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FFTF scale-model characterization of flow induced vibrational response of reactor internals

Abstract

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% to 111% of the scaled prototype design flow. Selected model and prototype components were shaker tested to establish modal characteristics. 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. (author)
Authors:
Ryan, J A; Julyk, L J [1] 
  1. Hanford Engineering Development Laboratory, Richland, WA (United States)
Publication Date:
Dec 01, 1977
Product Type:
Conference
Report Number:
IWGFR-21
Reference Number:
EDB-01:030698
Resource Relation:
Conference: IAEA-IWGFR specialists meeting on LMFBR flow induced vibrations, Argonne, IL (United States), 20-23 Sep 1977; Other Information: 6 refs, 41 figs, 8 tabs; PBD: Dec 1977; Related Information: In: Specialists meeting on LMFBR flow induced vibrations. Summary report, 236 pages.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FFTF REACTOR; FLOW RATE; FLUID FLOW; FREQUENCY RESPONSE TESTING; HYDRAULICS; MEASURING METHODS; MECHANICAL VIBRATIONS; MOCKUP; REACTOR COMPONENTS; REACTOR CORES
OSTI ID:
20146255
Research Organizations:
International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA0100309011777
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 133-164
Announcement Date:
Apr 16, 2001

Citation Formats

Ryan, J A, and Julyk, L J. FFTF scale-model characterization of flow induced vibrational response of reactor internals. IAEA: N. p., 1977. Web.
Ryan, J A, & Julyk, L J. FFTF scale-model characterization of flow induced vibrational response of reactor internals. IAEA.
Ryan, J A, and Julyk, L J. 1977. "FFTF scale-model characterization of flow induced vibrational response of reactor internals." IAEA.
@misc{etde_20146255,
title = {FFTF scale-model characterization of flow induced vibrational response of reactor internals}
author = {Ryan, J A, and Julyk, L J}
abstractNote = {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% to 111% of the scaled prototype design flow. Selected model and prototype components were shaker tested to establish modal characteristics. 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. (author)}
place = {IAEA}
year = {1977}
month = {Dec}
}