Pipe damping studies
Description
The Idaho National Engineering Laboratory (INEL) is conducting a research program to assist the United States Nuclear Regulatory Commission in determining best-estimate damping values for use in the dynamic analysis of nuclear power plant piping systems. This paper describes four tasks in the program that were undertaken in FY-86. In the first task, tests were conducted on a 5-in. INEL laboratory piping system and data were analyzed from a 6-in. laboratory system at the ANCO Engineers facility to investigate the parameters influencing damping in the seismic frequency range. Further tests were conducted on 3- and 5-in. INEL laboratory piping systems as the second task to determine damping values representative of vibrations in the 33 to 100 Hz range, typical of hydrodynamic transients. In the third task a statistical evaluation of the available damping data was conducted to determine probability distributions suitable for use in probabilistic risk assessments, and the final task evaluated damping data at high strain levels
Additional details
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission fourteenth water reactor safety information meeting. Volume 3. Equipment qualification, mechanical and structural research, seismic research, nuclear plant aging
- Journal Page Range
- p. 179-197.
- Report number
- NUREG/CP--0082-Vol.3
Conference
- Title
- 14. water reactor safety information meeting.
- Dates
- 27-31 Oct 1986.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19002108
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; DAMPING; DYNAMIC LOADS; EXPERIMENTAL DATA; IDAHO NATIONAL ENGINEERING LAB; INSPECTION; MECHANICAL VIBRATIONS; PIPES; PROBABILITY; PWR TYPE REACTORS; RADIATION PROTECTION; REACTOR MAINTENANCE; REACTOR SAFETY; RESEARCH PROGRAMS; RISK ASSESSMENT; SEISMIC EFFECTS; TRANSIENTS; US NRC
- Descriptors DEC
- DATA; ENRICHED URANIUM REACTORS; INFORMATION; MAINTENANCE; NATIONAL ORGANIZATIONS; NUMERICAL DATA; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS