Show source-provided references
2. DeBoo, G., Ramsden, K., Gesior, R., and Strub, B. (2007, January 22–26). Identification of Quad Cities main steam line acoustic source and vibration reduction. Proceedings of the Pressure Vessels and Piping Conference, San Antonio, TX, USA.
10.1115/PVP2007-26658 ↗4. Basavaraju, C., Manoly, K.A., Murphy, M.C., and Jessup, W.T. (2013, January 14–18). BWR Steam Dryer Issues and Lessons Learned Related to Flow-Induced Vibration. Proceedings of the ASME Pressure Vessels and Piping Conference, Paris, France.
10.1115/PVP2013-97218 ↗6. 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 Conditions
10.4028/www.scientific.net/DDF.362.190 ↗7. Hambric, S.A., Ziada, S., and Morante, R.J. (2018). Overview of Boiling Water Reactor Steam Dryer Alternating Stress Assessment Procedures. ASME J. Nucl. Rad. Sci., 4.
10.1115/1.4037898 ↗9. Flow-Induced Vibration: Guidelines for Design, Diagnosis and Troubleshooting of Common Power Plant Components
10.1115/1.3264460 ↗10. Hambric, S.A., Mulcahy, T.M., Shah, V.N., Scarbrough, T., and Wu, C. (2006, January 17–19). Flow Induced Vibration Effects on Nuclear Power Plant Components Due to Main Steam Line Valve Singing. Proceedings of the Ninth NRC/ASME Symposium on Valves, Pumps and Inservice Testing, NRC NUREG CP-0152, Washington, DC, USA. Available online: https://www.nrc.gov/docs/ml0727/ml072700042.pdf.
12. U.S. Nuclear Regulatory Commission (2023, February 01). Comprehensive Vibration Assessment Program for Reactor Internals during Preoperational and Initial Startup Testing 3, Regulatory Guide 1.20, Rev.4, Available online: https://www.nrc.gov/docs/ML1605/ML16056A338.pdf.
13. NRC (2023, February 01). 2002. Failure of Steam Dryer Cover Plate After a Recent Power Uprate. U.S. Nuclear Regulatory Commission. Washington, DC, NRC Information Notice 2002-26, Available online: https://www.nrc.gov/docs/ML0225/ML022530291.pdf.
14. NRC (2023, February 01). 2013. Programs for Monitoring Boiling-Water Reactor Steam Dryer Integrity. U.S. Nuclear Regulatory Commission, Washington, DC, NRC Information Notice 2013-10, ADAMS Accession No. ML13003A049, Available online: https://www.nrc.gov/docs/ML1300/ML13003A049.pdf.
15. Brazhenko, V., Cai, J.-C., and Fang, Y. (2024). Utilizing a Transparent Model of a Semi-Direct Acting Water Solenoid Valve to Visualize Diaphragm Displacement and Apply Resulting Data for CFD Analysis. Water, 16.
10.3390/w16233385 ↗17. Turbulence Modelling
18. (2024, March 01). ANSYS Fluent User’s Guide, Chapter 15. 2024. Modelling Turbulence, R2, 2061-2161. Available online: https://ansyshelp.ansys.com.
19. Benra, F.K., Dohmen, H.J., Pei, J., Schuster, S., and Wan, B. (2011). A comparison of one-way and two-way coupling methods for numerical analysis of fluid structure interactions. J. Appl. Math., 2011.
10.1155/2011/853560 ↗22. Ziada, S., and Lafon, P. (2014). Flow-Excited Acoustic Resonance Excitation Mechanism, Design Guidelines, and Counter Measures. Appl. Mech., 66.
10.1115/1.4025788 ↗23. Szasz, G., Fujikawa, K.K., and Ananth, R. (2005, January 24–28). Dynamic Pressure Data Acquisition Via Strain Gage Measurements. Proceedings of the ASME International Design Engineering Technical Conferences and Computers and Information in Engineering Conference, Long Beach, CA, USA.
24. Szasz, G., Fujikawa, K.K., and DeBoo, G. (2006, January 23–27). Assessment of Steam Line Dynamic Pressures Using External Strain Gage Measurement. Proceedings of the ASME 2006 Pressure Vessels and Piping/ICPVT-11, Vancouver, BC, Canada.
26. (2024, March 01). ANSYS Fluent User’s Guide, Chapter 23.2024. Predicting Aerodynamically Generated Noise, R2, 2659–2701. Available online: https://ansyshelp.ansys.com.