Finite-element blunt-crack propagation: a modified J-integral approach. [LMFBR]

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:6060727

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

In assessing the safety of a liquid metal fast breeder reactor (LMFBR), a major concern is the behavior of concrete structures subjected to high temperatures. The potential of concrete cracking is an important parameter which could significantly influence the safety assessment of thermally attacked concrete. A new modified J-integral approach for the blunt crack model has been derived to provide a general procedure to accurately predict the direction of crack growth. This formulation has been incorporated into the coupled heat transfer-stress analysis finite element code TEMP-STRESS. A description of the formulation is presented in this paper. Results for the problems of a Mode I and mixed mode crack in a plate using regular and slanted meshes subjected to uniaxial and shear loading are presented.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 6060727
• Report Number(s): CONF-830805-24; ON: DE83010579
• Resource Relation: Conference: 7. international conference on structural mechanics in reactor technology, Chicago, IL, USA, 22 Aug 1983
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
CONCRETES
FRACTURE PROPERTIES
CONTAINMENT BUILDINGS
THERMAL STRESSES
LMFBR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR MATERIALS
COMPUTER CALCULATIONS
CRACKS
FINITE ELEMENT METHOD
REACTOR SAFETY
ACCIDENTS
BREEDER REACTORS
BUILDING MATERIALS
CONTAINMENT
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
MATERIALS
MECHANICAL PROPERTIES
NUMERICAL SOLUTION
REACTORS
SAFETY
STRESSES
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
360603 - Materials- Properties