Prediction of high level vibration test results by use of available inelastic analysis techniques

Conference · Tue Jan 01 00:00:00 EST 1991

OSTI ID:5681684

Hofmayer, C H; Park, Y J ^[1]; Costello, J F ^[2]

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1. Brookhaven National Lab., Upton, NY (USA)
2. Nuclear Regulatory Commission, Washington, DC (USA)

As part of a cooperative study between the United States and Japan, the US Nuclear Regulatory Commission and the Ministry of International Trade and Industry of Japan agreed to perform a test program that would subject a large scale piping model to significant plastic strains under excitation conditions much greater than the design condition for nuclear power plants. The objective was to compare the results of the tests with state-of-the-art analyses. Comparisons were done at different excitation levels from elastic to elastic-plastic to levels where cracking was induced in the test model. The program was called the high Level Vibration Test (HLVT). The HLVT was performed on the seismic table at the Tadotsu Engineering Laboratory of Nuclear Power Engineering Test Center in Japan. The test model was constructed by modifying the 1/2.5 scale model of one loop of a PWR primary coolant system which was previously tested by NUPEC as part of their seismic proving test program. A comparison of various analysis techniques with test results shows a higher prediction error in the detailed strain values than in the overall response values. This prediction error is magnified as the plasticity in the test model increases. There is no significant difference in the peak responses between the simplified and the detailed analyses. A comparison between various detailed finite element model runs indicates that the material properties and plasticity modeling have a significant impact on the plastic strain responses under dynamic loading reversals. 5 refs., 12 figs.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5681684
• Report Number(s): BNL-NUREG-45835; CONF-910817-6; ON: DE91009437
• Resource Relation: Conference: 11. international conference on structural mechanics in reactor technology, Tokyo (Japan), 18-23 Aug 1991
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
MECHANICAL STRUCTURES
SEISMIC EFFECTS
PWR TYPE REACTORS
REACTOR SAFETY EXPERIMENTS
A CODES
BNL
CRACKS
DYNAMIC LOADS
EPRI
GROUND MOTION
JAPAN
MECHANICAL VIBRATIONS
PIPES
PLASTICITY
PRIMARY COOLANT CIRCUITS
REGULATIONS
RESEARCH PROGRAMS
SCALE MODELS
SEISMIC SOURCES
STRAINS
US NRC
ASIA
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
MECHANICAL PROPERTIES
MOTION
NATIONAL ORGANIZATIONS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
STRUCTURAL MODELS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled