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ASTM Selected Technical Papers
Constraint Effects in Fracture
By
EM Hackett,
EM Hackett
1
U.S. Nuclear Regulatory Commission
, Washington, DC
; symposium chairman and co-editor
Search for other works by this author on:
K-H Schwalbe,
K-H Schwalbe
2;
GKSS Research Center
, Federal Republic of Germany
symposium co-chairman and co-editor
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RH Dodds, Jr Jr
RH Dodds, Jr Jr
3
University of Illinois
, Urbana, IL
; symposium co-chairman and co-editor
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ISBN-10:
0-8031-1481-8
ISBN:
978-0-8031-1481-4
No. of Pages:
514
Publisher:
ASTM International
Publication date:
1993
eBook Chapter
Specimen Size Effects on J-R Curves for RPV Steels
By
AL Hiser, Jr
AL Hiser, Jr
1
Materials engineer
, United States Nuclear Regulatory Commission
, Mail Stop 217C NL/S, Washington, DC 20555
.
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Page Count:
44
-
Published:1993
Citation
Hiser, A, Jr. "Specimen Size Effects on J-R Curves for RPV Steels." Constraint Effects in Fracture. Ed. Hackett, E, Schwalbe, K, & Dodds, R, Jr. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959 : ASTM International, 1993.
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This study examined the effect of specimen size on J-R curves for reactor pressure vessel (RPV) steels. Overall comparisons for monolithic materials (base plate and forging) indicated that no significant size effect is apparent, using standard formulations for the J-integral within commonly accepted validity bounds. However, materials that are composite in nature, such as weld materials, or exhibit macro-scale inhomogeneities gave significant differences in JR curve trends for different sizes of specimens.
References
1.
Rice
, J. R.
, “A Path Independent Integral and the Approximate Analysis of Strain Concentration by Notches and Cracks
,” Transactions of ASME, Journal of Applied Mechanics
, Vol. 35
, 06
1968
, pp. 379–386.2.
Merkle
, J. G.
and Corten
, H. T.
, “A J-integral Analysis for the Compact Specimen, Considering Axial Force as Well as Bending Effects
,” Transactions of ASME, Journal of Pressure Vessel Technology
, 11
1974
, pp. 286–292.3.
Ernst
, H. A.
and Paris
, P. C.
, “Techniques of Analysis of Load-Displacement Records by J-Integral Methods
,” NUREG/CR-1222, U.S. Nuclear Regulatory Commission
, Washington, DC., 01
1980
.4.
Ernst
, H. A.
, “Materials Resistance and Instability Beyond J-Controlled Crack Growth
,” Elastic-Plastic Fracture
, ASTM STP 803, Vol. I
, ASTM
, Philadelphia
, 1983
, pp. 191–213.5.
Hutchinson
, J. R.
and Paris
, P. C.
, “The Theory of Stability Analysis of J-Controlled Crack Growth
,” Elastic-Plastic Fracture
, ASTM STP 668, ASTM
, Philadelphia
, 03
1979
, pp. 37–64.6.
Shih
, C. F.
, “An Engineering Approach for Examining Crack Growth and Stability in Flawed Structures
,” Proceedings of CSNI Specialists Meeting in Plastic Tearing Instability
, NUREG/CP-0010, U.S. Nuclear Regulatory Commission
, Washington, DC.
, 01
1980
.7.
McCabe
, D. E.
and Landes
, J. D.
, “JR-Curve Testing of Large Compact Specimens
,” Elastic-Plastic Fracture
, ASTM STP 803, Vol. II
, ASTM
, Philadelphia, PA
, 1983
, pp. 353–371.8.
Shih
, C. F.
, deLorenzi
, H. G.
, and Andrews
, W. R.
, “Studies on Crack Initiation and Stable Crack Growth
,” Elastic-Plastic Fracture
, ASTM STP 668, ASTM
, Philadelphia
, 03
1979
, pp. 65–120.9.
Vassilaros
, M. G.
, Joyce
, J. A.
, and Gudas
, J. P.
, “Effects of Specimen Geometry on the JI-R Curve for ASTM A533B Steel
,” Fracture Mechanics: Twelfth Conference
, ASTM STP 700, ASTM
, Philadelphia
, 1980
, pp. 251–270.10.
Davis
, D. A.
, Vassilaros
, M. G.
, and Gudas
, J. P.
, “Specimen Geometry and Extended Crack Growth Effects on JI-R Curve Characteristics for HY-130 and ASTM A533B Steels
,” Elastic-Plastic Fracture
, ASTM STP 803, Vol. II
, ASTM
, Philadelphia
, 1983
, pp. 582–610.11.
Hiser
, A. L.
and Loss
, F. J.
, “Alternative Procedures for J-R Curve Determination
,” NUREG/CR-3402, U.S. Nuclear Regulatory Commission
, Washington, DC., 07
1983
.12.
Saxena
, A.
and Hudak
, S. J.
, Jr., “Review and Extension of Compliance Information for Common Crack Growth Specimens
,” International Journal of Fracture
, Vol. 14
, No. 5
, 10
1978
, pp. 453–468.13.
Rice
, J. R.
, Drugan
, W. J.
, and Sham
, T.-L.
, “Elastic-Plastic Analysis of Growing Cracks
,” Fracture Mechanics: Twelfth Conference
, ASTM STP 700, ASTM
, Philadelphia
, 1980
, pp. 189–221.14.
Ernst
, H.
, Paris
, P. C.
, Rossow
, M.
, and Hutchinson
, J. W.
, “Analysis of Load-Displacement Relationships to Determine J-R Curve and Tearing Instability Material Properties
,” Fracture Mechanics
, ASTM STP 677, ASTM
, Philadelphia
, 1979
, pp. 581–599.15.
Joyce
, J. A.
, Ernst
, H.
, and Paris
, P. C.
, “Direct Evaluation of J-Resistance Curves from Load Displacement Curves
,” Fracture Mechanics: Twelfth Conference
, ASTM STP 700, ASTM
, Philadelphia
, 1980
, pp. 222–236.16.
Hawthorne
, J. R.
, “Significance of Nickel and Copper Content to Radiation Sensitivity and Postirradiation Heat Treatment Recovery of Reactor Vessel Steels
,” NUREG/CR-2948, U.S. Nuclear Regulatory Commission
, Washington, DC., 11
1982
.17.
Childress
, C. E.
, “Fabrication and Mechanical Test Data for Acceptance of the First Six 6-Inch-Thick Intermediate Test Vessels of the Heavy-Section Steel Technology Program
,” ORNL/TM-4351, Oak Ridge National Laboratory
, Oak Ridge, TN, 10
1973
.18.
Derby
, R. W.
et al, “Test of 6-Inch-Thick Pressure Vessels, Series 1: Intermediate Test Vessels V-1 and V-2
,” ORNL-4895, Oak Ridge National Laboratory
, Oak Ridge, TN, 02
1974
.19.
Loss
, F. J.
, Ed., “Structural Integrity of Water Reactor Pressure Boundary Components, Annual Report for 1983
,” NUREG/CR-3228, Vol. 2
, U.S. Nuclear Regulatory Commission
, Washington, DC., 09
1984
.20.
Childress
, C. E.
, “Fabrication and Mechanical Test Data for the Four 6-Inch-Thick Intermediate Test Vessels Made from Steel Plate for the Heavy-Section Steel Technology Program
,” ORNL/TM-5074, Oak Ridge National Laboratory
, Oak Ridge, TN, 01
1976
.21.
Merkle
, J. G.
et al, “Test of 6-Inch-Thick Pressure Vessels. Series 3: Intermediate Test Vessel V-7
,” ORNL/NUREG-1, Oak Ridge National Laboratory
, Oak Ridge, TN, 08
1976
.22.
Hiser
, A. L.
and Terrell
, J. B.
, “Size Effects on J-R Curves for A 302-B Plate
,” NUREG/CR-5265, U.S. Nuclear Regulatory Commission
, Washington, DC., 01
1989
.23.
Loss
, F.J.
, Ed., “Structural Integrity of Water Reactor Pressure Boundary Components, Progress Report Ending 29 Feb 1976
,” NRL Report 8006, Naval Research Laboratory
, Washington, DC., 26
08
1976
.24.
Hiser
, A. L.
, Loss
, F. J.
, and Menke
, B. H.
, “J-R Curve Characterization of Irradiated Low Upper Shelf Welds
,” NUREG/CR-3506, U.S. Nuclear Regulatory Commission
, Washington, DC., 04
1984
.25.
Emburg
, J. D.
, Petch
, N. J.
, Wraith
, A. E.
, and Wright
, A. E.
, “The Fracture of Mild Steel Laminates
,” Transactions of the Metallurgical Society of AIME
, Vol. 239
, 01
1967
, pp. 114–118.26.
Miyoshi
, E.
, Fukuda
, M.
, Iwanaga
, H.
, and Okazawa
, T.
, “The Effect of Separation on the Propagating Shear Fracture
,” Paper 4, Crack Propagation in Pipelines
, The Institute of Gas Engineers
, 03
1974
.27.
Poynton
, W. A.
and Christian
, J. R.
, “An Experimental Study of Shear Fracture Propagation Using Small Scale Models
,” Paper 5, Crack Propagation in Pipelines
, The Institute of Gas Engineers
, 03
1974
.
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