Published February 1987 | Version v1
Report

Pipe damping studies

Creators

  • 1. EG and G Idaho, Inc., Idaho Falls

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).