The High Level Vibration Test Program

Conference · Sun Jan 01 00:00:00 EST 1989

OSTI ID:6990570

Hofmayer, C H; Curreri, J R; Park, Y J; Kato, W Y ^[1]; Kawakami, S ^[2]

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1. Brookhaven National Lab., Upton, NY (USA)
2. Nuclear Power Engineering Test Center, Tokyo (Japan)

As part of cooperative agreements between the United States and Japan, tests have been performed on the seismic vibration table at the Tadotsu Engineering Laboratory of Nuclear Power Engineering Test Center (NUPEC) in Japan. The objective of the test program was to use the NUPEC vibration table to drive large diameter nuclear power piping to substantial plastic strain with an earthquake excitation and to compare the results with state-of-the-art analysis of the problem. The test model was designed by modifying the 1/2.5 scale model of the PWR primary coolant loop. Elastic and inelastic seismic response behavior of the test model was measured in a number of test runs with an increasing excitation input level up to the limit of the vibration table. In the maximum input condition, large dynamic plastic strains were obtained in the piping. Crack initiation was detected following the second maximum excitation run. The test model was subjected to a maximum acceleration well beyond what nuclear power plants are designed to withstand. This paper describes the overall plan, input motion development, test procedure, test results and comparisons with pre-test analysis. 4 refs., 16 figs., 2 tabs.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• Sponsoring Organization: EPRI; USNRC
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6990570
• Report Number(s): BNL-NUREG-43173; CONF-8910222-18; ON: DE90008516; TRN: 90-008878
• Resource Relation: Conference: 17. water reactor safety information meeting, Rockville, MD (USA), 23-25 Oct 1989
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
58 GEOSCIENCES
BWR TYPE REACTORS
SEISMIC EFFECTS
PWR TYPE REACTORS
ACCELERATION
COMPARATIVE EVALUATIONS
CRACKS
DATA PROCESSING
DESIGN
EARTHQUAKES
EMERGENCY PLANS
FAILURE MODE ANALYSIS
FATIGUE
FRACTURE MECHANICS
FREQUENCY ANALYSIS
MEASURING METHODS
MECHANICAL VIBRATIONS
MODIFICATIONS
PERFORMANCE TESTING
REACTOR COOLING SYSTEMS
REACTOR SAFETY
RISK ASSESSMENT
STEAM GENERATORS
TECHNOLOGY ASSESSMENT
BOILERS
COOLING SYSTEMS
ENERGY SYSTEMS
MECHANICAL PROPERTIES
MECHANICS
PROCESSING
REACTOR COMPONENTS
REACTORS
SAFETY
SEISMIC EVENTS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TESTING
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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210100 - Power Reactors
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210200 - Power Reactors
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580000 - Geosciences