-
1
-
-
5844362569
-
A User's Guide to the NRC's Piping Fracture Mechanics Database (PIFRAC)
-
U.S. Nuclear Regulatory Commission, Washington, D.C.
-
A. L. Hiser and G. M. Callahan, "A User's Guide to the NRC's Piping Fracture Mechanics Database (PIFRAC)," NUREG/CR-4894, U.S. Nuclear Regulatory Commission, Washington, D.C., 1987.
-
(1987)
NUREG/CR-4894
-
-
Hiser, A.L.1
Callahan, G.M.2
-
2
-
-
0342754359
-
Degraded Piping Program - Phase II
-
NUREG/CR-4082, U.S. Nuclear Regulatory Commission, Washington, D.C.
-
Wilkowski, G. M., et al. "Degraded Piping Program - Phase II," Semiannual Reports from March 1984 to January 1985, NUREG/CR-4082, Vols. 1-8, U.S. Nuclear Regulatory Commission, Washington, D.C., 1985-1989.
-
(1985)
Semiannual Reports from March 1984 to January 1985
, vol.1-8
-
-
Wilkowski, G.M.1
-
3
-
-
0001268316
-
The International Piping Integrity Research Group (IPIRG) Program - An Overview
-
Tokyo, Japan, August
-
R. A. Schmidt, G. M. Wilkowski, and M. E. Mayfield, "The International Piping Integrity Research Group (IPIRG) Program - An Overview," Transactions of the 11th International Conference on Structural Mechanics in Reactor Technology, Vol. G2: Fracture Mechanics and Non-Destructive Evaluation - 2, pp. 177-188, Tokyo, Japan, August 1991.
-
(1991)
Transactions of the 11th International Conference on Structural Mechanics in Reactor Technology, Vol. G2: Fracture Mechanics and Non-Destructive Evaluation - 2
, pp. 177-188
-
-
Schmidt, R.A.1
Wilkowski, G.M.2
Mayfield, M.E.3
-
4
-
-
0342715517
-
Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems
-
NUREG/CR-4744, U.S. Nuclear Regulatory Commission, Washington, D.C., May
-
Chopra, O., "Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems", Semiannual Report, NUREG/CR-4744, Vol. 7, No. 1, U.S. Nuclear Regulatory Commission, Washington, D.C., May 1993.
-
(1993)
Semiannual Report
, vol.7
, Issue.1
-
-
Chopra, O.1
-
5
-
-
0342693944
-
Elastic-Plastic Methodology to Establish R Curves and Instability Criteria
-
July 1, 1983 to December 31, 1983 by Westinghouse R&D Center, July 24
-
Landes, J. D., McCabe, D. E., and Ernst, H. A., "Elastic-Plastic Methodology to Establish R Curves and Instability Criteria", Semiannual Report on EPRI Contract No. RP1238-2, July 1, 1983 to December 31, 1983 by Westinghouse R&D Center, July 24, 1984.
-
(1984)
Semiannual Report on EPRI Contract No. RP1238-2
-
-
Landes, J.D.1
McCabe, D.E.2
Ernst, H.A.3
-
6
-
-
0042565524
-
Toughness of Ferritic Piping Steels
-
EPRI NP-6264, Electric Power Research Institute, Palo Alto, California, October
-
Van Der Sluys, W. A., "Toughness of Ferritic Piping Steels," Final Report, EPRI NP-6264, Electric Power Research Institute, Palo Alto, California, October 1988.
-
(1988)
Final Report
-
-
Van Der Sluys, W.A.1
-
7
-
-
84980287971
-
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, Vol. 35, pp. 376-386, 1968.
-
(1968)
Journal of Applied Mechanics
, vol.35
, pp. 376-386
-
-
Rice, J.R.1
-
8
-
-
0013532552
-
Fundamentals of the Phenomenological Theory of Nonlinear Fracture Mechanics
-
Hutchinson, J. W., "Fundamentals of the Phenomenological Theory of Nonlinear Fracture Mechanics," Journal of Applied Mechanics, Vol. 49, pp. 103-107, 1982.
-
(1982)
Journal of Applied Mechanics
, vol.49
, pp. 103-107
-
-
Hutchinson, J.W.1
-
9
-
-
0003727617
-
Elastic-Plastic Fracture Analysis of Through-Wall and Surface Flaws in Cylinders
-
Electric Power Research Institute, Palo Alto, California, January
-
Kumar, V. and German, M. D., "Elastic-Plastic Fracture Analysis of Through-Wall and Surface Flaws in Cylinders," EPRI NP-5596, Electric Power Research Institute, Palo Alto, California, January 1988.
-
(1988)
EPRI NP-5596
-
-
Kumar, V.1
German, M.D.2
-
10
-
-
3342904940
-
Fracture Behavior of Short Circumferentially Surface-Cracked Pipe
-
U.S. Nuclear Regulatory Commission, Washington, D.C., November
-
Krishnaswamy, P. K., and others, "Fracture Behavior of Short Circumferentially Surface-Cracked Pipe," NUREG/CR-6298, U.S. Nuclear Regulatory Commission, Washington, D.C., November 1995.
-
(1995)
NUREG/CR-6298
-
-
Krishnaswamy, P.K.1
-
11
-
-
0022754496
-
Evaluation of Flaws in Austenitic Steel Piping
-
Technical basis document for ASME IWB-3640 analysis procedure, prepared by Section XI Task Group for Piping Flaw Evaluation, Electric Power Research Institute, Palo Alto, California, April
-
"Evaluation of Flaws in Austenitic Steel Piping," Technical basis document for ASME IWB-3640 analysis procedure, prepared by Section XI Task Group for Piping Flaw Evaluation, EPRI Report NP-4690-SR, Electric Power Research Institute, Palo Alto, California, April 1986.
-
(1986)
EPRI Report NP-4690-SR
-
-
-
12
-
-
5844362794
-
Mechanical Fracture Predictions for Sensitized Stainless Steel Piping with Circumferential Cracks
-
EPRI NP-192, Electric Power Research Institute, Palo Alto, California, September
-
Kanninen, M. F. and others, "Mechanical Fracture Predictions for Sensitized Stainless Steel Piping with Circumferential Cracks," Final Report, EPRI NP-192, Electric Power Research Institute, Palo Alto, California, September 1976.
-
(1976)
Final Report
-
-
Kanninen, M.F.1
-
13
-
-
0023962529
-
Estimation of the Ductile Unstable Fracture of Pipe with a Circumferential Surface Crack Subjected to Bending
-
Kurihara, R., Ueda, S., and Sturm, D., "Estimation of the Ductile Unstable Fracture of Pipe with a Circumferential Surface Crack Subjected to Bending," Nuclear Engineering and Design, Vol. 106, pp. 265-273, 1988.
-
(1988)
Nuclear Engineering and Design
, vol.106
, pp. 265-273
-
-
Kurihara, R.1
Ueda, S.2
Sturm, D.3
-
14
-
-
84909830652
-
Approximate Methods for Fracture Analyses of Through-Wall Cracked Pipes
-
U.S. Nuclear Regulatory Commission, Washington, D.C., February
-
Brust, F. W., "Approximate Methods for Fracture Analyses of Through-Wall Cracked Pipes," NUREG/CR-4853, U.S. Nuclear Regulatory Commission, Washington, D.C., February 1987.
-
(1987)
NUREG/CR-4853
-
-
Brust, F.W.1
-
15
-
-
0004654179
-
Assessment of Short Through-Wall Cracks in Pipes - Experiments and Analyses
-
NUREG/CR-6226, U.S. Nuclear Regulatory Commission, Washington, D.C., April
-
Brust, F., and others, "Assessment of Short Through-Wall Cracks in Pipes - Experiments and Analyses," Topical Report, NUREG/CR-6226, U.S. Nuclear Regulatory Commission, Washington, D.C., April 1995.
-
(1995)
Topical Report
-
-
Brust, F.1
-
16
-
-
0026808071
-
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
-
17
-
-
0026941533
-
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
-
18
-
-
0002603052
-
An Approximate Method for Estimating Energy Release Rates of Through-Wall Cracked Pipe Weldments
-
ASME Special Publication, Edited by Bamford, Meyer, Wilkowski, Rybicki, Newaz, and Prager, June
-
Rahman, S., Brust, F. W., Nakagaki, M., and Gilles, P., "An Approximate Method for Estimating Energy Release Rates of Through-Wall Cracked Pipe Weldments," Fatigue, Fracture, and Risk - 1991, ASME Special Publication, Edited by Bamford, Meyer, Wilkowski, Rybicki, Newaz, and Prager, Vol. 215, June 1991.
-
(1991)
Fatigue, Fracture, and Risk - 1991
, vol.215
-
-
Rahman, S.1
Brust, F.W.2
Nakagaki, M.3
Gilles, P.4
-
19
-
-
0028557825
-
Analysis of Full-Scale Pipe Fracture Experiments on Stainless Steel Flux Welds
-
ASME Special Publication, Edited by G. Wilkowski, June
-
Rahman, S., Wilkowski, G., and Brust, F., "Analysis of Full-Scale Pipe Fracture Experiments on Stainless Steel Flux Welds," Fatigue, Flaw Evaluation, and Leak-Before-Break Assessments - 1994, ASME Special Publication, Edited by G. Wilkowski, PVP-Vol. 280, June 1994 (also to be published in Nuclear Engineering and Design).
-
(1994)
Fatigue, Flaw Evaluation, and Leak-Before-Break Assessments - 1994
, vol.280 PVP
-
-
Rahman, S.1
Wilkowski, G.2
Brust, F.3
-
20
-
-
0028557825
-
-
also to be published
-
Rahman, S., Wilkowski, G., and Brust, F., "Analysis of Full-Scale Pipe Fracture Experiments on Stainless Steel Flux Welds," Fatigue, Flaw Evaluation, and Leak-Before-Break Assessments - 1994, ASME Special Publication, Edited by G. Wilkowski, PVP-Vol. 280, June 1994 (also to be published in Nuclear Engineering and Design).
-
Nuclear Engineering and Design
-
-
-
21
-
-
0042064742
-
-
Hibbitt, Karlsson, and Sorenson, Inc., Pawtucket, RI
-
"ABAQUS User's Guide and Manual," Versions 4.6, 4.7, and 5.0, Hibbitt, Karlsson, and Sorenson, Inc., Pawtucket, RI, 1993.
-
(1993)
"ABAQUS User's Guide and Manual," Versions 4.6, 4.7, and 5.0
-
-
-
22
-
-
0004161838
-
-
Cambridge University Press, New York, New York
-
Press, W. H., Flannery, B. P., Teukolsky, S. A., and Vetterling, W. T., Numerical Recipes, Cambridge University Press, New York, New York, 1990.
-
(1990)
Numerical Recipes
-
-
Press, W.H.1
Flannery, B.P.2
Teukolsky, S.A.3
Vetterling, W.T.4
-
23
-
-
0018503596
-
Quadratic Limit States in Structural Reliability
-
ASCE
-
Fiessler, B., Neumann, H. J., and Rackwitz, R., "Quadratic Limit States in Structural Reliability," Journal of Engineering Mechanics, ASCE, 105(EM4), pp. 661-676.
-
Journal of Engineering Mechanics
, vol.105
, Issue.EM4
, pp. 661-676
-
-
Fiessler, B.1
Neumann, H.J.2
Rackwitz, R.3
-
24
-
-
0003634937
-
-
Prentice-Hall, Inc., Englewood Cliffs, New Jersey
-
Madsen, H. O., Krenk, S., and Lind, N. C., Methods of Structural Safety, Prentice-Hall, Inc., Englewood Cliffs, New Jersey, 1986.
-
(1986)
Methods of Structural Safety
-
-
Madsen, H.O.1
Krenk, S.2
Lind, N.C.3
-
25
-
-
0022440711
-
An Efficient Sampling Method for Probability of Failure Calculation
-
October
-
Harbitz, A., "An Efficient Sampling Method for Probability of Failure Calculation," Structural Safety, Vol. 3, No. 1., pp. 109-115, October 1986.
-
(1986)
Structural Safety
, vol.3
, Issue.1
, pp. 109-115
-
-
Harbitz, A.1
-
26
-
-
0042565525
-
Reliability Analysis of Uncertain Dynamic Systems Using Importance Sampling
-
Mexico City, Mexico
-
Ibrahim, Y. and Rahman, S., "Reliability Analysis of Uncertain Dynamic Systems Using Importance Sampling," Proceedings of the Sixth International Conference on Applications of Statistics and Probability in Civil Engineering, Mexico City, Mexico, 1991.
-
(1991)
Proceedings of the Sixth International Conference on Applications of Statistics and Probability in Civil Engineering
-
-
Ibrahim, Y.1
Rahman, S.2
-
27
-
-
0024144502
-
Improvement of Second-Order Reliability Estimates by Importance Sampling
-
ASCE, December
-
Hohenbichler, M., "Improvement of Second-Order Reliability Estimates by Importance Sampling," Journal of Engineering Mechanics, ASCE, Vol. 114, No. 12, pp. 2195-2199, December 1988.
-
(1988)
Journal of Engineering Mechanics
, vol.114
, Issue.12
, pp. 2195-2199
-
-
Hohenbichler, M.1
-
29
-
-
0029373485
-
A Stochastic Model for Elastic-Plastic Fracture Analysis of Circumferential Through-Wall-Cracked Pipes Subject to Bending
-
September
-
Rahman, S., "A Stochastic Model for Elastic-Plastic Fracture Analysis of Circumferential Through-Wall-Cracked Pipes Subject to Bending," Engineering Fracture Mechanics, Vol. 52, No. 2, September 1995.
-
(1995)
Engineering Fracture Mechanics
, vol.52
, Issue.2
-
-
Rahman, S.1
-
30
-
-
0003467028
-
Probabilistic Pipe Fracture Evaluations for Leak-Rate-Detection Applications
-
NUREG/CR-6004, U.S. Nuclear Regulatory Commission, Washington, D.C., April
-
Rahman, S., Ghadiali, N., Paul, D., and Wilkowski, G., "Probabilistic Pipe Fracture Evaluations for Leak-Rate-Detection Applications," Topical Report, NUREG/CR-6004, U.S. Nuclear Regulatory Commission, Washington, D.C., April 1995.
-
(1995)
Topical Report
-
-
Rahman, S.1
Ghadiali, N.2
Paul, D.3
Wilkowski, G.4
-
31
-
-
0027206636
-
Pipe Fracture Evaluations for Leak-Rate Detection: Probabilistic Models
-
Creep, Fatigue Evaluation, and Leak-Before-Break Assessment, Denver, Colorado, July
-
Rahman, S., Wilkowski, G., and Ghadiali, N., "Pipe Fracture Evaluations for Leak-Rate Detection: Probabilistic Models," Proceedings of the ASME Pressure Vessels and Piping Division Conference, PVP-Vol. 266, Creep, Fatigue Evaluation, and Leak-Before-Break Assessment, Denver, Colorado, July 1993.
-
(1993)
Proceedings of the ASME Pressure Vessels and Piping Division Conference
, vol.266 PVP
-
-
Rahman, S.1
Wilkowski, G.2
Ghadiali, N.3
-
32
-
-
0027187940
-
Pipe Fracture Evaluations for Leak-Rate Detection: Applications to BWR and PWR Piping
-
Creep, Fatigue Evaluation, and Leak-Before-Break Assessment, Denver, Colorado, July
-
Rahman, S., Wilkowski, G., and Ghadiali, N., "Pipe Fracture Evaluations for Leak-Rate Detection: Applications to BWR and PWR Piping," Proceedings of the ASME Pressure Vessels and Piping Division Conference, PVP-Vol. 266, Creep, Fatigue Evaluation, and Leak-Before-Break Assessment, Denver, Colorado, July 1993.
-
(1993)
Proceedings of the ASME Pressure Vessels and Piping Division Conference
, vol.266 PVP
-
-
Rahman, S.1
Wilkowski, G.2
Ghadiali, N.3
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