Method for predicting pump-induced acoustic pressures in fluid-handling systems. [ACSTIC code]
Conference
·
· Am. Soc. Mech. Eng., Pressure Vessels Piping Div., (Tech. Rep.) PVP; (United States)
OSTI ID:6196707
A method is described for predicting the amplitudes of pump-induced acoustic pressures in fluid-handling systems using a node-flow path discretization methodology and a harmonic analysis algorithm. A computer model of a Westinghouse test loop using the volumetric forcing function model of the pump is presented. Comparisons of measured pressure amplitude profiles in the loop with model prediction are shown to be in good agreement for both the first and second pump blade-passing frequencies. 10 refs.
- Research Organization:
- Westinghouse Electr Corp, Pittsburgh, PA, USA
- OSTI ID:
- 6196707
- Report Number(s):
- CONF-820601-
- Journal Information:
- Am. Soc. Mech. Eng., Pressure Vessels Piping Div., (Tech. Rep.) PVP; (United States), Vol. 63; Conference: ASME pressure vessel and piping conference, Orlando, FL, USA, 27 Jun 1982
- Country of Publication:
- United States
- Language:
- English
Similar Records
Sound generation by a centrifugal pump at blade passing frequency
Transient gas motion in nuclear-reactor-pumped lasers: Computational and experimental results
Transient gas motion in nuclear-reactor-pumped lasers: computational and experimental results
Book
·
Sun Dec 01 00:00:00 EST 1996
·
OSTI ID:6196707
Transient gas motion in nuclear-reactor-pumped lasers: Computational and experimental results
Conference
·
Tue Jan 01 00:00:00 EST 1991
·
OSTI ID:6196707
Transient gas motion in nuclear-reactor-pumped lasers: computational and experimental results
Journal Article
·
Mon Mar 01 00:00:00 EST 1993
· Nuclear Science and Engineering; (United States)
·
OSTI ID:6196707
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
REACTOR COOLING SYSTEMS
COMPUTERIZED SIMULATION
A CODES
COMPUTER CODES
DYNAMIC LOADS
MECHANICAL VIBRATIONS
COOLING SYSTEMS
ENERGY SYSTEMS
REACTOR COMPONENTS
REACTORS
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
PWR TYPE REACTORS
REACTOR COOLING SYSTEMS
COMPUTERIZED SIMULATION
A CODES
COMPUTER CODES
DYNAMIC LOADS
MECHANICAL VIBRATIONS
COOLING SYSTEMS
ENERGY SYSTEMS
REACTOR COMPONENTS
REACTORS
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled