skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

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

Conference ·
OSTI ID:5206964

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.

Research Organization:
Hanford Engineering Development Lab., Richland, WA (USA)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC14-76FF02170
OSTI ID:
5206964
Report Number(s):
HEDL-SA-1825-FP; CONF-801002-3; TRN: 80-015247
Resource Relation:
Conference: ANS/ASME topical meeting on reactor thermal-hydraulics, Saratoga, NY, USA, 9 Oct 1980
Country of Publication:
United States
Language:
English