selected publications academic article 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. 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. 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. 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. 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. 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. 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. 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. 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. 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. 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. 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. 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. 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. 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. 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. 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. 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. 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. 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. 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. Capone, L., Hassan, Y. A., & Vaghetto, R. (2011). Reactor cavity cooling system (Rccs) experimental characterization. Nuclear Engineering and Design. 241(12), 4775-4782. conference paper 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 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. 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. 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. 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. 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. Vaghetto, R., Hassan, Y., & Hollrah, B. (2020). VALIDATION OF THE SAM STEADY-STATE MODEL OF THE FAST FLUX TEST FACILITY. 1654-1657. 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 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 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 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 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. 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. 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. Lai, J., Merzari, E., Vaghetto, R., Nguyen, D. T., & Hassan, Y. (2018). Video: Numerical and Experimental Buoyant Mixing 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. 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 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. 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. 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. 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. 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 patent 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
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 Spatiotemporally Resolved Multiscale Measurements of Single- and Multi-Phase Flows Using State-Of-The-Art System of X-ray Tomography and Optical Sensors awarded by United States Department of Energy - (Washington D.C., District of Columbia, United States) 2017 - 2018
teaching activities NUEN491 Hnr-research Instructor NUEN623 Nucl Heat Trans Fluids Instructor NUEN685 Directed Studies Instructor NUEN691 Research Instructor NUEN691 Research Instructor
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
mailing address Texas A&M Engineering Experiment Station Nuclear Engineering 3133 TAMUS College Station, TX 77843-3133 USA