TSX graphite for extended use in the N-Reactor

Technical Report · Thu Aug 01 00:00:00 EDT 1985

DOI:https://doi.org/10.2172/5273245· OSTI ID:5273245

Kennedy, C R

This report reviews the limited amount of irradiation data available for grade TSX graphite with the purpose of obtaining reasonable estimates of material behavior. The results are enhanced by obtaining generalized behavior characteristics demonstrated by similar grades of graphite, such as CSF, AGOT, and PGA. Intent of this work is to furnish the necessary coefficients to describe the material behavior for inclusion in the constitutive equations for the anisotropic graphite grade TSX. Estimates of the free-dimensional changes of TSX graphite as a function of temperature and fluence have been made and shown to be in good agreement with the data. The effects of irradiation on other physical properties, such as elastic moduli, conductivity, and coefficient of thermal expansion, are also described. The irradiation creep characteristics of TSX graphite are also estimated on the basis of data for similar grades of graphite in the US and Europe. Crude approximations of stresses generated in the keyed structure were made to demonstrate the magnitude of the problem. The results clearly predict that the filler-block keys will fail and the tube-block keys will not. It is also indicated that the overall stack height growth will be increased by 25 to 38 mm (1 to 1.5 in.) because of creep.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5273245
• Report Number(s): ORNL/TM-9710; ON: DE85018149
• Resource Relation: Other Information: Portions of this document are illegible in microfiche products. Original copy available until stock is exhausted
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
GRAPHITE
PHYSICAL RADIATION EFFECTS
N-REACTOR
REACTOR MATERIALS
CREEP
DIMENSIONS
ELASTICITY
FRACTURE PROPERTIES
NEUTRON FLUENCE
STRESSES
THERMAL CONDUCTIVITY
THERMAL EXPANSION
CARBON
ELEMENTAL MINERALS
ELEMENTS
ENRICHED URANIUM REACTORS
EXPANSION
GRAPHITE MODERATED REACTORS
LWGR TYPE REACTORS
MATERIALS
MECHANICAL PROPERTIES
MINERALS
NONMETALS
PHYSICAL PROPERTIES
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRODUCTION REACTORS
RADIATION EFFECTS
REACTORS
TENSILE PROPERTIES
THERMODYNAMIC PROPERTIES
WATER COOLED REACTORS
360605* - Materials- Radiation Effects