Comparisons of inelastic J and J* evaluations for the blunt crack and the sharp crack models. [LMFBR]

Conference · Sun Jan 01 04:00:00 EST 1984

OSTI ID:6758855

Pan, Y C; Marchertas, A H; Kennedy, J M

Concrete cracking is an important consideration in assessing the safety of a liquid metal fast breeder reactor (LMFBR) plant under a hypothetical accident where molten metal may come into contact with concrete structures. At the present time, several options in modeling concrete cracking have been pursued in an ongoing research program at Argonne National Laboratory which encompasses many aspects of high temperature behavior of concrete. Main emphasis is currently given to the blunt crack model where the crack is assumed to be uniformly distributed throughout the area of an element, though the sharp crack model is still kept as an alternative option where the crack surface is treated as the boundary of the finite element mesh. Several crack propagation criteria have been considered. Among these is the development of the J-integral approach with the blunt crack model. Numerical results were compared with those of the sharp crack model and found to be in good agreement for the elastic problem of a mode I crack. In this paper, the J-integral approach is extended to the post yield regime. To examine the path independency, the J* integral option is added to the finite element code. Numerical results for the J and J* integral formulations are given for a three point bending specimen loaded beyond the yield point.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6758855
• Report Number(s): CONF-840833-6; ON: DE84011734
• Country of Publication: United States
• Language: English

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ACCIDENTS
ALKALI METALS
BREEDER REACTORS
BUILDING MATERIALS
BUILDINGS
CONCRETES
CONTAINERS
CONTAINMENT
CONTAINMENT BUILDINGS
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FAST REACTORS
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FLUID-STRUCTURE INTERACTIONS
FRACTURE PROPERTIES
LIQUID METAL COOLED REACTORS
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MATERIALS
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
METALS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTOR VESSELS
REACTORS
SAFETY
SODIUM
STRESSES
THERMAL STRESSES