Pipe damping-results of vibration tests in the 33 to 100 Hertz frequency range

Technical Report · Tue Jul 01 04:00:00 EDT 1986

OSTI ID:5362795

Ware, A G

Research was performed for the US Nuclear Regulatory Commission (USNRC) by the Idaho National Engineering Laboratory (INEL) to determine best-estimate representations of damping values for nuclear piping systems excited in the 33 to 100 Hz frequency range. Vibrations in this frequency range are typical of fluid-induced transients, for which no formal pipe damping guidelines exist. The available data found in the literature and the USNRC/INEL pipe damping data bank were reviewed, and two series of tests on 3- and 5-in. laboratory piping systems supported with several typical nuclear piping supports were conducted as part of this research program. It was concluded that a suitable representation of the test data can be made by extending the Pressure Vessel Research Committee (PVRC) uninsulated piping curve at 3% of critical damping for frequencies greater than or equal to20 Hz. 13 refs., 35 figs.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5362795
• Report Number(s): NUREG/CR-4562; EGG-2450; ON: TI86015185
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BWR TYPE REACTORS
CONTROL EQUIPMENT
DAMPING
EQUIPMENT
FLOW REGULATORS
FLUID MECHANICS
HYDRAULICS
MECHANICAL VIBRATIONS
MECHANICS
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
PWR TYPE REACTORS
REACTORS
RELIEF VALVES
RESEARCH PROGRAMS
TESTING
THERMAL POWER PLANTS
US NRC
US ORGANIZATIONS
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS