HR job title
- Tees Research Assistant Professor
- Contact Info
- 1 979 845 5791
- Websites
Vaghetto, Rodolfo Research Assistant Professor
Positions
- Research Assistant Professor, Nuclear Engineering, College of Engineering
- Overview
- Publications
- Research
- Teaching
- Background
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Overview
Publications
selected publications
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academic article
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Menezes, C., Vaghetto, R., & Hassan, Y. A.
(2022).
Experimental Investigation of the Subchannel Axial Pressure Drop and Hydraulic Characteristics of a 61-Pin Wire Wrapped Rod Bundle. Journal of Fluids Engineering.
144(5),
-
Orea, D., Al-Mahbobi, L., Vaghetto, R., & Hassan, Y.
(2022).
Temperature Dependence of Laser Induced Fluorescence in Molten LiF-NaF-KF Eutectic using Tb3+, Eu3+, and Dy3+. Journal of Luminescence.
243, 118641-118641.
-
Bovati, O., Alper Yildiz, M., Hassan, Y., & Vaghetto, R.
(2022).
Pressure drop and flow characteristics in partially blocked wire wrapped rod bundles. Annals of Nuclear Energy.
165, 108671-108671.
-
Chavez, D. E., Yang, S. R., Vaghetto, R., & Hassan, Y. A.
(2021).
Experimental investigation of single helium bubbles rising in FLiNaK molten salt. INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW.
92, 108875-108875.
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Arora, O., Lancaster, B., Yang, S. R., Vaghetto, R., & Hassan, Y.
(2021).
Advanced flow and temperature measurements in a forced convection molten salt test loop. Annals of Nuclear Energy.
159, 108269-108269.
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Bovati, O., Yildiz, M. A., Hassan, Y., & Vaghetto, R.
(2021).
RANS simulations for transition and turbulent flow regimes in wire-wrapped rod bundles. INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW.
90, 108838-108838.
-
Childs, M., Vaghetto, R., Jones, P., Goth, N., & Hassan, Y.
(2021).
Experimental determination and analysis of the transverse pressure difference in a wire-wrapped rod bundle. International Journal of Heat and Mass Transfer.
170, 120958-120958.
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Vaghetto, R., Yang, S., Hodge, D., & Hassan, Y.
(2021).
Two-phase flow measurements and observations in a cooling panel of the reactor cavity cooling system. PROGRESS IN NUCLEAR ENERGY.
131, 103578-103578.
-
Childs, M., Muyshondt, R., Vaghetto, R., Nguyen, D. T., & Hassan, Y.
(2020).
Experimental Study on the Effect of Localized Blockages on the Friction Factor of a 61-Pin Wire-Wrapped Bundle. Journal of Fluids Engineering.
142(11),
-
Hollrah, B., Bucknor, M., Lisowski, D., Hassan, Y., Vaghetto, R., & Hu, R.
(2020).
Benchmark Simulation of the Natural Convection Shutdown Heat Removal Test Facility Using SAM. Nuclear Technology.
206(9), 1337-1350.
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Nguyen, T., Vaghetto, R., & Hassan, Y.
(2020).
Experimental investigation of turbulent wake flows in a helically wrapped rod bundle in presence of localized blockages. Physics of Fluids.
32(7), 075113-075113.
-
Orea, D., Vaghetto, R., Nguyen, T., & Hassan, Y.
(2020).
Experimental measurements of flow mixing in cold leg of a pressurized water reactor. Annals of Nuclear Energy.
140, 107137-107137.
-
Holler, D., Vaghetto, R., & Hassan, Y.
(2020).
Water temperature measurements with a Rayleigh backscatter distributed sensor. Optical Fiber Technology.
55, 102160-102160.
-
Nguyen, T., White, L., Vaghetto, R., & Hassan, Y.
(2019).
High-fidelity velocity measurements in a totally blocked interior subchannel of a wire-wrapped 61-pin hexagonal fuel bundle. Nuclear Engineering and Design.
353, 110234-110234.
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Holler, D., Vaghetto, R., & Hassan, Y.
(2019).
High-resolution wall temperature measurements with distributed fiber optic sensors. International Journal of Thermal Sciences.
145, 106042-106042.
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Nguyen, T., White, L., Vaghetto, R., & Hassan, Y.
(2019).
Turbulent flow and vortex characteristics in a blocked subchannel of a helically wrapped rod bundle. Experiments in Fluids: experimental methods and their applications to fluid flow.
60(8), 129.
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Quintanar, N. R., Nguyen, T., Vaghetto, R., & Hassan, Y. A.
(2019).
Natural circulation flow distribution within a multi-branch manifold. International Journal of Heat and Mass Transfer.
135, 1-15.
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Blakely, C., Zhang, H., Szilard, R., Epiney, A., Vaghetto, R., & Ban, H.
(2018).
Demonstration of LOTUS multiphysics BEPU analysis framework for LB-LOCA simulations. Annals of Nuclear Energy.
122, 8-22.
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Goth, N., Jones, P., Nguyen, D. T., Vaghetto, R., Hassan, Y. A., Obabko, A., Merzari, E., & Fischer, P. F.
(2018).
Comparison of experimental and simulation results on interior subchannels of a 61-pin wire-wrapped hexagonal fuel bundle. Nuclear Engineering and Design.
338, 130-136.
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Yildiz, M. A., Yang, S. R., Vaghetto, R., & Hassan, Y. A.
(2018).
Numerical analysis of 1/28 scaled NGNP HTGR reactor building test facility response to depressurization event using GOTHIC. Annals of Nuclear Energy.
119, 46-65.
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Goth, N., Jones, P., Duy Nguyen, T., Vaghetto, R., Hassan, Y., Salpeter, N., & Merzari, E.
(2018).
PTV/PIV measurements of turbulent flows in interior subchannels of a 61-pin wire-wrapped hexagonal fuel bundle. INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW.
71, 295-304.
-
Yang, S. R., Kappes, E., Nguyen, T., Vaghetto, R., & Hassan, Y.
(2018).
Experimental study on 1/28 scaled NGNP HTGR reactor building test facility response to depressurization event. Annals of Nuclear Energy.
114, 154-164.
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Nguyen, T., Goth, N., Jones, P., Vaghetto, R., & Hassan, Y.
(2018).
Stereoscopic PIV measurements of near-wall flow in a tightly packed rod bundle with wire spacers. Experimental Thermal and Fluid Science.
92, 420-435.
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Vaghetto, R., Jones, P., Goth, N., Childs, M., Lee, S., Thien Nguyen, D., & Hassan, Y. A.
(2018).
Pressure Measurements in a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle. Journal of Fluids Engineering.
140(3),
-
Vaghetto, R., Jones, P., Goth, N., Childs, M., Lee, S., Nguyen, D. T., & Hassan, Y. A.
(2017).
Pressure Measurements in a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle. Journal of Fluids Engineering.
140(3), 031104-1485.
-
Nguyen, T., Goth, N., Jones, P., Lee, S., Vaghetto, R., & Hassan, Y.
(2017).
PIV measurements of turbulent flows in a 61-pin wire-wrapped hexagonal fuel bundle. INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW.
65, 47-59.
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Vaghetto, R., Childs, M., Jones, P., Lee, S., Kee, E., & Hassan, Y. A.
(2017).
Experimental observations of boric acid precipitation scenarios. Nuclear Engineering and Design.
312, 422-428.
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Beeny, B., Vaghetto, R., Vierow, K., & Hassan, Y. A.
(2016).
MELCOR and GOTHIC Analyses of a Large Dry PWR Containment to Support Resolution of GSI-191. Nuclear Technology.
196(2), 292-302.
-
Kee, E., Hasenbein, J., Zolan, A., Grissom, P., Reihani, S., Mohaghegh, Z., ... Sakurahara, T.
(2016).
RoverD: Use of Test Data in GSI-191 Risk Assessment. Nuclear Technology.
196(2), 270-291.
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Vaghetto, R., Childs, M., Kee, E., & Hassan, Y. A.
(2016).
Observations and measurements of boric acid precipitation scenarios. PROGRESS IN NUCLEAR ENERGY.
91, 302-309.
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Vaghetto, R., Crook, T., Vanni, A., & Hassan, Y. A.
(2016).
Impact of Pressure Relief Holes on Core Coolability for a PWR during a Large-Break Loss-of-Coolant Accident with Core Blockage Using RELAP5-3D. Nuclear Technology.
193(1), 88-95.
-
Lee, S., Abdulsattar, S. S., Vaghetto, R., & Hassan, Y. A.
(2015).
Permeability and compression of fibrous porous media generated from dilute suspensions of fiberglass debris during a loss of coolant accident. Nuclear Engineering and Design.
291, 244-260.
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Vaghetto, R., & Hassan, Y. A.
(2014).
Modeling the thermalhydraulic behavior of the reactor cavity cooling system using RELAP5-3D. Annals of Nuclear Energy.
73, 75-83.
-
Vaghetto, R., & Hassan, Y. A.
(2014).
Experimental Investigation of a Scaled Water-Cooled Reactor Cavity Cooling System. Nuclear Technology.
187(3), 282-293.
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Lee, S., Hassan, Y. A., Abdulsattar, S. S., & Vaghetto, R.
(2014).
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 ENERGY.
74, 166-175.
-
Vaghetto, R., & Hassan, Y. A.
(2013).
Study of debris-generated core blockage scenarios during loss of coolant accidents using RELAP5-3D. Nuclear Engineering and Design.
261, 144-155.
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Vaghetto, R., Capone, L., & Hassan, Y. A.
(2012).
Experimental Study of the Effect of Graphite Dispersion on the Heat Transfer Phenomena in a Reactor Cavity Cooling System. Nuclear Technology.
177(2), 217-230.
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Capone, L., Hassan, Y. A., & Vaghetto, R.
(2011).
Reactor cavity cooling system (Rccs) experimental characterization. Nuclear Engineering and Design.
241(12), 4775-4782.
-
Menezes, C., Vaghetto, R., & Hassan, Y. A.
(2022).
Experimental Investigation of the Subchannel Axial Pressure Drop and Hydraulic Characteristics of a 61-Pin Wire Wrapped Rod Bundle. Journal of Fluids Engineering.
144(5),
-
conference paper
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Orea, D., Chavez, R., Nguyen, D. T., Vaghetto, R., Anand, N. K., Hassan, Y. A., & Sabharwall, P.
(2021).
PARTICLE DEPOSITION STUDY IN A HORIZONTAL SQUARE CHANNEL USING HIGH-RESOLUTION IMAGING. EPJ Web of Conferences.
10011-10011.
-
Nguyen, T., Vaghetto, R., & Hassan, Y.
(2020).
Turbulent Flow Characteristics in a Blocked Exterior Subchannel of a Helically Wrapped Rod Bundle
-
Childs, M., Muyshondt, R., Busco, G., Yildiz, M. A., Vaghetto, R., & Hassan, Y.
(2020).
Effect of Localized Blockages on the Friction Factor of a 61-Pin Wire-Wrapped Bundle
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Hodge, D., Yang, S., Hassan, Y., & Vaghetto, R.
(2020).
Behavior of a Scaled Water-Cooled Reactor Cavity Cooling System under Hypothetical Accident Conditions. 1843-1846.
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Yildiz, M., Vaghetto, R., Hassan, Y., & Bovati, O.
(2020).
CFD Simulations on a hexagonal 61-pin wire-wrapped fuel bundle with STARCCM+ and comparison with experimental data. 1509-1511.
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Alawneh, L., Vaghetto, R., Yang, S., Hassan, Y., & Alsmadi, E.
(2020).
Design and Optimization of the Shielding of an Accelerator Driven Thorium-Fueled Molten Salt Loop using MCNP6. 1259-1262.
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Vaghetto, R., Yang, S., Hassan, Y., & Arora, O.
(2020).
Flow Rate Estimation from Transient Temperature Response of a Forced Convection Molten Salt Test Facility. 1863-1866.
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Nguyeny, D., Childs, M., Anand, N., Vaghetto, R., Hassan, Y., & Muyshondt, R.
(2020).
Pressure Drop Measurements in a 61-Pin Wire Wrapped Hexagonal Fuel Bundle in Presence of Localized Subchannel Blockages. 1531-1534.
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Vaghetto, R., Hassan, Y., & Hollrah, B.
(2020).
VALIDATION OF THE SAM STEADY-STATE MODEL OF THE FAST FLUX TEST FACILITY. 1654-1657.
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Orea, D., Nguyen, T., Vaghetto, R., Anand, N. K., Hassan, Y. A., & Sabharwall, P.
(2019).
Experimental Study of Surrogate Particle Transport and Deposition in a Square Channel Using Particle Tracking Technique
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Orea, D., Choi, B., Nguyen, T., Vaghetto, R., Anand, N., Hassan, Y., & Sabharwall, P.
(2019).
An Investigation to Develop Measurement Techniques for Quantifying Fission Product Transport in a Gas-cooled Fast Reactor-Versatile Test Reactor Program
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Roelofs, F., Uitslag-Doolaard, H., Mikuz, B., Dovizio, D., de Santis, D., Shams, A., ... Pointer, D.
(2019).
CFD and experiments for wire-wrapped fuel assemblies
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Obabko, A., Merzari, E., Brockmeyer, L., Fischer, P., Sofu, T., Jackson, B., ... Hassan, Y.
(2019).
Validation of NEK5000 for 37-And 61-pin wire-wrap geometries with conjugate heat transfer
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Hassan, Y., Kyriakopoulos, V., Nguyen, T., Orea, D., & Vaghetto, R.
(2019).
Benchmark Exercise on Flow Mixing in Cold Leg of a Pressurized Water Reactor. 1783-1786.
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Hassan, Y., Holler, D., & Vaghetto, R.
(2019).
Distributed Wall Temperature Measurements in a Scaled Water-Cooled RCCS. 183-186.
-
Anand, N., Chavez, R., Hassan, Y., Nguyen, D., Orea, D., Sabharwall, P., & Vaghetto, R.
(2019).
Experimental Investigation of Surrogate Particle Transport in a Turbulent Channel Flow: Versatile Test Reactor Program. 1153-1156.
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Muyshondt, R., Nguyen, T., Hassan, Y., & Anand, N. K.
(2019).
High-Fidelity Velocity Measurements in a Cross-flow Plane of a Randomly Packed Bed Using Timeresolved Particle Image Velocimetry. The Proceedings of the International Conference on Nuclear Engineering (ICONE).
2389-2389.
-
Arora, O., Chavez, D., Hassan, Y., Holler, D., & Vaghetto, R.
(2019).
Response Time of Thermowells for Corrosive, High-Temperature Experiments. 1673-1676.
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Lai, J., Merzari, E., Vaghetto, R., Nguyen, D. T., & Hassan, Y.
(2018).
Video: Numerical and Experimental Buoyant Mixing
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Goth, N. E., Jones, P., Nguyen, T. D., Vaghetto, R., & Hassan, Y.
(2018).
Turbulent Transverse Plane PIV Measurements on a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle. v06at08a043-v06at08a043.
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Aksan, N., D'Auria, F., Lanfredini, M., Lutsanych, S., Bestion, D., Moretti, F., Hassan, Y., & Vaghetto, R.
(2018).
Prospective for nuclear thermal hydraulics created by ongoing and new Networks
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Mulloy, J. P., Hassan, Y. A., Orea, D., & Vaghetto, R.
(2018).
A RANS simulation of cold leg buoyant mixing. Transactions of the American Nuclear Society.
983-989.
-
Holler, D., Vaghetto, R., & Hassan, Y.
(2018).
Distributed wall temperature measurements in a scaled water-cooled RCCs. Transactions of the American Nuclear Society.
146-148.
-
Goth, N., White, L., Headley, W., Nguyen, D. T., Vaghetto, R., & Hassan, Y. A.
(2018).
High resolution transverse plane PIV measurements of a 61-pin LMFBR fuel bundle. Transactions of the American Nuclear Society.
129-132.
-
Quintanar, N., Nguyen, T., Vaghetto, R., & Hassan, Y.
(2018).
Particle image velocimetry (PIV) measurements in 1/23 scaled water reactor cavity cooling system (WRCCS). AISTech - Iron and Steel Technology Conference Proceedings.
71-74.
-
Quintanar, N., Nguyen, T., Vaghetto, R., & Hassan, Y.
(2018).
Particle image velocimetry (PIV) measurements in 1/23 scaled water reactor cavity cooling system (WRCCS). Transactions of the American Nuclear Society.
71-74.
-
Goth, N., Jones, P., Nguyen, D. T., Vaghetto, R., Hassan, Y. A., Obabko, A., Merzari, E., & Fischer, P. F.
(2017).
Comparison of experimental and simulation results on interior subchannel of a 61-pin wire-wrapped hexagonal fuel bundle
-
Kappes, E., Yang, S. R., Vaghetto, R., Nguyen, T., & Hassan, Y. A.
(2017).
Experimental investigation of depressurization characteristics on the 1/28 scaled simplified HTGR reactor building Model
-
Vaghetto, R., Kee, E., Crook, T., & Hassan, Y.
(2017).
Full risk-informed resolution of the GSI-191: Simulations of loca scenarios using RELAP5-3D and MELCOR. 703-710.
-
Holler, D., Vaghetto, R., & Hassan, Y.
(2017).
New plenum design for a reactor cavity cooling system experimental apparatus. Transactions of the American Nuclear Society.
104-107.
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Bui, H., Sakurahara, T., Cheng, W. C., Crook, T., Vaghetto, R., Wortman, M., ... Moiseytseva, V.
(2017).
Protective systems: An application of regulatory guidance for ECCS sump performance. 693-702.
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Vanni, A., Vaghetto, R., & Hassan, Y.
(2017).
RELAP5-3D sensitivity analysis of ECCS pumps' source conditions during a core blockage following a LB-LOCA in hot leg. Transactions of the American Nuclear Society.
1561-1564.
-
Quintanar, N., Yang, S., White, L., Vaghetto, R., & Hassan, Y.
(2017).
Temperature distribution in a scaled 9 riser water reactor cavity cooling system (WRCCS). Transactions of the American Nuclear Society.
1542-1545.
-
Goth, N., Jones, P., Lee, S., Nguyen, D. T., Vaghetto, R., & Hassan, Y. A.
(2017).
Time-resolved PIV/PTV measurements on interior subchannels of a wire-wrapped 61-pin hexagonal fuel bundle. Transactions of the American Nuclear Society.
1318-1321.
-
Goth, N., Jones, P., Childs, M., Lee, S., Nguyen, D., Vaghetto, R., & Hassan, Y.
(2016).
Pressure Measurements in a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle
-
Goth, N., Jones, P., Lee, S., Nguyen, D., Vaghetto, R., Hassan, Y., & Leavitt, J.
(2016).
Velocity and Pressure Measurements in a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle
-
Childs, M., Kuffel, L., Vaghetto, R., & Hassan, Y.
(2016).
Development of a measurement technique of boric acid concentration in high concentrated aqueous solutions. 1528-1532.
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Yang, S. R., Silberberg, M., Fullerton, C., Nguyen, T., Vaghetto, R., & Hassan, Y.
(2016).
Experimental study on a simplified facility of HTGR Reactor building response to depressurization accidental scenarios. 605-612.
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Vaghetto, R., Goth, N., Childs, M., Jones, P., Lee, S., Nguyen, D. T., & Hassan, Y. A.
(2016).
Flow field and pressure measurements in a 61-pin wire-wrapped bundle. Transactions of the American Nuclear Society.
1474-1477.
-
Goth, N., Childs, M., Jones, P., Lee, S., Nguyen, D. T., Vaghetto, R., & Hassan, Y. A.
(2016).
Particle image velocimetry measurements in a wire-wrapped 61-pin hexagonal fuel bundle. Transactions of the American Nuclear Society.
1478-1481.
-
Crook, T., Vaghetto, R., Vanni, A., & Hassan, Y. A.
(2016).
Sensitivity study of PWR upper vessel flow and phenomena using RELAP5-3D. Transactions of the American Nuclear Society.
985-988.
-
Lee, S., Kyriakopoulos, V., Abdulsattar, S., Vaghetto, R., Hassan, Y. A., & Leavitt, J.
(2016).
Sensitivity tests of aluminum precipitate preparation methods on head loss through debris beds on a sump screen. Transactions of the American Nuclear Society.
1531-1534.
-
Beeny, B., Vaghetto, R., Vierow, K., & Hassan, Y. A.
(2015).
A sensitivity study supporting comparative analysis of MELCOR and GOTHIC large dry pressurized water reactor containment models. 6998-7010.
-
Crook, T., Vaghetto, R., & Hassan, Y. A.
(2015).
Effects of manual operation during a loss-of-coolant accident with pump unavailability. Transactions of the American Nuclear Society.
555-558.
-
Yang, S., Kyriakopoulos, V., Lee, S., Vaghetto, R., & Hassan, Y. A.
(2015).
Experimental investigation of approach velocity effect on the fibrous debris penetration through a containment sump strainer for generic safety issue 191. Transactions of the American Nuclear Society.
1463-1466.
-
Vaghctto, R., Lee, S., Kee, E., & Ahassan, Y.
(2015).
Experimental observations of boric acid precipitation scenarios. 5263-5274.
-
Beeny, B., Vaghetto, R., Vierow, K., & Hassan, Y. A.
(2015).
MELCOR and GOTHIC analyses of a large dry pressurized water reactor containment to support resolution of GSI-191. 6983-6997.
-
Childs, M., Jones, P., Vaghetto, R., & Hassan, Y. A.
(2015).
Measurements of boric acid concentration in pasTa experimental facility. Transactions of the American Nuclear Society.
1489-1492.
-
Lee, S., Vaghetto, R., Lim, J. G., Kappes, M. J., & Hassan, Y. A.
(2015).
The effect of electric potential on fibrous debris bypass through a containment sump strainer. 5317-5326.
-
Crook, T., Vaghetto, R., Vanni, A., & Hassan, Y. A.
(2014).
Sensitivity Analysis of a PWR Response During a Loss of Coolant Accident Under a Hypothetical Core Blockage Scenario Using RELAP5-3D. v005t17a073-v005t17a073.
-
Vaghetto, R., Franklin, A., Vanni, A., & Hassan, Y. A.
(2014).
Sensitivity Analysis of the Response of PWR Containment During a Loss of Coolant Accident Using RELAP5-3D and MELCOR. v02bt09a062-v02bt09a062.
-
Lee, S., Hassan, Y. A., Vaghetto, R., Abdulsattar, S., & Kappes, M.
(2014).
Water Chemistry Sensitivity on Fibrous Debris Bypass Through a Containment Sump Strainer. v02bt09a055-v02bt09a055.
-
Lee, S., Vaghetto, R., Abdulsattar, S., Kappes, M., & Hassan, Y. A.
(2014).
Effects of pH and electrical conductivity on the quantity of fibrous debris bypass through a containment sump strainer. Transactions of the American Nuclear Society.
645-648.
-
Crook, T., Vaghetto, R., Vanni, A., & Hassan, Y. A.
(2014).
Emergency core cooling system sensitivity analysis for a four-loop pressurized water reactor with three independent injection trains. Transactions of the American Nuclear Society.
1535-1538.
-
Vaghetto, R., Vanni, A., Franklin, A., & Hassan, Y. A.
(2014).
Sensitivity analysis of the pressure response of a typical large, dry containment during a double-ended guillotine break LOCA using RELAP5-3D and MELCOR. Transactions of the American Nuclear Society.
701-705.
-
Lee, S., Vaghetto, R., & Hassan, Y. A.
(2013).
Measurement of water chemistry sensitivity on NUKON fibrous debris penetration through a sump strainer. Transactions of the American Nuclear Society.
1935-1938.
-
Vaghetto, R., Kee, E., & Hassan, Y. A.
(2013).
RELAP5-3D simulation of core flow paths during a hypothetical debris-generated core blockage scenario. Transactions of the American Nuclear Society.
1914-1917.
-
Mohaghegh, Z., Kee, E., Reihani, S. A., Kazemi, R., Johnson, D., Grantom, R., ... Blossom, S.
(2013).
Risk-informed resolution of Generic Safety Issue 191. 2458-2471.
-
Vaghetto, R., Beeny, B. A., Hassan, Y. A., & Vierow, K.
(2013).
Sensitivity analysis of a typical large, dry containment response during a loss of coolant accident using RELAP5-3D and MELCOR. Transactions of the American Nuclear Society.
970-973.
-
Vaghetto, R., Franklin, A., & Hassan, Y. A.
(2013).
Sensitivity study of hypothetical debris-generated core blockage scenarios. Transactions of the American Nuclear Society.
1789-1792.
-
Vaghetto, R., Lee, S., & Hassan, Y. A.
(2012).
Analyis of the steady-state phase of the reactor cavity cooling system experimental facility. 82-91.
-
Vaghetto, R., Beeny, B. A., Hassan, Y. A., & Vierow, K.
(2012).
Analysis of long-term cooling of a LOCA by coupling RELAP5-3D and MELCOR. 162-167.
-
Vaghetto, R., Beeny, B. A., Hassan, Y. A., & Vierow, K.
(2012).
Analysis of long-term cooling of a LOCA by coupling RELAP5-3D and MELCOR. Transactions of the American Nuclear Society.
1339-1343.
-
Lee, S., Abdulsattar, S., Vaghetto, R., & Hassan, Y. A.
(2012).
Experimental study of fibrous debris head loss through sump strainer. 282-286.
-
Vaghetto, R., Huali, W., & Hassan, Y. A.
(2012).
RELAP5-3D simulations of the reactor cavity cooling system experimental facility. Transactions of the American Nuclear Society.
979-981.
-
Vaghetto, R., Lee, S., & Hassan, Y. A.
(2012).
Reactor Cavity Cooling System Facility Shakedown and RELAP5-3D Model Validation. 775-782.
-
Rodriguez, O. A., Vaghetto, R., & Hassan, Y. A.
(2012).
Sensitivity Study of the South Texas Project Power Plant Steady-State Simulations Using RELAP5-3D Coupled With Dakota. 595-602.
-
Wei, H. C., Vaghetto, R., & Hassan, Y. A.
(2011).
CFD simulation for a reactor cavity cooling system of the very high temperature reactors. Transactions of the American Nuclear Society.
938-939.
-
Vaghetto, R., & Hassan, Y. A.
(2011).
Scaling the NGNP reactor cavity cooling system. Transactions of the American Nuclear Society.
1023-1024.
-
Vaghetto, R., & Hassan, Y. A.
(2011).
ANALYSIS OF THE THERMOHYDRAULIC BEHAVIOR OF THE NEW TEXAS A&M RCCS EXPERMINENTAL FACILITY USING RELAP5-3D. The Proceedings of the International Conference on Nuclear Engineering (ICONE).
_icone1943-_icone1943.
-
Capone, L., Vaghetto, R., & Hassan, Y.
(2010).
Graphite dispersion effects experimental analysis for a Reactor Cavity Cooling System (RCCS). Transactions of the American Nuclear Society.
1015-1020.
-
Yang, S., Kyriakopoulos, V., Lee, S., Vaghetto, R., & Hassan, Y.
Development of Thermal Hydraulic Simulation Models for TAMU Water-Cooled RCCS
-
Orea, D., Chavez, R., Nguyen, D. T., Vaghetto, R., Anand, N. K., Hassan, Y. A., & Sabharwall, P.
(2021).
PARTICLE DEPOSITION STUDY IN A HORIZONTAL SQUARE CHANNEL USING HIGH-RESOLUTION IMAGING. EPJ Web of Conferences.
10011-10011.
-
patent
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Shao, L., Hassan, Y., Vaghetto, R., Frost, H., & Parker, T.
(2021).
Thorium Molten Salt System Using Internally Generated Proton-Induced Neutrons
-
Frost, H., Parker, T. D., Vaghetto, R., Hassan, Y., & Shao, L.
(2020).
Proton source thorium molten salt assembly for energy generation
-
Vaghetto, R., Frost, H., Hassan, Y., Shao, L., & Parker, T. D.
(2020).
Thorium fuel rod structure and assembly
-
Vaghetto, R., Frost, H., Hassan, Y., Shao, L., & Parker, T.
(2020).
Thorium fuel rod structure and assembly
-
Vaghetto, R., Frost, H., Hassan, Y., Shao, L., & Parker, T.
(2020).
Thorium fuel rod structure and assembly
-
Frost, H., Parker, T., Vaghetto, R., Hassan, Y., & Shao, L.
(2020).
Thorium molten salt assembly for energy generation
-
Frost, H., Parker, T., Vaghetto, R., Hassan, Y., & Shao, L.
(2020).
Thorium molten salt assembly for energy generation including solid Thorium rods
-
Frost, H., Parker, T., Vaghetto, R., Hassan, Y., & Shao, L.
(2020).
Thorium molten salt system for energy generation
-
Shao, L., Hassan, Y., Vaghetto, R., Frost, H., & Parker, T.
(2021).
Thorium Molten Salt System Using Internally Generated Proton-Induced Neutrons
Research
principal investigator on
- High Resolution Temperature and Flow Measurements in Wire-Wrapped Fuel Assemblies awarded by United States Department of Energy - (Washington D.C., District of Columbia, United States) 2017 - 2020
- An Experimental Study of Design and Performance for the Water-based Reactor Cavity Cooling System awarded by United States Department of Energy - (Washington D.C., District of Columbia, United States) 2016 - 2019
co-principal investigator on
Teaching
teaching activities
- NUEN491 Hnr-research Instructor
- NUEN623 Nucl Heat Trans Fluids Instructor
- NUEN685 Directed Studies Instructor
- NUEN691 Research Instructor
- NUEN691 Research Instructor
Background
education and training
- Ph.D. in Nuclear Engineering, Texas A&M University - (College Station, Texas, United States) 2013
- M.S. in Nuclear Engineering, Texas A&M University - (College Station, Texas, United States) 2011
- Nuc.E. in Nuclear Engineering, University of Palermo - (Palermo, Italy) 2000
Contact
first name
- Rodolfo
has last name
- Vaghetto
mailing address
-
Texas A&M Engineering Experiment Station
Nuclear Engineering
3133 TAMUS
College Station, TX 77843-3133
USA
Other
- r.vaghetto@tamu.edu