Pipe tests to evaluate high amplitude response and damping

Conference · Sun Jan 01 04:00:00 EST 1984

OSTI ID:6625526

Ware, A G

EG and G Idaho is assisting the USNRC and the Pressure Vessel Research Committee in supporting a final position on revised damping values for structural analyses of nuclear piping systems. The program began in 1981 and has proceeded in phases. Initially a literature survey and an assessment of available data were performed to establish a data base and to determine if the program was worth pursuing. It has continued with testing of laboratory piping systems in which one parameter at a time could be varied to calculate the various effects on damping. As part of this program, a series of vibrational tests on 76-mm and 203-mm (3-in. and 8-in.) Schedule 40 carbon steel piping was conducted to determine the changes in structural damping due to various parametric effects. The 10-m (33-ft) straight sections of piping were rigidly supported at the ends. Spring, rod, and constant force hangers, as well as a sway brace and snubbers were included as intermediate supports. Excitation was provided by low force level hammer impacts, a hydraulic shaker, and a 445-kN (50-ton) overhead crane for snapback tests. This paper presents the overall program plan, selected test results, and current and future research.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6625526
• Report Number(s): EGG-M-13684; CONF-840763-3; ON: DE84016120
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
ALLOYS
CARBON STEELS
DAMPING
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL STRUCTURES
MECHANICAL VIBRATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
SEISMIC EFFECTS
STEELS
SUPPORTS
TESTING
THERMAL POWER PLANTS