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Volumn 373, Issue , 1998, Pages 489-495

Elastic-plastic analysis of off-center cracks in cylindrical structures

Author keywords

[No Author keywords available]

Indexed keywords

BENDING (DEFORMATION); COMPUTER SIMULATION; CRACKS; CYLINDERS (SHAPES); ELASTICITY; FINITE ELEMENT METHOD; PLASTIC DEFORMATION;

EID: 3342933047     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Article
Times cited : (4)

References (37)
  • 1
    • 3342899769 scopus 로고
    • Report to the U.S. Nuclear Regulatory Commission Piping Review Committee
    • prepared by Pipe Break Task Group, U.S. Nuclear Regulatory Commission, Washington, D.C., November
    • USNRC, "Report to the U.S. Nuclear Regulatory Commission Piping Review Committee," prepared by Pipe Break Task Group, NUREG/CR-1061, Vol. 3, U.S. Nuclear Regulatory Commission, Washington, D.C., November 1984.
    • (1984) NUREG/CR-1061 , vol.3
  • 2
    • 0041573877 scopus 로고
    • Standard Review Plan, Section 3.6.3 Leak-Before-Break Evaluation Procedures
    • Notices, August
    • Federal Register, "Standard Review Plan, Section 3.6.3 Leak-Before-Break Evaluation Procedures," Public comment paper, Vol. 52, No. 167, Notices, pp. 32626-32633, August 1987.
    • (1987) Public Comment Paper , vol.52 , Issue.167 , pp. 32626-32633
  • 4
    • 0003533459 scopus 로고
    • Refinement and Evaluation of Crack-Opening-Area Analyses for Circumferential Through-Wall Cracks in Pipes
    • U.S. Nuclear Regulatory Commission, Washington, D.C., April
    • Rahman, S., Brust, F., Ghadiali, N., Choi, Y. H., Krishnaswamy, P., Moberg, F., and Brickstad, and Wilkowski, G., "Refinement and Evaluation of Crack-Opening-Area Analyses for Circumferential Through-Wall Cracks in Pipes," NUREG/CR-6300, U.S. Nuclear Regulatory Commission, Washington, D.C., April 1995.
    • (1995) NUREG/CR-6300
    • Rahman, S.1    Brust, F.2    Ghadiali, N.3    Choi, Y.H.4    Krishnaswamy, P.5    Moberg, F.6    Brickstad7    Wilkowski, G.8
  • 5
    • 0029425515 scopus 로고
    • Effects of Off-Centered Crack and Restraint of Induced Bending on the Crack-Opening-Area Analysis of Pipes
    • Honolulu, Hawaii, Fatigue and Fracture Mechanics in Pressure Vessels and Piping, Edited by H. Mehta, July
    • Rahman, S., Ghadiali, N., Wilkowski, G., and Bonora, N., "Effects of Off-Centered Crack and Restraint of Induced Bending on the Crack-Opening-Area Analysis of Pipes," Proceedings of 1995 ASME/JSME Pressure Vessels and Piping Conference, Honolulu, Hawaii, Fatigue and Fracture Mechanics in Pressure Vessels and Piping, Edited by H. Mehta, PVP-Vol. 304, July 1995, pp. 149-162.
    • (1995) Proceedings of 1995 ASME/JSME Pressure Vessels and Piping Conference , vol.304 PVP-VOL. , pp. 149-162
    • Rahman, S.1    Ghadiali, N.2    Wilkowski, G.3    Bonora, N.4
  • 6
    • 0009687044 scopus 로고    scopus 로고
    • Effects of Off-Centered Crack and Restraint of Induced Bending Due to Pressure on the Crack-Opening-Area Analysis of Pipes
    • Rahman, S., Ghadiali, N., Wilkowski, G., and Bonora, N., "Effects of Off-Centered Crack and Restraint of Induced Bending Due to Pressure on the Crack-Opening-Area Analysis of Pipes" Nuclear Engineering and Design, Vol. 167, pp. 55-67, 1997.
    • (1997) Nuclear Engineering and Design , vol.167 , pp. 55-67
    • Rahman, S.1    Ghadiali, N.2    Wilkowski, G.3    Bonora, N.4
  • 7
    • 3342913583 scopus 로고
    • Short Cracks in Piping and Piping Program
    • U.S. Nuclear Regulatory Commission, Washington, D.C.
    • Wilkowski, G. M., and others, "Short Cracks in Piping and Piping Program," NUREG/CR-4599, Vois. 1 to 3, Nos. 1 and 2, U.S. Nuclear Regulatory Commission, Washington, D.C., 1991-1994.
    • (1991) NUREG/CR-4599 , vol.1-3 , Issue.1-2
    • Wilkowski, G.M.1
  • 9
    • 0242639431 scopus 로고    scopus 로고
    • Deterministic and Probabilistic Evaluations for Uncertainty in Pipe Fracture Parameters in Leak-Before-Break and In-Service Flaw Evaluations
    • U. S. Nuclear Regulatory Commission, Washington, DC, June
    • Ghadiali, N., Rahman, S., Choi, Y. H., and Wilkowski, G., "Deterministic and Probabilistic Evaluations for Uncertainty in Pipe Fracture Parameters in Leak-Before-Break and In-Service Flaw Evaluations," Topical Report, NUREG/CR-6443, U. S. Nuclear Regulatory Commission, Washington, DC, June 1996.
    • (1996) Topical Report, NUREG/CR-6443
    • Ghadiali, N.1    Rahman, S.2    Choi, Y.H.3    Wilkowski, G.4
  • 10
    • 0032056140 scopus 로고    scopus 로고
    • Crack-Opening-Area Analyses for Circumferential Through-Wall Cracks in Pipes - Part I: Analytical Models
    • accepted for publication (in press)
    • Rahman, S., Brust, F. W., Ghadiali, N., and Wilkowski., "Crack-Opening-Area Analyses for Circumferential Through-Wall Cracks in Pipes - Part I: Analytical Models," accepted for publication in the International Journal of Pressure Vessels and Piping, 1998 (in press).
    • (1998) International Journal of Pressure Vessels and Piping
    • Rahman, S.1    Brust, F.W.2    Ghadiali, N.3    Wilkowski4
  • 11
    • 0032056202 scopus 로고    scopus 로고
    • Crack-Opening-Area Analyses for Circumferential Through-Wall Cracks in Pipes - Part II: Model Validations
    • accepted for publication (in press)
    • Rahman, S., Brust, F. W., Ghadiali, N., and Wilkowski, G., "Crack-Opening-Area Analyses for Circumferential Through-Wall Cracks in Pipes - Part II: Model Validations," accepted for publication in the International Journal of Pressure Vessels and Piping, 1998 (in press).
    • (1998) International Journal of Pressure Vessels and Piping
    • Rahman, S.1    Brust, F.W.2    Ghadiali, N.3    Wilkowski, G.4
  • 12
    • 0032056054 scopus 로고    scopus 로고
    • Crack-Opening-Area Analyses for Circumferential Through-Wall Cracks in Pipes - Part III: Off-Center Cracks, Restraint of Bending, Thickness Transition, and Weld Residual Stresses
    • accepted for publication (in press)
    • Rahman, S., Brust, F. W., Ghadiali, N., and Wilkowski., "Crack-Opening-Area Analyses for Circumferential Through-Wall Cracks in Pipes - Part III: Off-Center Cracks, Restraint of Bending, Thickness Transition, and Weld Residual Stresses," accepted for publication in the International Journal of Pressure Vessels and Piping, 1998 (in press).
    • (1998) International Journal of Pressure Vessels and Piping
    • Rahman, S.1    Brust, F.W.2    Ghadiali, N.3    Wilkowski4
  • 13
    • 84980287971 scopus 로고
    • A Path Independent Integral and the Approximate Analysis of Strain Concentration by Notches and Cracks
    • Rice, J. R., "A Path Independent Integral and the Approximate Analysis of Strain Concentration by Notches and Cracks," Journal of Applied Mechanics, 35, pp. 379-386, 1968.
    • (1968) Journal of Applied Mechanics , vol.35 , pp. 379-386
    • Rice, J.R.1
  • 14
    • 0005014684 scopus 로고
    • Singular Behavior at the End of a Tensile Crack in a Hardening Material
    • Hutchinson, J. W., "Singular Behavior at the End of a Tensile Crack in a Hardening Material," Journal Mech. Phys. Solids, 16, pp. 13-31, 1968.
    • (1968) Journal Mech. Phys. Solids , vol.16 , pp. 13-31
    • Hutchinson, J.W.1
  • 15
    • 33746751566 scopus 로고
    • Plane Strain Deformations Near a Crack Tip in a Power-Law Hardening Material
    • Rice, J. R., and Rosengren, G. F., "Plane Strain Deformations Near a Crack Tip in a Power-Law Hardening Material," Journal Mech. Phys. Solids, 16, pp. 1-12, 1968.
    • (1968) Journal Mech. Phys. Solids , vol.16 , pp. 1-12
    • Rice, J.R.1    Rosengren, G.F.2
  • 16
    • 0021609296 scopus 로고
    • Incremental Path-Independent Integrals for Inelastic and Dynamic Fracture Mechanics
    • Atluri, S. N., Nishioka, T., and Nakagaki, M., "Incremental Path-Independent Integrals for Inelastic and Dynamic Fracture Mechanics," Engineering Fracture Mechanics, Vol. 20, No. 2, pp. 209-244, 1984.
    • (1984) Engineering Fracture Mechanics , vol.20 , Issue.2 , pp. 209-244
    • Atluri, S.N.1    Nishioka, T.2    Nakagaki, M.3
  • 18
    • 85170555247 scopus 로고
    • Elastic-Plastic Fracture Mechanics Evaluations of Stainless Steel Tungsten/Inert-Gas Welds
    • Edited by J. D. Landes, A. Saxena, and J. G. Merkle, American Society for Testing and Materials, Philadelphia, PA
    • Nakagaki, M., Marschall, C., and F. W. Brust, "Elastic-Plastic Fracture Mechanics Evaluations of Stainless Steel Tungsten/Inert-Gas Welds," ASTM STP 995, Edited by J. D. Landes, A. Saxena, and J. G. Merkle, American Society for Testing and Materials, Philadelphia, PA, pp. 214-243, 1989.
    • (1989) ASTM STP 995 , pp. 214-243
    • Nakagaki, M.1    Marschall, C.2    Brust, F.W.3
  • 19
    • 0342754359 scopus 로고
    • Degraded Piping Program - Phase II
    • U.S. Nuclear Regulatory Commission, Washington, D.C.
    • Wilkowski, G. M. and others, "Degraded Piping Program - Phase II," Final and Semiannual Reports, NUREG/CR-4082, Vols. 1 to 8, U.S. Nuclear Regulatory Commission, Washington, D.C., 1985-1989.
    • (1985) Final and Semiannual Reports, NUREG/CR-4082 , vol.1-8
    • Wilkowski, G.M.1
  • 22
    • 3342896290 scopus 로고    scopus 로고
    • Summary of Results from the IPIRG-2 Round-Robin Analyses
    • U.S. Nuclear Regulatory Commission, Washington, D.C., February
    • Rahman, S., Olson, R., Rosenfield, A., and Wilkowski, G., "Summary of Results from the IPIRG-2 Round-Robin Analyses," NUREG/CR-6337, U.S. Nuclear Regulatory Commission, Washington, D.C., February 1996.
    • (1996) NUREG/CR-6337
    • Rahman, S.1    Olson, R.2    Rosenfield, A.3    Wilkowski, G.4
  • 23
    • 3342904940 scopus 로고
    • Fracture Behavior of Short Circumferentially Surface-Cracked Pipe
    • U. S. Nuclear Regulatory Commission, Washington, DC, November
    • Krishnaswamy, P., Scott, P., Choi, Y., Mohan, R., Rahman, S., Brust, F., and Wilkowski, G., "Fracture Behavior of Short Circumferentially Surface-Cracked Pipe," Topical Report, NUREG/CR-6298, U. S. Nuclear Regulatory Commission, Washington, DC, November 1995.
    • (1995) Topical Report, NUREG/CR-6298
    • Krishnaswamy, P.1    Scott, P.2    Choi, Y.3    Mohan, R.4    Rahman, S.5    Brust, F.6    Wilkowski, G.7
  • 24
    • 0040350543 scopus 로고
    • Fracture Evaluations of Fusion Line Cracks in Nuclear Pipe Bimetallic Welds
    • U. S. Nuclear Regulatory Commission, Washington, DC, April
    • Scott, P., Francini, R., Rahman, S., Rosenfield, A., and Wilkowski, G., "Fracture Evaluations of Fusion Line Cracks in Nuclear Pipe Bimetallic Welds," Topical Report, NUREG/CR-6297, U. S. Nuclear Regulatory Commission, Washington, DC, April 1995.
    • (1995) Topical Report, NUREG/CR-6297
    • Scott, P.1    Francini, R.2    Rahman, S.3    Rosenfield, A.4    Wilkowski, G.5
  • 25
    • 0026941533 scopus 로고
    • An Estimation Method for Evaluating Energy Release Rates of Circumferential Through-Wall Cracked Pipe Welds
    • Rahman, S. and Brust, F., "An Estimation Method for Evaluating Energy Release Rates of Circumferential Through-Wall Cracked Pipe Welds," Engineering Fracture Mechanics, Vol. 43, No. 3, pp. 417-430, 1992.
    • (1992) Engineering Fracture Mechanics , vol.43 , Issue.3 , pp. 417-430
    • Rahman, S.1    Brust, F.2
  • 26
    • 0026808071 scopus 로고
    • Elastic-Plastic Fracture of Circumferential Through-Wall Cracked Pipe Welds Subject to Bending
    • November
    • Rahman, S. and Brust, F., "Elastic-Plastic Fracture of Circumferential Through-Wall Cracked Pipe Welds Subject to Bending," Journal of Pressure Vessel Technology, Vol. 114, No. 4, pp. 410-416, November 1992.
    • (1992) Journal of Pressure Vessel Technology , vol.114 , Issue.4 , pp. 410-416
    • Rahman, S.1    Brust, F.2
  • 27
    • 30244572919 scopus 로고    scopus 로고
    • Fracture Analysis of Full-Scale Pipe Experiments on Stainless Steel Flux Welds
    • Rahman, S., Wilkowski, G., and Brust, F., "Fracture Analysis of Full-Scale Pipe Experiments on Stainless Steel Flux Welds," Nuclear Engineering and Design, Vol. 160, pp. 77-96, 1996.
    • (1996) Nuclear Engineering and Design , vol.160 , pp. 77-96
    • Rahman, S.1    Wilkowski, G.2    Brust, F.3
  • 28
    • 0022659760 scopus 로고
    • Energy Release Rate Along a Three-Dimensional Crack Front in a Thermally Stressed Body
    • Shih, C. F., Moran, B., and Nakamura, T., "Energy Release Rate Along a Three-Dimensional Crack Front in a Thermally Stressed Body," International Journal of Fracture, Vol. 30, pp. 79-102, 1986.
    • (1986) International Journal of Fracture , vol.30 , pp. 79-102
    • Shih, C.F.1    Moran, B.2    Nakamura, T.3
  • 29
    • 0023594596 scopus 로고
    • A General Treatment of Crack Tip Contour Integrals
    • Moran, B. and Shih, C. F., "A General Treatment of Crack Tip Contour Integrals," International Journal of Fracture, Vol. 35, pp. 295-310, 1987.
    • (1987) International Journal of Fracture , vol.35 , pp. 295-310
    • Moran, B.1    Shih, C.F.2
  • 34
    • 0003727617 scopus 로고
    • Elastic-Plastic Fracture Analysis of Through-Wall and Surface Flaws in Cylinders
    • Electric Power Research Institute, Palo Alto, CA, January
    • Kumar, V. and German, M., "Elastic-Plastic Fracture Analysis of Through-Wall and Surface Flaws in Cylinders," EPRI Topical Report, NP-5596, Electric Power Research Institute, Palo Alto, CA, January 1988.
    • (1988) EPRI Topical Report, NP-5596
    • Kumar, V.1    German, M.2


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