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Nuclear reactors > Containment
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Reliability

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1.
Pretest analysis of a 1:4-scale prestressed concrete containment vessel model
Published
Washington, DC : The Office : [Supt. of Docs., U.S. G.P.O., distributor], 2000.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/6685
Format
Books / Microforms
2.
Resolution of the direct containment heating issue for combustion engineering plants and Babcock & Wilcox plants
Published
Washington, DC : Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1998.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/6475
Format
Books / Microforms
3.
Risk assessment of severe accident-induced steam generator tube rupture
Published
Washington, DC : Division of Systems Safety and Analysis, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1998.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:10/1570
Format
Books / Microforms
4.
Aging assessment of Westinghouse PWR and General Electric BWR containment isolation functions
Published
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1996.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/6339
Format
Books / Microforms
5.
Applications of reliability degradation analysis
Author
Vesley, W. E.
Published
Washington, DC : Division [of] Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1996.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/6415
Format
Books / Microforms
6.
Estimated net value and uncertainty for automating ECCS switchover at PWRs
Published
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1996.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/6432
Format
Books / Microforms
7.
Reliability-based condition assessment of steel containment and liners
Author
Ellingwood, Bruce
Published
Washington, D.C. : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1996.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/5442
Format
Books / Microforms
8.
Resolution of the direct containment heating issue for all Westinghouse plants with large dry containments or subatmospheric containments
Author
Pilch, M.
Published
Washington, DC : Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1996.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/6338
Format
Books / Microforms
9.
The effects of age on nuclear power plant containment cooling systems
Published
Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1994.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/5939
Format
Books / Microforms
10.
The Probability of Mark-I containment failure by melt-attack of the liner
Published
Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1993.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/6025
Format
Books / Microforms
11.
The Probability of liner failure in a Mark-I containment
Published
Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : For sale by the U.S. G.P.O., Supt. of Docs., 1991.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/5423
Format
Books / Microforms
12.
Assessment of ice-condenser containment performance issues
Author
Nourbakhsh, H. P.
Published
Washington, DC : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/5589
Format
Books / Microforms
13.
Evaluations of core melt frequency effects due to component aging and maintenance
Author
Vesely, W. E.
Published
Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1990.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/5510
Format
Books / Microforms