-
1
-
-
0043203308
-
-
US Nuclear Regulatory Commission, Washington, D.C., July
-
Ashar, H., Bagchi, G., 1995. NUREG-1522, assessment of inservice conditions of safety-related nuclear plant structures. US Nuclear Regulatory Commission, Washington, D.C., July.
-
(1995)
NUREG-1522, Assessment of Inservice Conditions of Safety-related Nuclear Plant Structures
-
-
Ashar, H.1
Bagchi, G.2
-
4
-
-
0042200995
-
-
US Nuclear Regulatory Commission, Washington, D.C., June
-
Chen, J.T., Chokshi, N.C., Kenneally, R.M., Kelly, G.B., Beckner, W.D., McCraken, C., Murphy, A.J., Reiter, L., Jeng, D., 1991. NUREG-1407, procedural and submittal guidance for the IPEEE for severe accident vulnerabilities. US Nuclear Regulatory Commission, Washington, D.C., June.
-
(1991)
NUREG-1407, Procedural and Submittal Guidance for the 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
McCraken, C.6
Murphy, A.J.7
Reiter, L.8
Jeng, D.9
-
5
-
-
0030397326
-
Analysis of containment structures with corrosion damage
-
Sandia National Laboratories, 17-22 November, Atlanta Hilton and Towers, Atlanta, GA
-
Cherry, J.L., 1996. Analysis of containment structures with corrosion damage. Sandia National Laboratories, presented at the ASME 1996 Int. Mech. Eng. Congr. and Exposition, Symp. on Development, Validation, and Application of Inelastic Methods for Structural Analysis and Design, 17-22 November, Atlanta Hilton and Towers, Atlanta, GA.
-
(1996)
ASME 1996 Int. Mech. Eng. Congr. and Exposition, Symp. on Development, Validation, and Application of Inelastic Methods for Structural Analysis and Design
-
-
Cherry, J.L.1
-
6
-
-
0042702257
-
-
US Nuclear Regulatory Commission, Washington, D.C., March
-
Ellingwood, B.R., Song, J., 1996. NUREG/CR-6425, impact of structural aging on seismic risk assessment of reinforced concrete structures in nuclear power plants. US Nuclear Regulatory Commission, Washington, D.C., March.
-
(1996)
NUREG/CR-6425, Impact of Structural Aging on Seismic Risk Assessment of Reinforced Concrete Structures in Nuclear Power Plants
-
-
Ellingwood, B.R.1
Song, J.2
-
7
-
-
0042200993
-
-
US Nuclear Regulatory Commission, Washington, D.C., June
-
Ellingwood, B.R., Bhattacharya, B., Zheng, R.H., 1996. Draft Report NUREG/CR-5442, reliability-based condition assessment of steel containment and liners. US Nuclear Regulatory Commission, Washington, D.C., June.
-
(1996)
Draft Report NUREG/CR-5442, Reliability-based Condition Assessment of Steel Containment and Liners
-
-
Ellingwood, B.R.1
Bhattacharya, B.2
Zheng, R.H.3
-
10
-
-
0010743602
-
-
Nuclear Regulatory Commission, Washington, D.C., March
-
Naus, D.J., Oland, C.B., Ellingwood, B.R., 1996. NUREG/CR-6424, report on aging of nuclear power plant reinforced concrete structures. Nuclear Regulatory Commission, Washington, D.C., March.
-
(1996)
NUREG/CR-6424, Report on Aging of Nuclear Power Plant Reinforced Concrete Structures
-
-
Naus, D.J.1
Oland, C.B.2
Ellingwood, B.R.3
-
11
-
-
0010660127
-
-
Oak Ridge National Laboratory, Oak Ridge, TN, February
-
Oland, C.B., Naus, D.J., 1996. ORNL/NRC/LTR-95/29, degradation assessment methodology for application to steel containments and liners of reinforced concrete structures in nuclear power plants. Oak Ridge National Laboratory, Oak Ridge, TN, February.
-
(1996)
ORNL/NRC/LTR-95/29, Degradation Assessment Methodology for Application to Steel Containments and Liners of Reinforced Concrete Structures in Nuclear Power Plants
-
-
Oland, C.B.1
Naus, D.J.2
-
12
-
-
85031584148
-
-
US Nuclear Regulatory Commission, Washington, D.C., June
-
Petrone, C.D., Correia, R.P., Black, S.C., 1995. NUREG-1526, lessons learned from early implementation of the maintenance rule at nine nuclear power plants. US Nuclear Regulatory Commission, Washington, D.C., June.
-
(1995)
NUREG-1526, Lessons Learned from Early Implementation of the Maintenance Rule at Nine Nuclear Power Plants
-
-
Petrone, C.D.1
Correia, R.P.2
Black, S.C.3
-
13
-
-
0042200977
-
-
inservice inspection of prestressed concrete containment structures with grouted tendons. US Nuclear Regulatory Commission, Washington, D.C., August
-
Regulatory Guide 1.90, 1977. Revision 1, inservice inspection of prestressed concrete containment structures with grouted tendons. US Nuclear Regulatory Commission, Washington, D.C., August.
-
(1977)
Regulatory Guide 1.90, 1977. Revision 1
-
-
-
14
-
-
0042702244
-
-
inspection of water-control structures associated with nuclear power plants. US Nuclear Regulatory Commission, Washington, D.C., March
-
Regulatory Guide 1.127, 1978. Revision 1, inspection of water-control structures associated with nuclear power plants. US Nuclear Regulatory Commission, Washington, D.C., March.
-
(1978)
Regulatory Guide 1.127, 1978. Revision 1
-
-
-
15
-
-
0038980326
-
-
Regulatory Guide 1.35, US Nuclear Regulatory Commission, Washington, D.C., July
-
Regulatory Guide 1.35, 1990. Revision 3, inservice inspection of ungrouted tendons in prestressed concrete containments. US Nuclear Regulatory Commission, Washington, D.C., July.
-
(1990)
Revision 3, Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments
-
-
-
17
-
-
0041700468
-
-
Title 10, The Maintenance Rule, Office of the Federal Register, National Archives and Records Administration, Washington, D.C., January
-
Title 10, 1996. Part 50.65 of Code of Federal Regulations (10 CFR 50.65). The Maintenance Rule, Office of the Federal Register, National Archives and Records Administration, Washington, D.C., January.
-
(1996)
Part 50.65 of Code of Federal Regulations (10 CFR 50.65)
-
-
-
18
-
-
0042200964
-
-
Title 10, The License Renewal Rule, Office of the Federal Register, National Archives and Records Administration. Washington, D.C., January
-
Title 10, 1996. Part 54 of Code of Federal Regulations (10 CFR Part 54). The License Renewal Rule, Office of the Federal Register, National Archives and Records Administration. Washington, D.C., January.
-
(1996)
Part 54 of Code of Federal Regulations (10 CFR Part 54)
-
-
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