. Book ASTM Stand.; (United States)
OSTI ID:5553847
The recommended practice covers procedures for determining and reporting the neutron flux density and fluence for the correlation of radiation-induced changes in nuclear graphites. The purpose of the recommended 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. Excluded are graphite test specimens containing fissionable materials and specimens containing materials having high neutron cross sections. The practice includes a discussion of significance, exposure unit for graphite irradiations, reporting, precision, and accuracy. (JMT)
- OSTI ID:
- 5553847
- Journal Information:
- Annu. Book ASTM Stand.; (United States), Vol. 45
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
GRAPHITE
PHYSICAL RADIATION EFFECTS
MATERIALS TESTING
STANDARDS
ACCURACY
CROSS SECTIONS
DENSITY
DOSIMETRY
FISSIONABLE MATERIALS
IRRADIATION
MEASURING METHODS
MODERATORS
NEUTRON FLUENCE
NEUTRON FLUX
NUCLEAR INDUSTRY
STANDARDIZATION
CARBON
ELEMENTAL MINERALS
ELEMENTS
INDUSTRY
MATERIALS
MINERALS
NONMETALS
PHYSICAL PROPERTIES
RADIATION EFFECTS
RADIATION FLUX
TESTING
360605* - Materials- Radiation Effects
GRAPHITE
PHYSICAL RADIATION EFFECTS
MATERIALS TESTING
STANDARDS
ACCURACY
CROSS SECTIONS
DENSITY
DOSIMETRY
FISSIONABLE MATERIALS
IRRADIATION
MEASURING METHODS
MODERATORS
NEUTRON FLUENCE
NEUTRON FLUX
NUCLEAR INDUSTRY
STANDARDIZATION
CARBON
ELEMENTAL MINERALS
ELEMENTS
INDUSTRY
MATERIALS
MINERALS
NONMETALS
PHYSICAL PROPERTIES
RADIATION EFFECTS
RADIATION FLUX
TESTING
360605* - Materials- Radiation Effects