J-integral of circumferential crack in large diameter pipes

Conference · Tue Dec 01 00:00:00 EST 1992

OSTI ID:10108283

Ji, Wei; Chao, Yuh J; Sutton, M A ^[1]; Lam, P S; Mertz, G E ^[2]

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1. South Carolina Univ., Columbia, SC (United States). Dept. of Mechanical Engineering
2. Westinghouse Savannah River Co., Aiken, SC (United States)

Large diameter thin-walled pipes are encountered in low pressure nuclear power piping system. Fracture parameters such as K and J, associated with postulated cracks are needed to assess the safety of the structure, for example, prediction of the onset of tile crack growth and the stability of the crack. The Electric Power Research Institute (EPRI) has completed a comprehensive study of cracks in pipes and handbook-type data is available. However, for some large diameter, thin-walled pipes the needed information is not included in the handbook. This paper reports our study of circumferential cracks in large diameter, thin-walled pipes (R/t=30 to 40) under remote bending or tension loads. Elastic-Plastic analyses using finite element method were performed to determine the elastic and fully plastic J values for various pipe/crack geometries. A non-linear Ramberg-Osgood material model is used, with strain hardening exponents(n) ranging from 3 to 10. A number of circumferential, through thickness cracks were studied with half crack angles ranging from 0.063{pi} to 0.5{pi}. Results are tabulated for use with the EPRI estimation scheme.

• Research Organization: Westinghouse Savannah River Co., Aiken, SC (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 10108283
• Report Number(s): WSRC-MS-92-320; CONF-9203208-1; ON: DE93003708
• Resource Relation: Conference: 2. international conference on nuclear engineering,San Francisco, CA (United States),21-24 Mar 1992; Other Information: PBD: [1992]
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
PIPES
CRACKS
NUCLEAR POWER PLANTS
CRACK PROPAGATION
FRACTURES
SAFETY
STRESSES
FINITE ELEMENT METHOD
STRAINS
FRACTURE MECHANICS
CALCULATION METHODS
BENDING
MATERIALS TESTING
COMPUTER CALCULATIONS
MATHEMATICAL MODELS
220200
360103
COMPONENTS AND ACCESSORIES
MECHANICAL PROPERTIES