You need JavaScript to view this

CRBRP flow induced vibration program

Abstract

The program to assure the structural adequacy of Clinch River Breeder Reactor (CRBRP) components during its planned 30 years of operation is described. The program includes (1) an assessment of reactor components relative to their susceptibility to FIV, (2) designing to minimize component excitation due to Fluid induced vibrations (FIV), (3) scale model tests to measure structural response during simulated operating conditions and (4) preoperational tests. An overview of the CRBRP test program is described. Additionally, details of scale model testing of reactor internals and the steam generator is described in more detail. (author)
Authors:
Novendstern, E H; [1]  Grochowski, F A; Yang, T M; [2]  Ryan, J A; Mulcahy, T M
  1. Westinghouse Advanced Reactor Division, Madison, PA (United States)
  2. General Electric Co., Fast Breeder Reactor Department, Sunnyvale, CA (United States)
Publication Date:
Dec 01, 1977
Product Type:
Conference
Report Number:
IWGFR-21
Reference Number:
EDB-01:030693
Resource Relation:
Conference: IAEA-IWGFR specialists meeting on LMFBR flow induced vibrations, Argonne, IL (United States), 20-23 Sep 1977; Other Information: 7 refs, 18 figs, 9 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; CLINCH RIVER BREEDER REACTOR; FLUID FLOW; MECHANICAL VIBRATIONS; PERFORMANCE TESTING; REACTOR COMPONENTS; REACTOR OPERATION; STEADY-STATE CONDITIONS; STEAM GENERATORS
OSTI ID:
20146250
Research Organizations:
International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA0100304011772
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 71-98
Announcement Date:
Apr 16, 2001

Citation Formats

Novendstern, E H, Grochowski, F A, Yang, T M, Ryan, J A, and Mulcahy, T M. CRBRP flow induced vibration program. IAEA: N. p., 1977. Web.
Novendstern, E H, Grochowski, F A, Yang, T M, Ryan, J A, & Mulcahy, T M. CRBRP flow induced vibration program. IAEA.
Novendstern, E H, Grochowski, F A, Yang, T M, Ryan, J A, and Mulcahy, T M. 1977. "CRBRP flow induced vibration program." IAEA.
@misc{etde_20146250,
title = {CRBRP flow induced vibration program}
author = {Novendstern, E H, Grochowski, F A, Yang, T M, Ryan, J A, and Mulcahy, T M}
abstractNote = {The program to assure the structural adequacy of Clinch River Breeder Reactor (CRBRP) components during its planned 30 years of operation is described. The program includes (1) an assessment of reactor components relative to their susceptibility to FIV, (2) designing to minimize component excitation due to Fluid induced vibrations (FIV), (3) scale model tests to measure structural response during simulated operating conditions and (4) preoperational tests. An overview of the CRBRP test program is described. Additionally, details of scale model testing of reactor internals and the steam generator is described in more detail. (author)}
place = {IAEA}
year = {1977}
month = {Dec}
}