-
1
-
-
0041573861
-
-
Hibbitt, Karlsson & Sorensen, Pawtucket, RI
-
ABAQUS, User's Guide and Theoretical Manual, Version 5.3, Hibbitt, Karlsson & Sorensen, Pawtucket, RI, 1993.
-
(1993)
User's Guide and Theoretical Manual, Version 5.3
-
-
-
2
-
-
84909830652
-
-
NUREG/CR-4853, US Nuclear Regulatory Commission, Washington, DC
-
F.W. Brust, Approximate methods for fracture analyses of through-wall cracked pipes, NUREG/CR-4853, US Nuclear Regulatory Commission, Washington, DC, 1987.
-
(1987)
Approximate Methods for Fracture Analyses of Through-wall Cracked Pipes
-
-
Brust, F.W.1
-
3
-
-
0026479610
-
Elastic-plastic analysis of small cracks in tubes
-
Calgary, Alberta, June
-
F. Brust, S. Rahman and N. Ghadiali, Elastic-plastic analysis of small cracks in tubes, Proc. 11th Int. Conf. on Offshore Mechanics and Arctic Engineering, Calgary, Alberta, June 1992.
-
(1992)
Proc. 11th Int. Conf. on Offshore Mechanics and Arctic Engineering
-
-
Brust, F.1
Rahman, S.2
Ghadiali, N.3
-
4
-
-
0041573877
-
Public comment paper on 'Standard review plan, section 3.6.3 leak-before-break evaluation procedures'
-
Federal Register, Public Comment Paper on 'Standard review plan, Section 3.6.3 leak-before-break evaluation procedures', Federal Register 52(167) (1987) 32626-32633.
-
(1987)
Federal Register
, vol.52
, Issue.167
, pp. 32626-32633
-
-
-
5
-
-
0003734449
-
-
NUREG/CR-4572, US Nuclear Regulatory Commission, Washington DC
-
R. Klecker, F. Brust and G. Wilkowski, NRC leak-before-break (LBB.NRC) analysis method for circumferentially through-wall-cracked pipes under axial plus bending loads, NUREG/CR-4572, US Nuclear Regulatory Commission, Washington DC, 1986.
-
(1986)
NRC Leak-before-break (LBB.NRC) Analysis Method for Circumferentially Through-wall-cracked Pipes under Axial Plus Bending Loads
-
-
Klecker, R.1
Brust, F.2
Wilkowski, G.3
-
6
-
-
85040265963
-
An engineering approach for elastic-plastic fracture analysis
-
Electric Power Research Institute, Palo Alto, CA
-
V. Kumar, M. German and C. Shin, An engineering approach for elastic-plastic fracture analysis, EPRI Rep. NP-1931, Electric Power Research Institute, Palo Alto, CA, 1981.
-
(1981)
EPRI Rep. NP-1931
-
-
Kumar, V.1
German, M.2
Shin, C.3
-
7
-
-
0003727613
-
Advances in elastic-plastic fracture analysis
-
Electric Power Research Institute, Palo Alto, CA
-
V. Kumar, M. German, W. Wilkening, W. Andrews, H. deLorenzi and D. Mowbray, Advances in elastic-plastic fracture analysis, EPRI Final Rep. NP-3607, Electric Power Research Institute, Palo Alto, CA, 1984.
-
(1984)
EPRI Final Rep. NP-3607
-
-
Kumar, V.1
German, M.2
Wilkening, W.3
Andrews, W.4
DeLorenzi, H.5
Mowbray, D.6
-
8
-
-
0004117641
-
PICEP: Pipe crack evaluation program
-
Electric Power Research Institute, Palo Alto, CA
-
D. Norris et al., PICEP: pipe crack evaluation program, EPRI Rep. NP-3596-SR, Electric Power Research Institute, Palo Alto, CA, 1984.
-
(1984)
EPRI Rep. NP-3596-SR
-
-
Norris, D.1
-
9
-
-
0003827973
-
-
NUREG/CR-3464, US Nuclear Regulatory Commission, Washington, DC
-
P.C. Paris and H. Tada, The application of fracture proof design methods using tearing instability theory to nuclear piping postulating circumferential through-wall cracks, NUREG/CR-3464, US Nuclear Regulatory Commission, Washington, DC, 1983.
-
(1983)
The Application of Fracture Proof Design Methods Using Tearing Instability Theory to Nuclear Piping Postulating Circumferential Through-wall Cracks
-
-
Paris, P.C.1
Tada, H.2
-
10
-
-
0003730669
-
-
NUREG/CR-5128, Rev. 1, US Nuclear Regulatory Commission, Washington, DC
-
D. Paul, J. Ahmad, P.M. Scott, L.F. Flanigan and G. Wilkowski, Evaluation and Refinement of leak-rate estimation models, NUREG/CR-5128, Rev. 1, US Nuclear Regulatory Commission, Washington, DC, 1994.
-
(1994)
Evaluation and Refinement of Leak-rate Estimation Models
-
-
Paul, D.1
Ahmad, J.2
Scott, P.M.3
Flanigan, L.F.4
Wilkowski, G.5
-
11
-
-
0026941533
-
An estimation method for evaluating energy release rates of circumferential through-wall cracked pipe welds
-
S. Rahman and F. Brust, An estimation method for evaluating energy release rates of circumferential through-wall cracked pipe welds, Eng. Fract. Mech. 43(3) (1992a) 417-430.
-
(1992)
Eng. Fract. Mech.
, vol.43
, Issue.3
, pp. 417-430
-
-
Rahman, S.1
Brust, F.2
-
12
-
-
0026808071
-
Elastic-plastic fracture of circumferential through-wall cracked pipe welds subject to bending
-
S. Rahman and F. Brust, Elastic-plastic fracture of circumferential through-wall cracked pipe welds subject to bending, J. Pressure Vessel Technol. 114(4) (1992b) 410-416.
-
(1992)
J. Pressure Vessel Technol.
, vol.114
, Issue.4
, pp. 410-416
-
-
Rahman, S.1
Brust, F.2
-
13
-
-
0003467028
-
Probabilistic pipe fracture evaluations for leak-rate-detection applications
-
US Nuclear Regulatory Commission, Washington, DC
-
S. Rahman, N. Ghadiali, D. Paul and G. Wilkowski, Probabilistic pipe fracture evaluations for leak-rate-detection applications, Topical Rep. NUREG/CR 6004, US Nuclear Regulatory Commission, Washington, DC, 1995.
-
(1995)
Topical Rep. NUREG/CR 6004
-
-
Rahman, S.1
Ghadiali, N.2
Paul, D.3
Wilkowski, G.4
-
14
-
-
0001268316
-
The International Piping Integrity Research Group (IPIRG) program: An overview
-
H. Shibata (ed.), August paper G23/1
-
R.A. Schmidt, G.M. Wilkowski and M.E. Mayfield, The International Piping Integrity Research Group (IPIRG) Program: An overview, in H. Shibata (ed.), Trans. 11th Int. Conf. on Structural Mechanics in Reactor Technology, Vol. G2: Fracture Mechanics and Non-Destructive Evaluation - 2, August 1991, paper G23/1, pp. 177-188.
-
(1991)
Trans. 11th Int. Conf. on Structural Mechanics in Reactor Technology, Vol. G2: Fracture Mechanics and Non-destructive Evaluation - 2
, vol.G2
, pp. 177-188
-
-
Schmidt, R.A.1
Wilkowski, G.M.2
Mayfield, M.E.3
-
15
-
-
0042576080
-
-
prepared by the Pipe Break Task Group, NUREG/CR-1061, US Nuclear Regulatory Commission, Washington, DC
-
US NRC, Report to the US Nuclear Regulatory Commission Piping Review Committee, prepared by the Pipe Break Task Group, NUREG/CR-1061, Vol. 3, US Nuclear Regulatory Commission, Washington, DC, 1984.
-
(1984)
Report to the US Nuclear Regulatory Commission Piping Review Committee
, vol.3
-
-
-
16
-
-
0342754359
-
Degraded piping program - Phase II
-
October 1984-March 1985, NUREG/ CR-4082, US Nuclear Regulatory Commission, Washington, DC
-
G.M. Wilkowski et al., Degraded piping program - Phase II, Semiannual Report, October 1984-March 1985, NUREG/ CR-4082, Vol. 2, US Nuclear Regulatory Commission, Washington, DC, 1985.
-
(1985)
Semiannual Report
, vol.2
-
-
Wilkowski, G.M.1
-
17
-
-
0042075061
-
-
March 1984-January 1989, NUREG/CR-4082, US Nuclear Regulatory Commission, Washington, DC
-
G.M. Wilkowski et al., Degraded piping program - Phase II: summary of technical results and their significance to leak-before-break and in-service flaw acceptance criteria, March 1984-January 1989, NUREG/CR-4082, Vol. 8, US Nuclear Regulatory Commission, Washington, DC, 1989.
-
(1989)
Degraded Piping Program - Phase II: Summary of Technical Results and Their Significance to Leak-before-break and In-service Flaw Acceptance Criteria
, vol.8
-
-
Wilkowski, G.M.1
-
18
-
-
3342913583
-
Short cracks in piping and piping welds
-
2, NUREG/CR-4599, US Nuclear Regulatory Commission, Washington, DC
-
G.M. Wilkowski, F. Brust, R. Francini, N. Ghadiali, T. Kilinski, P. Krishnaswamy, M. Landow, C.W. Marschall, S. Rahman and P. Scott, Short cracks in piping and piping welds, Semi-annual Reports, Vois. 1, 2, 3, nos. 1 and 2, NUREG/CR-4599, US Nuclear Regulatory Commission, Washington, DC, 1990-1992.
-
(1990)
Semi-annual Reports
, vol.1-3
, Issue.1-2
-
-
Wilkowski, G.M.1
Brust, F.2
Francini, R.3
Ghadiali, N.4
Kilinski, T.5
Krishnaswamy, P.6
Landow, M.7
Marschall, C.W.8
Rahman, S.9
Scott, P.10
-
19
-
-
0027309704
-
Pipe fracture evaluations for leak-rate detection: Deterministic models
-
Denver, CO PVP. 266, Creep, Fatigue Evaluation, and Leak-Before-Break Assessment
-
G. Wilkowski, S. Rahman, D. Paul and N. Ghadiali, Pipe fracture evaluations for leak-rate detection: deterministic models, Proc. 1993 ASME Pressure Vessels and Piping Conf., Denver, CO PVP. 266, Creep, Fatigue Evaluation, and Leak-Before-Break Assessment, pp. 243-254, 1993.
-
(1993)
Proc. 1993 ASME Pressure Vessels and Piping Conf.
, pp. 243-254
-
-
Wilkowski, G.1
Rahman, S.2
Paul, D.3
Ghadiali, N.4
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