Effect of steam oxidation on the tensile strength of HTGR structural graphites
The core support system of the General Atomic Company design High Temperature Gas-Cooled Reactor (HTGR) contains type PGX graphite as core support blocks. The change in ultimate tensile strength of PGX graphite specimens with oxidation (burnoff) has been determined in a safety-related experimental program at Brookhaven National Laboratory(BNL). It is shown that Fe, an impurity in PGX graphite, plays a key role in the rate of oxidation. The subsequent failure of the graphite specimens is dependent upon the total weight loss due to oxidation. The results indicate that the loss in tensile strength is exponentially related to the percent burnoff (weight loss), and that grain orientation of the specimen has a significant effect.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- EY-76-C-02-0016
- OSTI ID:
- 7096088
- Report Number(s):
- BNL-NUREG-23000; CONF-770708-3
- Country of Publication:
- United States
- Language:
- English
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210300* -- Power Reactors
Nonbreeding
Graphite Moderated
36 MATERIALS SCIENCE
360604 -- Materials-- Corrosion
Erosion
& Degradation
CARBON
CHEMICAL REACTIONS
ELEMENTS
GAS COOLED REACTORS
GRAPHITE
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
NONMETALS
OXIDATION
PERFORMANCE TESTING
REACTOR COMPONENTS
REACTOR CORES
REACTORS
SUPPORTS
TENSILE PROPERTIES
TESTING