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)
Novendstern, E H;
[1]
Grochowski, F A;
Yang, T M;
[2]
Ryan, J A;
Mulcahy, T M
- Westinghouse Advanced Reactor Division, Madison, PA (United States)
- General Electric Co., Fast Breeder Reactor Department, Sunnyvale, CA (United States)
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}
}
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}
}