Blunt indentation of core graphite
Description
Blunt indentation experiments were carried out on unoxidized and thermally oxidised IM1-24 graphite as a model to simulate local point stresses acting on graphite moderator bricks. Blunt indentation of unoxidized graphite initiates cracks close to the region of maximum tensile stress at the edge of the indentation. Cracks propagate and converge to form a cone of material. Failure is catastrophic, typically forming three pieces of graphite and ejecting the cone referred to above. The failure mode under indentation loading for highly oxidised graphite (weigh loss > 40%) is different from that for the unoxidized graphite. There is no longer a distinct crack path, the indentation is much deeper than in the case of the unoxidized graphite, and there is a region of crushed debris beneath the indentation, producing a crater-like structure. The reduction in the compressive fracture stress, σcf, under indentation loading with increasing fractional weight loss on oxidation, x, can be fitted to σcf/σ0 = exp-[5.2x] where σ0 is the compressive fracture stress of the unoxidized graphite. This indicates that the effect of thermal oxidation on indentation fracture stress is more severe than the effects of radiolytic oxidation on conventional strengths of nuclear graphites. (author). 8 refs, 12 figs
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28008820.pdf
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Additional details
Publishing Information
- Imprint Title
- Graphite moderator lifecycle behaviour. Proceedings of a specialists meeting
- Imprint Pagination
- 367 p.
- Journal Page Range
- p. 263-273.
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--901
Conference
- Title
- Specialists meeting on graphite moderator lifecycle behaviour.
- Dates
- 24-27 Sep 1995.
- Place
- Bath (United Kingdom).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 28008820
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGR TYPE REACTORS; BRICKS; CRACKS; FAILURES; GRAPHITE; OXIDATION; SIMULATION; STRESSES
- Descriptors DEC
- BUILDING MATERIALS; CARBON; CHEMICAL REACTIONS; ELEMENTS; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MATERIALS; NONMETALS; REACTORS