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

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:
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
Research Org:
Hanford Engineering Development Lab., Richland, WA (USA)
Sponsoring Org:
USDOE
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