-
2
-
-
0003600382
-
-
ACI 318-99. American Concrete Institute, Farmington Hills, MI
-
ACI 318-99, 1999. Building Code Requirements for Reinforced Concrete. American Concrete Institute, Farmington Hills, MI.
-
(1999)
Building Code Requirements for Reinforced Concrete
-
-
-
3
-
-
0032140704
-
Factors Controlling Cracking of Concrete Affected by Reinforcement Corrosion
-
RILEM, Cachan, France
-
Alonso, C., Andrade, C., Rodriguez, J., Diez, J.M., 1998. Factors Controlling Cracking of Concrete Affected by Reinforcement Corrosion, Materials and Structures, vol. 31, issue 211. RILEM, Cachan, France, pp. 435-441.
-
(1998)
Materials and Structures
, vol.31
, Issue.211
, pp. 435-441
-
-
Alonso, C.1
Andrade, C.2
Rodriguez, J.3
Diez, J.M.4
-
4
-
-
0033134524
-
Corrosion Influence on Bond Between Steel and Concrete
-
American Concrete Institute, Farmington Hills, MI
-
Amleh, I., Mirza, S., 1999. Corrosion Influence on Bond Between Steel and Concrete. American Concrete Institute, Farmington Hills, MI. ACI Struct. J. 96 (3), 415-423.
-
(1999)
ACI Struct. J.
, vol.96
, Issue.3
, pp. 415-423
-
-
Amleh, I.1
Mirza, S.2
-
5
-
-
0442304966
-
Finite Element Computer Code
-
ANSYS, Inc., Canonsburg, PA
-
ANSYS. Finite Element Computer Code, ANSYS Rev. 5.4. ANSYS, Inc., Canonsburg, PA.
-
ANSYS Rev. 5.4
-
-
-
6
-
-
0017680733
-
Shear Strength of Low-Rise Walls with Boundary Elements
-
American Concrete Institute
-
Barda, F., Hanson, J.M., Corley, W.G., 1977. Shear Strength of Low-Rise Walls with Boundary Elements, Reinforced Concrete Structures in Seismic Zones, ACI SP-53. American Concrete Institute.
-
(1977)
Reinforced Concrete Structures in Seismic Zones
, vol.ACI SP-53
-
-
Barda, F.1
Hanson, J.M.2
Corley, W.G.3
-
9
-
-
0032318526
-
Issues related to structural aging in probabilistic risk analysis of nuclear power plants
-
Ellingwood B.R. Issues related to structural aging in probabilistic risk analysis of nuclear power plants. Reliabil. Eng. Syst. Saf. 62(3):1998;171-183.
-
(1998)
Reliabil. Eng. Syst. Saf.
, vol.62
, Issue.3
, pp. 171-183
-
-
Ellingwood, B.R.1
-
10
-
-
0022131895
-
Probabilistic descriptions of resistance of safety-related structures in nuclear plants
-
Ellingwood B.R., Hwang H. Probabilistic descriptions of resistance of safety-related structures in nuclear plants. Nucl. Eng. Des. 88(2):1985;169-178.
-
(1985)
Nucl. Eng. Des.
, vol.88
, Issue.2
, pp. 169-178
-
-
Ellingwood, B.R.1
Hwang, H.2
-
11
-
-
0021425165
-
Seismic fragilities for nuclear power plant studies
-
Kennedy R.P., Ravindra M. Seismic fragilities for nuclear power plant studies. Nucl. Eng. Des. 79(1):1984;47-68.
-
(1984)
Nucl. Eng. Des.
, vol.79
, Issue.1
, pp. 47-68
-
-
Kennedy, R.P.1
Ravindra, M.2
-
12
-
-
0020746624
-
Statistical analysis of resistance of reinforced and prestressed concrete members
-
MacGregor J.G., Mirza S.A., Ellingwood B.R. Statistical analysis of resistance of reinforced and prestressed concrete members. J. Am. Concrete Inst. 80(3):1983;167-176.
-
(1983)
J. Am. Concrete Inst.
, vol.80
, Issue.3
, pp. 167-176
-
-
MacGregor, J.G.1
Mirza, S.A.2
Ellingwood, B.R.3
-
13
-
-
0033220755
-
Summary and conclusions of a program to address aging of nuclear power plant concrete structures
-
Naus D.J., Oland C.B., Ellingwood B.R., Hookham C.J., Graves H.L. Summary and conclusions of a program to address aging of nuclear power plant concrete structures. Nucl. Eng. Des. 194:1999;73-96.
-
(1999)
Nucl. Eng. Des.
, vol.194
, pp. 73-96
-
-
Naus, D.J.1
Oland, C.B.2
Ellingwood, B.R.3
Hookham, C.J.4
Graves, H.L.5
-
14
-
-
0006971137
-
An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis
-
July. U.S. Nuclear Regulatory Commission, Washington, DC
-
NRC Regulatory Guide 1.174, July 1998. An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis. U.S. Nuclear Regulatory Commission, Washington, DC.
-
(1998)
NRC Regulatory Guide 1.174
-
-
-
16
-
-
0343149887
-
-
NUREG-1407. U.S. Nuclear Regulatory Commission, Washington, DC
-
NUREG-1407, 1991. Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities, by Chen, J.T., Chokshi, N.C., Kenneally, R.M., Kelly, G.B., Beckner, W.D., McCracken, C.A., Murphy, J., Reiter, L., Jeng, D. U.S. Nuclear Regulatory Commission, Washington, DC.
-
(1991)
Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities
-
-
Chen, J.T.1
Chokshi, N.C.2
Kenneally, R.M.3
Kelly, G.B.4
Beckner, W.D.5
McCracken, C.A.6
Murphy, J.7
Reiter, L.8
Jeng, D.9
-
17
-
-
0043203308
-
-
NUREG-1522. U.S. Nuclear Regulatory Commission, Washington, DC
-
NUREG-1522, 1995. Assessment of Inservice Conditions of Safety-Related Nuclear Plant Structures, by Ashar, H., Bagchi, G. U.S. Nuclear Regulatory Commission, Washington, DC.
-
(1995)
Assessment of Inservice Conditions of Safety-Related Nuclear Plant Structures
-
-
Ashar, H.1
Bagchi, G.2
-
18
-
-
0040893118
-
-
NUREG/CR-3558
-
NUREG/CR-3558, 1985. Handbook of Nuclear Power Plant Seismic Fragilities, by Cover, L.E., Bohn, M.P., Campbell, D.A., Wesley, D.A.
-
(1985)
Handbook of Nuclear Power Plant Seismic Fragilities
-
-
Cover, L.E.1
Bohn, M.P.2
Campbell, D.A.3
Wesley, D.A.4
-
19
-
-
0039707142
-
-
NUREG/CR-4334, Lawrence Livermore National Laboratory
-
NUREG/CR-4334, 1985. An Approach to the Quantification of Seismic Margins in Nuclear Power Plants, by Budnitz, R.J., Amico, P.J., Cornell, C.A., Hall, W.J., Kennedy, R.P., Reed, J.W., Shinozuka, M. Lawrence Livermore National Laboratory.
-
(1985)
An Approach to the Quantification of Seismic Margins in Nuclear Power Plants
-
-
Budnitz, R.J.1
Amico, P.J.2
Cornell, C.A.3
Hall, W.J.4
Kennedy, R.P.5
Reed, J.W.6
Shinozuka, M.7
-
20
-
-
0442273498
-
-
NUREG/CR-6679, Brookhaven National Laboratory, Upton, NY
-
NUREG/CR-6679, 2000. Assessment of Age-Related Degradation of Structures and Passive Components for U.S. Nuclear Power Plants, by Braverman, J.I., Hofmayer, C.H., Morante, R.J., Shteyngart, S., Bezler, P. Brookhaven National Laboratory, Upton, NY.
-
(2000)
Assessment of Age-Related Degradation of Structures and Passive Components for U.S. Nuclear Power Plants
-
-
Braverman, J.I.1
Hofmayer, C.H.2
Morante, R.J.3
Shteyngart, S.4
Bezler, P.5
-
21
-
-
0010742008
-
-
NUREG/CR-6715, Brookhaven National Laboratory, Upton, NY
-
NUREG/CR-6715, 2001. Probability-Based Evaluation of Degraded Reinforced Concrete Components in Nuclear Power Plants, by Braverman, J.I., Miller, C.A., Ellingwood, B.R., Naus, D.J., Hofmayer, C.H., Shteyngart, S., Bezler, P. Brookhaven National Laboratory, Upton, NY.
-
(2001)
Probability-Based Evaluation of Degraded Reinforced Concrete Components in Nuclear Power Plants
-
-
Braverman, J.I.1
Miller, C.A.2
Ellingwood, B.R.3
Naus, D.J.4
Hofmayer, C.H.5
Shteyngart, S.6
Bezler, P.7
-
22
-
-
0032319332
-
Survey of seismic fragilities used in PRA studies of nuclear power plants
-
Park Y.J., Hofmayer C.H., Chokshi N.C. Survey of seismic fragilities used in PRA studies of nuclear power plants. Reliabil. Eng. Syst. Saf. 62(3):1998;185-195.
-
(1998)
Reliabil. Eng. Syst. Saf.
, vol.62
, Issue.3
, pp. 185-195
-
-
Park, Y.J.1
Hofmayer, C.H.2
Chokshi, N.C.3
-
24
-
-
0442304961
-
-
Sakai, K., Banthia, N., Gjorv, O.E. (Eds.), An Experimental Study on Deterioration of Aseismic Behavior of R/C Structural Walls Damaged by Electrolytic Corrosion Testing Method. E & FN Spon, London, UK
-
Yamakawa, T., 1995. In: Sakai, K., Banthia, N., Gjorv, O.E. (Eds.), An Experimental Study on Deterioration of Aseismic Behavior of R/C Structural Walls Damaged by Electrolytic Corrosion Testing Method, Concrete Under Severe Conditions: Environment and Loading, vol. 2. E & FN Spon, London, UK.
-
(1995)
Concrete Under Severe Conditions: Environment and Loading
, vol.2
-
-
Yamakawa, T.1
|