Issue Section:
Research Papers
1.
ASME Boiler and Pressure Vessel Code, 1989, Section
III, Nuclear Power Plant Components, Division I and Section XI, Rules for
Inservice Inspection of Nuclear Power Plant Components, Division I, New York,
NY.
2.
U.S. Code of Federal Regulations,
“Reactor Site Criteria,” Part 100, Appendix A, Title 10,
“Energy.”
3.
U.S. Nuclear Regulatory Commissions, 1981, “Standard
Review Plan for the Review of Safety Analysis Reports for Nuclear Power
Plants—LWR Edition,” USNRC Report NUREG-0800, Revision 1, July.
4.
ASME, 1967, “Power Piping,” USAS B31.1.0, New York,
NY.
5.
U.S. Nuclear Regulatory Commission, 1978 “Evaluation
of the Plastic Characteristics of Piping Products in Relation to ASME Code
Criteria,” NUREG/CR-0261, July.
6.
General Electric Company, 1978, “Functional
Capability Criteria for Essential Mark II Piping,” NEDO-21985,
Sept.
7.
U.S. Nuclear Regulatory Commission, 1984/85, “Report
of the U.S. Nuclear Regulatory Commission Piping Review Committee,” NUREG-1061,
5 Vols.
8.
U.S. Nuclear Regulatory Commission, 1992, “Functional
Capability of Piping Systems,” NUREG-1367, Nov.
9.
U.S. Nuclear Regulatory Commission, 1991,
“Verification of Piping Response Calculations of SMACS Code with Data from
Seismic Testing of an In-plant Piping System,” NUREG/CR-5757 (ANL-91/25),
Sept.
10.
ASME Boiler and Pressure Vessel Code, “Code Cases,”
1984a, N-411, Alternative Damping Values for Response Spectra Analysis of Class
1, 2, and 3 Piping, Sept.
11.
ASME Boiler and Pressure Vessel Code, 1984b, “Code
Cases,” N-397, Alternative Rules for Spectrum Broadening Procedures of N-1226.3
for Class 1, 2, and 3 Piping Section III, Division 1, Feb.
12.
U.S. Nuclear Regulatory Commission, 1988, “High-Level
Seismic Response and Failure Prediction Methods for Piping,” NUREG/CR-5023
(WHC-EP-0081), Jan.
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