TY - JOUR
T1 - Simulation of the Acoustic Loads Generated in the Intersection of a Main Steam Line and its Safety Relief Valve Branch of a BWR Plant under Extended Power Uprate Condition
AU - Ocampo-Ramirez, Arturo
AU - Hernández-Gómez, Luis H.
AU - Ruiz-López, Pablo
AU - Moreno-Cuahquentzi, Noel
AU - Urriolagoitia-Calderón, Guillermo
AU - Beltrán-Fernández, Juan A.
AU - Urriolagoitia-Sosa, Guillermo
AU - Fernandez-Valdés, Dayvis
N1 - Publisher Copyright:
© 2015 Trans Tech Publications Ltd, Switzerland.
PY - 2015
Y1 - 2015
N2 - The structural integrity of a BWR nuclear power plant can be compromised due to severe dynamic loads. Acoustic loads coming from a Safety Relief Valve branch can be adversely amplified if the steam flow is increased at the Main Steam Piping. This phenomenon has been reported previously in one BWR nuclear power plant. Its steam dryer was fractured and loose parts were generated due to high-cycle fatigue. This event has driven the United States Nuclear Regulatory Commission to issue specific regulations to evaluate acoustic loads which would be detrimental to the BWR steam dryer. In this paper, the acoustic loads were simulated when the steam flow is incremented from normal operation conditions to an Extended Power Uprate condition. It was analyzed, when the output power was incremented 14% and 28%. The initial conditions were determined with Computational Fluid Dynamics under steady state condition. This data was used in subsequent transient analysis. The model of Large Eddy Simulation was used and the acoustic simulation was performed with the Fowcs Williams and Hawkings Method. The Power Spectral Density was obtained with Fast Fourier Transform. The frequency peaks were found between 148 Hz and 155 Hz. These results are consistent with those obtained with the Helmholtz model and other results reported in the open literature. The results show that the peak pressure can be increased up to six times in resonance conditions, corresponding to a power uprate of 28%.
AB - The structural integrity of a BWR nuclear power plant can be compromised due to severe dynamic loads. Acoustic loads coming from a Safety Relief Valve branch can be adversely amplified if the steam flow is increased at the Main Steam Piping. This phenomenon has been reported previously in one BWR nuclear power plant. Its steam dryer was fractured and loose parts were generated due to high-cycle fatigue. This event has driven the United States Nuclear Regulatory Commission to issue specific regulations to evaluate acoustic loads which would be detrimental to the BWR steam dryer. In this paper, the acoustic loads were simulated when the steam flow is incremented from normal operation conditions to an Extended Power Uprate condition. It was analyzed, when the output power was incremented 14% and 28%. The initial conditions were determined with Computational Fluid Dynamics under steady state condition. This data was used in subsequent transient analysis. The model of Large Eddy Simulation was used and the acoustic simulation was performed with the Fowcs Williams and Hawkings Method. The Power Spectral Density was obtained with Fast Fourier Transform. The frequency peaks were found between 148 Hz and 155 Hz. These results are consistent with those obtained with the Helmholtz model and other results reported in the open literature. The results show that the peak pressure can be increased up to six times in resonance conditions, corresponding to a power uprate of 28%.
KW - Acoustic simulation
KW - Computational fluid dynamics
KW - Fatigue
KW - Ffowcs Williams and Hawkings Method
KW - Power spectral density
KW - Tone cavity
UR - http://www.scopus.com/inward/record.url?scp=85124390358&partnerID=8YFLogxK
U2 - 10.4028/www.scientific.net/DDF.362.190
DO - 10.4028/www.scientific.net/DDF.362.190
M3 - Artículo
AN - SCOPUS:85124390358
SN - 1012-0386
VL - 362
SP - 190
EP - 199
JO - Defect and Diffusion Forum
JF - Defect and Diffusion Forum
ER -