High level vibration test of nuclear power piping: Overall plan, input motion development and analysis

Hofmayer, C H; Curreri, J R; Park, Y J; Kato, W Y; Costello, J F; Tang, H T; Kawakami, S

Title: High level vibration test of nuclear power piping: Overall plan, input motion development and analysis

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Abstract

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 tests involved increasing the excitation up to the limits of the vibration table in order to induce inelastic response in a reactor coolant system piping model. The model was subjected to a maximum acceleration well beyond what nuclear power plants are designed to withstand. The High Level Vibration Test (HLVT) 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. The upper and middle steam generator shell supports of the model, which simulated the actual plant condition, were removed and the steam generator shell was truncated. Furthermore, the four lower support columns for the steam generator were replaced by a pin-type support. A modified earthquake excitation was used to drive the structure to a condition of substantial strain. Since the piping was pressurized, and the high level input motion was repeated several times, it was possible to investigate the effects of ratchetting andmore »« less

Authors:: Hofmayer, C H; Curreri, J R; Park, Y J; Kato, W Y; Costello, J F; Tang, H T; Kawakami, S

Publication Date:: Sun Jan 01 00:00:00 EST 1989

Research Org.:: Brookhaven National Lab., Upton, NY (USA)

OSTI Identifier:: 5914377

Report Number(s):: BNL-NUREG-42677; CONF-890855-44
ON: DE89012671

DOE Contract Number:: AC02-76CH00016

Resource Type:: Conference

Resource Relation:: Conference: 10. international conference on Structural Mechanics in Reactor Technology (SMIRT), Anaheim, CA, USA, 14-18 Aug 1989; Other Information: Portions of this document are illegible in microfiche products

Country of Publication:: United States

Language:: English

Subject:: 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PIPES; SEISMIC EFFECTS; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; MECHANICAL VIBRATIONS; REACTOR SAFETY; SCALE MODELS; TEST FACILITIES; COOLING SYSTEMS; ENERGY SYSTEMS; REACTOR COMPONENTS; REACTORS; SAFETY; STRUCTURAL MODELS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

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                    Hofmayer, C H, Curreri, J R, Park, Y J, Kato, W Y, Costello, J F, Tang, H T, and Kawakami, S. High level vibration test of nuclear power piping: Overall plan, input motion development and analysis.  United States: N. p., 1989. 
        Web.

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                    Hofmayer, C H, Curreri, J R, Park, Y J, Kato, W Y, Costello, J F, Tang, H T, & Kawakami, S. High level vibration test of nuclear power piping: Overall plan, input motion development and analysis.  United States.

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                    Hofmayer, C H, Curreri, J R, Park, Y J, Kato, W Y, Costello, J F, Tang, H T, and Kawakami, S. 1989.  
        "High level vibration test of nuclear power piping: Overall plan, input motion development and analysis".  United States.  https://www.osti.gov/servlets/purl/5914377.

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@article{osti_5914377,

  title        = {High level vibration test of nuclear power piping: Overall plan, input motion development and analysis},

  author       = {Hofmayer, C H and Curreri, J R and Park, Y J and Kato, W Y and Costello, J F and Tang, H T and Kawakami, S},

  abstractNote = {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 tests involved increasing the excitation up to the limits of the vibration table in order to induce inelastic response in a reactor coolant system piping model. The model was subjected to a maximum acceleration well beyond what nuclear power plants are designed to withstand. The High Level Vibration Test (HLVT) 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. The upper and middle steam generator shell supports of the model, which simulated the actual plant condition, were removed and the steam generator shell was truncated. Furthermore, the four lower support columns for the steam generator were replaced by a pin-type support. A modified earthquake excitation was used to drive the structure to a condition of substantial strain. Since the piping was pressurized, and the high level input motion was repeated several times, it was possible to investigate the effects of ratchetting and fatigue as well. An isometric view of the test model and support frame is shown in Figure 1. Further details of the hot leg pipe are shown in Figure 2. The piping in the model is stainless steel, 14-15 inches in diameter and 1 to 1 1/4 inches thick. This paper describes the overall plan, the input motion development and pre-test analysis results. 4 refs., 8 figs., 1 tab.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/5914377},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Sun Jan 01 00:00:00 EST 1989},

  month        = {Sun Jan 01 00:00:00 EST 1989}

}

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