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Review of high-temperature graphite irradiation behavior

Technical Report ·
DOI:https://doi.org/10.2172/6707573· OSTI ID:6707573
;
The irradiation behavior of reactor graphites at high temperatures (500/sup 0/ to 1400/sup 0/C) to high fluences (up to 4 x 10/sup 22/ n/cm/sup 2/) is reviewed. Recent data generated during the period 1965 through 1971 are emphasized. The review covers graphite manufacture, irradiation damage, dimensional and structural changes, thermal expansion, thermal conductivity, Young's modulus, strength, and irradiation-induced creep.
Research Organization:
Gulf General Atomic Co., San Diego, CA (USA)
DOE Contract Number:
AM03-76SF00167
OSTI ID:
6707573
Report Number(s):
GULF-GA-A-10988
Country of Publication:
United States
Language:
English

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Related Subjects

36 MATERIALS SCIENCE
360605* -- Materials-- Radiation Effects
CARBON
CREEP
CRYSTAL STRUCTURE
DIMENSIONS
DOCUMENT TYPES
ELEMENTS
EXPANSION
FABRICATION
GRAPHITE
HIGH TEMPERATURE
MECHANICAL PROPERTIES
MICROSTRUCTURE
NEUTRON FLUENCE
NONMETALS
PHYSICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REVIEWS
TEMPERATURE DEPENDENCE
THERMAL CONDUCTIVITY
THERMAL EXPANSION
THERMODYNAMIC PROPERTIES
VERY HIGH TEMPERATURE
YOUNG MODULUS