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Title: Scale-model characterization of flow-induced vibrational response of FFTF reactor internals

Abstract

Fast Test Reactor core internal and peripheral components were assessed for flow-induced vibrational characteristics under scaled and simulated prototype flow conditions in the Hydraulic Core Mockup as an integral part of the Fast Test Reactor Vibration Program. The Hydraulic Core Mockup was an 0.285 geometric scale model of the Fast Test Reactor internals designed to simulate prototype vibrational and hydraulic characteristics. Using water to simulate sodium coolant, vibrational characteristics were measured and determined for selected model components over the scaled flow range of 36 to 110%. Additionally, in-situ shaker tests were conducted on selected Hydraulic Core Mockup outlet plenum components to establish modal characteristics. Most components exhibited resonant response at all test flow rates; however, the measured dynamic response was neither abnormal nor anomalously flow-rate dependent, and the predicted prototype components' response were deemed acceptable.

Authors:
;
Publication Date:
Research Org.:
Hanford Engineering Development Lab., Richland, WA (USA)
Sponsoring Org.:
USDOE
OSTI Identifier:
5206964
Report Number(s):
HEDL-SA-1825-FP; CONF-801002-3
TRN: 80-015247
DOE Contract Number:
AC14-76FF02170
Resource Type:
Conference
Resource Relation:
Conference: ANS/ASME topical meeting on reactor thermal-hydraulics, Saratoga, NY, USA, 9 Oct 1980
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FFTF REACTOR; REACTOR INTERNALS; HYDRAULICS; LIQUID FLOW; MECHANICAL VIBRATIONS; MOCKUP; TEST FACILITIES; EPITHERMAL REACTORS; FAST REACTORS; FLUID FLOW; FLUID MECHANICS; LIQUID METAL COOLED REACTORS; MECHANICS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; STRUCTURAL MODELS; TEST REACTORS; 220600* - Nuclear Reactor Technology- Research, Test & Experimental Reactors

Citation Formats

Ryan, J. A., and Mahoney, J. J. Scale-model characterization of flow-induced vibrational response of FFTF reactor internals. United States: N. p., 1980. Web.
Ryan, J. A., & Mahoney, J. J. Scale-model characterization of flow-induced vibrational response of FFTF reactor internals. United States.
Ryan, J. A., and Mahoney, J. J. Wed . "Scale-model characterization of flow-induced vibrational response of FFTF reactor internals". United States. doi:. https://www.osti.gov/servlets/purl/5206964.
@article{osti_5206964,
title = {Scale-model characterization of flow-induced vibrational response of FFTF reactor internals},
author = {Ryan, J. A. and Mahoney, J. J.},
abstractNote = {Fast Test Reactor core internal and peripheral components were assessed for flow-induced vibrational characteristics under scaled and simulated prototype flow conditions in the Hydraulic Core Mockup as an integral part of the Fast Test Reactor Vibration Program. The Hydraulic Core Mockup was an 0.285 geometric scale model of the Fast Test Reactor internals designed to simulate prototype vibrational and hydraulic characteristics. Using water to simulate sodium coolant, vibrational characteristics were measured and determined for selected model components over the scaled flow range of 36 to 110%. Additionally, in-situ shaker tests were conducted on selected Hydraulic Core Mockup outlet plenum components to establish modal characteristics. Most components exhibited resonant response at all test flow rates; however, the measured dynamic response was neither abnormal nor anomalously flow-rate dependent, and the predicted prototype components' response were deemed acceptable.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Oct 01 00:00:00 EDT 1980},
month = {Wed Oct 01 00:00:00 EDT 1980}
}

Conference:
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  • As an integral part of the Fast Test Reactor Vibration Program for Reactor Internals, the flow-induced vibrational characteristics of scaled Fast Test Reactor core internal and peripheral components were assessed under scaled and simulated prototype flow conditions in the Hydraulic Core Mockup. The Hydraulic Core Mockup, a 0.285 geometric scale model, was designed to model the vibrational and hydraulic characteristics of the Fast Test Reactor. Model component vibrational characteristics were measured and determined over a range of 36 percent to 111 percent of the scaled prototype design flow. Selected model and prototype components were shaker tested to establish modal characteristics.more » The dynamic response of the Hydraulic Core Mockup components exhibited no anomalous flow-rate dependent or modal characteristics, and prototype response predictions were adjudged acceptable.« less
  • It is shown that $sup 1$/$sub 24$th scale model test results accurately predict the flow-induced vibration and modes of full-size reactor internals. Dimensional analysis principles are reviewed and the similitude requirements for valid model tests of the flow-induced vibration of reactor internals are identified. Test results on reactor internals flow vibration models are presented and compared with plant test results. Reactor internals with neutron pads are shown to vibrate only about one-third as much as internals having a thermal shield. 17 references. (auth)
  • The sloshing response of a large reactor tank with in-tank components is presented. The study indicates that the presence of the internal components can significantly change the dynamic characteristics of the sloshing motion. The sloshing frequency of a tank with internals is considerably higher than that of a tank without internal. The higher sloshing frequency reduces the sloshing wave height on the free-surface but increases the dynamic pressure in the fluid.