Dr. Rodolfo Vaghetto

Photo of Vaghetto
Research Assistant Professor
TEES Assistant Research Engineer

Email: r.vaghetto@tamu.edu

Dr. Rodolfo Vaghetto is a research engineer in the Nuclear Engineering Department. He earned his Ph.D. and Master's in Nuclear Engineering at Texas A&M University where he developed experimental and computational skills working on different projects involving the High Temperature Gas-Cooled Reactors. His research interests also include computational thermal-hydraulics applied to existing Light Water Reactors (LWR) and Generation IV reactors. He currently leads the ongoing thermal-hydraulic activity to support the nuclear industry for the resolution of one of the most discussed generic safety issues of the operating reactors (GSI-191). 


Publications

  1. S. Lee, S. S. Abdulsattar, R. Vaghetto, Y. A. Hassan, "Permeability and compression of fibrous porous media generated from dilute suspensions of fiberglass debris during a loss of coolant accident," Nuclear Engineering and Design, Vol. 291, pp. 244-260, 2015.
  2. B. Beeny, R. Vaghetto, K. Vierow, Y. A. Hassan, "A Sensitivity Study Supporting Comparative Analysis of MELCOR and GOTHIC Large Dry Pressurized Water Reactor Containment Models," Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) NURETH15-13356.
  3. R. Vaghetto, S. Lee, E. Kee, Y. A. Hassan, "Experimental Observations of Boric Acid Precipitation Scenarios," Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) NURETH15-13055.
  4. B. Beeny, R. Vaghetto, K. Vierow, Y. A. Hassan, "MELCOR and GOTHIC Analyses of a Large Dry Pressurized Water Reactor Containment to Support Resolution of GSI-191," Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) NURETH15-13354.
  5. S. Lee, R. Vaghetto, J. Lim, M. Kappes, Y. A. Hassan, "The Effect of Electric Potential on Fibrous Debris Bypass through a Containment Sump Strainer," Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) NURETH15-13760
  6. T. Crook, R. Vaghetto, Y. A. Hassan, "Effects of Manual Operation during a Loss-of-Coolant Accident with Pump Unavailability," Proceedings of the 2015 American Nuclear Society Conference Annual Meeting, San Antonio, TX, June 7-11, 2015.
  7. R. Vaghetto, Y. A. Hassan, "Modelling the Thermal-Hydraulic Behaviour of the Reactor Cavity Cooling System using RELAP5-3D," Annuals in Nuclear Engineering, Vol. 73, pp. 75-83, 2014.
  8. R. Vaghetto, Y. A. Hassan, "Experimental Investigation of a Scaled Water-Cooled Reactor Cavity Cooling System," Nuclear Technology, Vol. 187, pp. 282-293, 2014.
  9. R. Vaghetto, A. Franklin, A. Vanni, Y. A. Hassan, "Sensitivity Analysis of a PWR Containment during a Loss of Coolant Accident Using RELAP5-3D," Proceedings of the 22nd International Conference on Nuclear Engineering, ICONE22 July 7-11, 2014, Prague, Czech Republic.
  10. T. Crook, R. Vaghetto, A. Vanni, Y. A. Hassan, "Sensitivity Analysis of a PWR Response during a Loss of Coolant Accident Under Hypothetical Core Blockage Scenario Using RELAP5-3D," Proceedings of the 22nd International Conference on Nuclear Engineering, ICONE22 July 7-11, 2014, Prague, Czech Republic.
  11. S. Lee, Y. A. Hassan, R. Vaghetto, S. S. Abdulsattar, M. Kappes, "Water Chemistry Sensitivity on Fibrous Debris Bypass through a Containment Sump Strainer," Proceedings of the 22nd International Conference on Nuclear Engineering, ICONE22 July 7-11, 2014, Prague, Czech Republic.
  12. S. Lee, Y. A. Hassan, S. S. Abdulsattar, and R. Vaghetto, "Experimental study of head loss through an LOCA-generated fibrous debris bed deposited on a sump strainer for Generic Safety Issue 191," Progress in Nuclear Engineering, Vol. 74, pp. 166-175, 2014.
  13. S. Lee, R. Vaghetto, S. S. Abdulsattar, M. Kappes, Y. A. Hassan, "Effects of pH and Electrical Conductivity on the Quantity of Fibrous Debris Bypass through a Containment Sumpt Strainer," 2014 ANS Annual Meeting, June 15-19 2014, Reno, Nevada.
  14. R. Vaghetto, A. Franklin, A. Vanni, Y. A. Hassan, "Sensitivity Analysis of a Pressure Response of a Typical Large, Dry, Containment during a Double-Ended Guillotine Break LOCA Using RELAP5-3D and MELCOR," Proceedings of the 2014 ANS Annual Meeting, Reno, NV June 15-19 (2014).
  15. S. Lee, R. Vaghetto, Y. A. Hassan, "Measurement of Water Chemistry Sensitivity on NUKON Fibrous Debris Penetration through a Sump Strainer," Risk Management for Complex Socio-Technical Systems (RM4CSS), November 11-15, 2013, Washington, D.C.
  16. R. Vaghetto, E. Kee, Y. A. Hassan, "RELAP5-3D Simulation of Core Flow Paths during a Hypothetical Debris-Generated Core Blockage Scenario," American Nuclear Society 2013 Winter Meeting and Nuclear Technology Expo, November 10-14 2013, Washington, D.C. (2013).
  17. R. Vaghetto, A. Franklin, Y. A. Hassan, "Sensitivity Study of Hypothetical Debris-Generated Core Blockage Scenarios," American Nuclear Society 2013 Winter Meeting and Nuclear Technology Expo, November 10-14 2013, Washington, D.C. (2013).
  18. R. Vaghetto, Y. A. Hassan, "Study of debris-generated core blockage scenarios during loss of coolant accidents using RELAP5-3D," Nuclear Engineering and Design, Vol. 261, pp. 144-155, 2013.
  19. R. Vaghetto, B. A. Beeny, Y. A. Hassan, K. Vierow, "Sensitivity Analysis of a Typical Large, Dry Containment Response during a Loss of Coolant Accident using RELAP5-3D and MELCOR," American Nuclear Society 2013 Annual Meeting, June 16-20 2013, Atlanta, GA.
  20. R. Vaghetto, D. De Luca, Y. A. Hassan, "Analysis of Thermal-Hydraulic System Response of a Pressurized Water Reactor during Hypothetical Core Blockage Scenarios," The 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15), Convention Hall, Pisa, Italy - May 12-17 2013.
  21. R. Vaghetto, Y. A. Hassan, "The Steady-State Phase of the Reactor Cavity Cooling System Experimental Facility and Comparison with RELAP5-3D Simulations," The 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15), Convention Hall, Pisa, Italy - May 12-17 2013.
  22. R. Vaghetto, B. A. Beeny, Y. A. Hassan, K. Vierow, "Analysis of Long-Term Cooling of a LOCA by Coupling RELAP5-3D and MELCOR," American Nuclear Society 2012 Winter Meeting and Nuclear Technology Expo, November 11-15 2012, San Diego, CA.
  23. R. Vaghetto, S. Lee, Y. A. Hassan, "Analysis of the Steady-State Phase of the Reactor Cavity Cooling System Experimental Facility," American Nuclear Society 2012 Winter Meeting and Nuclear Technology Expo, November 11-15 2012, San Diego, CA.
  24. S. Lee, S. S. Abdulsattar, R. Vaghetto, Y. A. Hassan, "Experimental Study of Fibrous Debris Head Loss through Sump Strainer," Advances in Thermal Hydraulics (ATH '12), November 11-15 2012, San Diego, CA.
  25. R. Vaghetto, D. De Luca, Y. A. Hassan, "Thermal-Hydraulic System Response of a Pressurized Water Reactor Under Full Core Blockage Hypothesis during Loss of Coolant Accidents," International Workshop of Nuclear Safety and Severe Accident (NUSSA), September 7-8 2012, Beijing, China.
  26. R. Vaghetto, S. Lee, Y. A. Hassan, "Reactor Cavity Cooling System Experimental Facility Shakedown and RELAP5-3D Model Validation," Proceedings of the 20th International Conference on Nuclear Engineering, ICONE20 July 30-August 3, 2012, Anaheim, California.
  27. O. Rodriguez, R. Vaghetto, Y. A. Hassan, "Sensitivity Study of the South Texas Project Power Plant Steady-State Simulations using RELAP5-3D coupled with DAKOTA," Proceedings of the 20th International Conference on Nuclear Engineering, ICONE20 July 30-August 3, 2012, Anaheim, California, USA. 55235.
  28. R. Vaghetto, H. Wu, Y. A. Hassan, "RELAP5-3D Simulations of the Reactor Cavity Cooling System Experimental Facility," Presented at 2012 ANS Annual Meeting, June 24-28, 2012, Chicago, Il and published in the ANS Transactions, Vol. 106, 2012.
  29. R. Vaghetto, L. Capone, Y. A. Hassan, "Experimental Study of the Effect of Graphite Dispersion on the Heat Transfer Phenomena in a Reactor Cavity Cooling System," Nuclear Technology, Vol. 177, pp. 217-230, 2012.
  30. L. Capone, Y. A. Hassan, R. Vaghetto, "Reactor cavity cooling system (RCCS) experimental characterization," Nuclear Engineering and Design, Vol. 241, pp. 4775-4782, 2011.
  31. R. Vaghetto, Y. A. Hassan, "Scaling the NGNP Reactor Cavity Cooling System," American Nuclear Society 2011 Winter Meeting, October 30-November 3, 2011, Washington, D.C.
  32. R. Vaghetto, H. Wei, Y. A. Hassan, "Simulation of a Simple RCCS Experiment with RELAP5-3D System Code and Computational Fuid Dynamics Computer Program," 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, NURETH-14, Toronto, Ontario, Canada, September 25-30, 2011. NURETH14-352
  33. R. Vaghetto, Y. A. Hassan, "Analysis of the Thermo-hydraulic Behavior of the New TEXAS A&M RCCS Experimental Facility Using Relap5-3D," Proceedings of ICONE19, 19th International Conference on Nuclear Engineering, May 16-19, 2011, Chiba, Japan. ICONE19-43266.
  34. R. Vaghetto, P. D. Bayless, R. R. Schultz, Y. A. Hassan, "Modeling the Modular High Temperature Gas-Cooled Reactor Core with RELAP5-3D," Proceedings of ICONE19, 19th International Conference on Nuclear Engineering, May 16-19, 2011, Chiba, Japan. ICONE19-43261.
  35. L. Capone, R. Vaghetto, Y. A. Hassan, "Experimental Analysis of the Effects of the Graphite Dispersion on the Thermal-Hydraulic Phenomena Inside the Reactor Cavity Cooling System," Proceedings of ICAPP 2011, Nice, France, May 2-5, 2011, Paper 11471.
  36. L. Capone, R. Vaghetto, Y. A. Hassan, "Graphite Dispersion Effects Experimental Analysis for a Reactor Cavity Cooling System (RCCS)," American Nuclear Society 2010 Winter Meeting, Novemeber 7-11 2010, Las Vegas Nv.