Pipe tests to evaluate high amplitude response and damping

Conference · Sun Jan 01 00:00:00 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
• Resource Relation: Conference: MITI-USNRC seismic information exchange meeting, Palo Alto, CA, USA, 18 Jul 1984; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

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