Caleb Brooks

For More Information

• Multiphase Thermo-fluid Dynamics Laboratory
• Illinois Microreactor RD&D Center

Education

• Purdue University, Ph.D., School of Nuclear Engineering, 2014
• Purdue University, B.S., School of Nuclear Engineering, 2008

Academic Positions

• 2020 - present, Associate Professor, University of Illinois, Department of Nuclear, Plasma, and Radiological Engineering
• 2014 - 2020, Assistant Professor, University of Illinois, Department of Nuclear, Plasma, and Radiological Engineering

Resident Instruction

• NPRE 247: Modeling Nuclear Energy System
• NPRE/ME 598: Computational Multi-phase Flow
• NPRE 448: Nuclear System Engineering and Design
• NPRE 511: Nuclear Reactor Heat Transfer

Selected Articles in Journals

• Zhu, L., Ooi, Z.J., Zhang, T., Brooks, C.S., Pan, L., 2023. Identification of flow regimes in boiling flow with clustering algorithms: An interpretable machine-learning perspective, Applied Thermal Engineering, Volume 228, 120493. DOI: 10.1016/j.applthermaleng.2023.120493
• McCord, M., Brooks, C.S., 2023. Experimental Comparison of the Rewet Phenomenon in Transient and Stable Film Boiling in Low Pressure and Low Flow Conditions, International Journal of Heat and Mass Transfer, Volume 209, 124099. DOI: 10.1016/j.ijheatmasstransfer.2023.124099
• Wodrich, L., Lee, A.J.H., Kozlowski, T., Brooks, C.S., 2023. Modeling of an energy diverse embedded grid for microreactor integration, Nuclear Technology, Volume 209 (6), 809-834. DOI: 10.1080/00295450.2022.2161276
• Bottini, J.L., Brooks, C.S., 2023. Interphase and Intergroup Mass Transfer in the Two-Group Two-Fluid Model in Flows with Phase Change, Nuclear Technology, Nuclear Technology, (invited). DOI: 10.1080/00295450.2022.2156244
• Zhang, T., Brooks, C.S., 2023. Stability Tests and Analysis on a Low-pressure Natural Circulation Loop with Flashing Instability, Nuclear Technology, (invited). DOI: 10.1080/00295450.2022.2151823
• Chen, J., Brooks, C.S., 2023. Simulation of the Axial-Flow Centrifugal Bubble Separator for Liquid-Fueled Molten Salt Reactors using Eulerian Two-Fluid Model, Nuclear Science and Engineering, Volume 197 (5), 886-906 (invited). DOI: 10.1080/00295639.2022.2103347
• Chapman, A., Shigetomi, Y., Karmaker, S.C., Saha, B., Brooks, C.S., 2022. Cultural and demographic energy system awareness and preference: Implications for future energy system design in the United States, Energy Economics, Vol 112, 106141. (invited) DOI: 10.1016/j.eneco.2022.106141
• Zhu, L., Bottini, J.L., Brooks, C.S., Zhang, L., 2022. Comparison of intergroup mass transfer coefficient correlations in two-group IATE for subcooled boiling flow, Frontiers in Energy Research, Vol 10, 890795. DOI: 10.3389/fenrg.2022.890795
• Ooi, Z.J., Zhu, L., Bottini, J.L., Brooks, C.S., 2022. Identification of flow regimes in boiling flows in a vertical annulus channel with machine learning techniques, International Journal of Heat and Mass Transfer, Vol 185, 122430. DOI: 10.1016/j.ijheatmasstransfer.2021.122439
• Zhu, L., Zhang, T., Bottini, J.L., Brooks, C.S., 2022. Two-dimensional quantitative study of boiling flow evolution in vertical inner-heated annulus channel, International Journal of Heat and Mass Transfer, 122190, DOI: https://doi.org/10.1016/j.ijheatmasstransfer.2021.122190
• Chapman, A., Shigetomi, Y., Karmaker, S.C., Saha, B.B., Huff, K.D., Brooks, C.S., Stubbins, J., 2021. The Role of Culture Toward Demographics, Energy System Preferences and Outcomes, Energy Research and Social Science , Volume 80, 102231, DOI: https://doi.org/10.1016/j.erss.2021.102231
• Ooi, Z.J., Brooks, C.S., 2021. Two-group Interfacial Area Transport Equation Coupled with Void Transport Equation in Adiabatic Steam Water Flows, International Journal of Heat and Mass Transfer, Volume 177, 121531, DOI: https://doi.org/10.1016/j.ijheatmasstransfer.2021.121531
• Zhang, T., Smith, E.R., Brooks, C.S., Fanning, T.H., 2021. Validation of SAS4A/SASSYS-1 for Predicting Steady-state Single-phase Natural Circulation, Nuclear Engineering and Design, Volume 377, 111149, DOI: https://doi.org/10.1016/j.nucengdes.2021.111149
• Ooi, Z.J., Brooks, C.S., 2021. Beyond time-averaged measurement of bubble parameters in steam-water flows with conductivity probes, International Journal of Multiphase Flow, Volume 138, 103594, DOI: https://doi.org/10.1016/j.ijmultiphaseflow.2021.103594
• Zhu, L., Ooi, Z.J., Brooks, C.S., Shan, J., 2021. Modeling sensitivity in prediction of interfacial area concentration in boiling flow, Progress in Nuclear Energy, 133, 103638. DOI: https://doi.org/10.1016/j.pnucene.2021.103638
• Chen, J., Brooks, C.S., 2021. Experiments and CFD Simulation of Mass Transfer and Hydrodynamics in a Cylindrical Bubble Column, Chemical Engineering Science, 234, 116435. DOI: https://doi.org/10.1016/j.ces.2020.116435
• Zhang, T., Brooks, C.S., 2021. Linear stability analysis of flashing instability based on the homogeneous equilibrium model, Nuclear Engineering and Design, 373, 110994. DOI: 10.1016/j.nucengdes.2020.110994
• Zhu, L., Ooi, Z.J., Bottini, J.L., Brooks, C.S., Shan, J., 2020. Bubble diameter distribution and intergroup mass transfer coefficient in flows with phase change, International Journal of Heat and Mass Transfer, 163, 120456. DOI: 10.1016/j.ijheatmasstransfer.2020.120456
• Ooi, Z.J., Zhang, T., Brooks, C.S., 2020. Experimental dataset with high-speed visualization for vertical upward steam-water flow with transition from annulus to circular channel, International Journal of Heat and Mass Transfer, 161, 120281, DOI: 10.1016/j.ijheatmasstransfer.2020.120281
• Miernicki, E.A, Heald, A.L., Huff, K.D., Brooks, C.S., Margenot, A.J., 2020. Nuclear waste heat use in agriculture: history and opportunities, Journal of Cleaner Production, 267, 121918, DOI: 10.1016/j.jclepro.2020.121918
• Bottini, J.L., Zhu, L., Ooi, Z.J., Zhang, T., Brooks, C.S., 2020. Experimental study of boiling flow in a vertical Heated Annulus with local two-phase measurements and visualization, International Journal of Heat and Mass Transfer, 155, 119712, DOI: 10.1016/j.ijheatmasstransfer.2020.119712
• Kumar, V., Brooks, C.S., 2020, Benchmark of interfacial area concentration approaches for the two-fluid model in gas-dispersed condensing flow, Progress in Nuclear Energy, 124, 103329, DOI: 10.1016/j.pnucene.2020.103329
• Borowiec, K., Kozlowski, T., Brooks, C.S., 2020. Validation and uncertainty quantification for two-phase natural circulation flows using TRACE code, Nuclear Science and Engineering, Vol. 194, 737-747. DOU:10.1080/00295639.2020.1713671
• Ooi, Z.J., Kumar, V., Brooks, C.S., 2020. Validation of the Interfacial Area Transport Equation Coupled with the Void Transport Equation for Prediction of Flashing Flows, Nuclear Science and Engineering, Vol. 194, 598-619. DOI: 10.1080/00295639.2020.1732123
• Zhang, T., Ooi, Z.J., Skrzpek, M., Brooks, C.S., 2020. A multi-dimensional dataset for two-phase instability in low pressure natural circulation based on direct transient local measurement, International Journal of Heat and Mass Transfer, Vol 151, 119447. DOI:10.1016/j.ijheatmasstransfer.2020.119447
• Ooi, Z.J., Kumar, V., Brooks, C.S., 2019. Experimental database of two-phase natural circulation with local measurements, Progress in Nuclear Energy, Vol. 116, 124-136. DOI:10.1016/j.pnucene.2019.04.003
• Kumar, V., Ooi, Z.J., Brooks, C.S., 2019. Forced convective steam-water experimental database in a vertical annulus with local measurements, International Journal of Heat and Mass Transfer, Vol 137, 216-228. DOI:10.1016/j.ijheatmasstransfer.2019.03.099
• Colgan, N., Bottini, J.L., Ooi, Z.J., Brooks, C.S., 2019. Experimental study of wall nucleation characteristics in flow boiling under subatmospheric pressures in a vertical square channel, International Journal of Heat and Mass Transfer, Vol. 134, 58-68. DOI:10.1016/j.ijheatmasstransfer.2018.12.153
• Ju, P., Liu, Y., Brooks, C.S., Ishii, M., 2019. Prediction of Interfacial Shear Stress of Vertical Upward Adiabatic Annular Flow in Pipes, International Journal of Heat and Mass Transfer, Vol 133, 500-509. DOI:10.1016/j.ijheatmasstransfer.2018.12.057
• Colgan, N., Bottini, J.L., Martinez-Cuenca, R., Brooks, C.S., 2019. Experimental study of critical heat flux in flow boiling under subatmospheric pressure in a vertical square channel, International Journal of Heat and Mass Transfer, Vol 130, 514-522. DOI:10.1016/j.ijheatmasstransfer.2018.10.082
• Bottini, J.L., Kumar, V., Hammouti, S., Ruzic, D., Brooks, C.S., 2018. Influence of wettability due to laser-texturing on critical heat flux in vertical flow boiling, International Journal of Heat and Mass Transfer, Vol 127, 806-817. DOI:10.1016/j.ijheatmasstransfer.2018.06.113
• Kumar, V., Brooks, C.S., 2018. Inter-group mass transfer modeling in the two-group two-fluid model with interfacial area transport equation in condensing flow, International Journal of Heat and Mass Transfer, Vol 119, 688-703. DOI:10.1016/j.ijheatmasstransfer.2017.11.087.
• Ooi, Z.J., Kumar, V., Bottini, J.L., Brooks, C.S., 2018. Experimental investigation of variability in bubble departure characteristics between nucleation sites in subcooled boiling flow, International Journal of Heat and Mass Transfer, Vol 118, 327-339. DOI:10.1016/j.ijheatmasstransfer.2017.10.116
• Kumar, V., Brooks, C.S., 2017. Validation and model sensitivity of the interfacial area transport equation in condensing flows, International Journal of Heat and Mass Transfer, Vol 113, 647-661. DOI:10.1016/j.ijheatmasstransfer.2017.05.118
• Sharma, S.L., Hibiki, T., Ishii, M., Brooks, C.S., Schlegel, J.P., Liu, Y., Buchanan Jr., J.R., 2017. Turbulence-induced Bubble Collision Modeling and Validation in Adiabatic Two-phase Flow, Nuclear Engineering and Design, Vol 312, 399-409. DOI:10.1016/j.nucengdes.2016.05.006
• Fullmer, W.D., Kumar, V., Brooks, C.S., 2016. Validation of RELAP5/MOD3.3 for Subcooled Boiling, Flashing and Condensation in a Vertical Annulus, Progress in Nuclear Energy, Vol 93, 205-217 DOI: 10.1016/j.pnucene.2016.08.013
• Dandekar, A.V., Brooks, C.S., 2016. Modeling of Void Fraction Covariance in Two-phase Flows with Phase Change, International Journal of Heat and Mass Transfer, Vol 100, 231-242. DOI:10.1016/j.ijheatmasstransfer.2016.04.066
• Brooks, C.S. and Hibiki, T., 2016. Modeling and validation of interfacial area transport equation in subcooled boiling flow, Journal of Nuclear Science and Technology, Vol 53 (8), 1192-1204. DOI: 10.1080/00223131.2015.1096852
• Shi, S., Schlegel, J.P., Brooks, C.S., Lin, Y-C., Eoh, J., Liu, Z., Zhu, Q., Liu, Y., Hibiki, T., Ishii, M., 2015. Experimental investigation of natural circulation instability in a BWR-type small modular reactor, Progress in Nuclear Energy, Vol 85, 96-107. DOI:10.1016/j.pnucene.2015.06.014
• Ju, P., Brooks, C.S., Ishii, M., Liu, Y., Hibiki, T., 2015. Film thickness of vertical upward co-current adiabatic flow in pipes, International Journal of Heat and Mass Transfer, Vol 89, 985-995. DOI:10.1016/j.ijheatmasstransfer.2015.06.002
• Shi, S., Wu, Z., Liu, Z., Schlegel, J.P., Brooks, C.S., Eoh, J., Yan, Y., Liu, Y., Yang, W.S., Ishii, M., 2015. Experimental study of natural circulation instability with void reactivity feedback during startup transients for a BWR-type SMR, Progress in Nuclear Energy, 83, 73-81. DOI:10.1016/j.pnucene.2015.03.003
• Brooks, C.S. and Hibiki, T., 2015. Wall Nucleation Modeling in Subcooled Boiling Flow, International Journal of Heat and Mass Transfer, Vol 86., 183-196, DOI: 10.1016/j.ijheatmasstransfer.2015.03.005.
• Brooks, C.S., Silin, N., Hibiki, T., Ishii, M., 2015. Experimental investigation of wall nucleation characteristics in flow boiling, Journal of Heat Transfer, Vol 137 (5), DOI: 10.1115/1.4029593.
• Martinez, R., Brooks, C.S., Julia, J.E., Hibiki, T., Ishii, M., 2015. Stochastic nature of wall nucleation and its impact on the time averaged boundary condition, Journal of Heat Transfer, Vol 137 (2), DOI:10.1115/1.4028975.
• Brooks, C.S., Ozar, B., Hibiki, T., Ishii, M., 2014. Interfacial area transport of subcooled boiling flow in a vertical annulus, Nuclear Engineering and Design, Vol 269, 152-163, DOI:10.1016/j.nucengdes.2013.04.041.
• Brooks, C.S., Liu, Y., Hibiki, T., Ishii, M., 2014. Effect of void fraction covariance on relative velocity in gas-dispersed two-phase flow, Progress in Nuclear Energy, Vol 70, 209-220, DOI:10.1016/j.pnucene.2013.10.006.
• Ozar, B, Brooks, C.S., Hibiki, T., Ishii, M., 2013. Interfacial area transport of vertical upward steam-water two-phase flow in an annular channel at elevated pressures, International Journal of Heat and Mass Transfer, Vol 57, 504-518, DOI:10.1016/j.ijheatmasstransfer.2012.10.059.
• Ozar, B, Brooks, C.S., Euh, D.J, Hibiki, T., Ishii, M., 2013. Investigation of one-dimensional interfacial area transport for vertical upward air-water two-phase flow in an annular channel at elevated pressures, Nuclear Engineering and Design, Vol 263, 362-379, DOI:10.1016/j.nucengdes.2013.05.018.
• Brooks, C.S., Ozar, B., Hibiki, T., Ishii, M., 2012. Two-group Drift-flux Model in Boiling Flow, International Journal of Heat and Mass Transfer, Vol 55, 6121-6129, DOI:10.1016/j.pnucene.2012.07.001.
• Brooks, C.S., Hibiki, T., Ishii, M., 2012. Interfacial Drag Force in One-dimensional Two-fluid Model, Progress in Nuclear Energy, Vol 61, 57-68, DOI:10.1016/j.pnucene.2012.07.001.
• Brooks, C.S., Paranjape, S.S., Ozar, B., Hibiki, T., Ishii, M., 2012. Two-group Drift-flux Model for Closure of the Modified Two-fluid Model, International Journal of Heat and Fluid Flow, Vol 37, 196-208, DOI:10.1016/j.ijheatfluidflow.2012.04.002.

Articles in Conference Proceedings

• Novak, A.J., Chaube, A., Shaver, D.R., Brooks, C.S. Validation of NekRS-MOOSE Conjugate Heat Transfer Coupling for a 7-Pin Bare Bundle, Proceedings of ANS 2022
• Bottini, J.L., Ooi, Z.J., Brooks, C.S., Trends in vapor generation and intergroup mass transfer in the two-group two fluid model in flows with phase change, Japan-U.S. Seminar on Two-phase Flow Dynamics, Ann Arbor, MI, USA, May 8-11, 2022 (invited).
• McCord, M., Bottini, J. L., and Brooks, C. S., Experimental Comparison of Transient and Stable Film Boiling Minimum Rewet Conditions at Low Pressure and Low Flow Rate, International Topical Meeting on Advances in Thermal Hydraulics, Anaheim, CA, June 12-16, 2022.
• Zhang, T., Brooks, C.S., Stability Tests and Analysis on a Low-pressure Natural Circulation Loop with Flashing Instability, 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH), Brussels, Belgium, March 6-11, 2022 (Best Paper Award).
• Zhu, L., Zhang, T., Ooi, Z.J., Brooks, C.S., Shan, J., Pan, L., Validation of Interfacial Mass Transfer Closures in Drift Flux Model for Condensation Flow, 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH), Brussels, Belgium, March 6-11, 2022.
• Zhu, L., Ooi, Z.J., Zhang, T., Brooks, C.S., Pan, L., Flow Regime Identification for Boiling Flow and Study of Feed-in Information in Unsupervised Machine Learning, 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH), Brussels, Belgium, March 6-11, 2022.
• Bottini, J. L., Brooks, C. S., Modeling Vapor Mass Generation in Vertical Boiling Flow Using the Two-Group Two-Fluid Model, 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH), Brussels, Belgium, March 6-11, 2022.
• Chen, J., Brooks, C.S., Simulation and Analysis of a Prototypical Bubble Separator for Molten Salt Reactor, ANS Winter Meeting, Washington, D.C., November 31-December 3, 2021.
• Lee, A. J. H., Wodrich, L., Brooks, C.S., Kozlowski, T., Modeling Micro-Reactor Benefits to an Existing Campus Microgrid, ANS Winter Meeting, Washington, D.C., November 31-December 3, 2021.
• Zhu, L., Bottini, J.L., Brooks, C.S., Comparison of intergroup mass transfer coefficient correlations in two-group IATE for subcooled boiling flow, ANS Winter Meeting, Chicago, IL, November 16-19, 2020.
• Zhang, T., Brooks, C.S., Linear Stability Analysis of Flashing Instability with Homogeneous Equilibrium Model, ANS Winter Meeting, Chicago, IL, November 16-19, 2020.
• McCord, M.L., Bottini, J.L., Brooks, C.S., Transient measurement of film boiling during cooldown from CHF in vertical flow, ANS Winter Meeting, Chicago, IL, November 16-19, 2020.
• Chen, J., Brooks, C.S., Simulation and analysis of a prototypical xenon removal system, ANS Winter Meeting, Chicago, IL, November 16-19, 2020.
• Chen, J., Brooks, C.S., Experimental study of fluid motion and mass transfer in a cylindrical bubble column, International Topical Meeting on Advances in Thermal Hydraulics, Paris, France, March 31-April 3, 2020.
• Ooi, Z.J., Brooks, C.S., Beyond time-averaged measurements using conductivity probes, International Topical Meeting on Advances in Thermal Hydraulics, Paris, France, March 31-April 3, 2020.
• Zhu, L., Ooi, Z.J., Kumar, V., Brooks, C.S., Current Intergroup Mass Transfer Limitations in the Multi-group Two-fluid Model, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, Oregon, USA, August 18-23, 2019.
• Zhu, L., Kumar, V., Ooi, Z.J., Brooks, C.S., Current Capability of Interfacial Area Transport Equation in Subcooled Boiling, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, Oregon, USA, August 18-23, 2019.
• Zhang, T., Ooi, Z.J., Brooks, C.S., Transient local thermal hydraulics data for two-phase flow instability in natural circulation, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, Oregon, USA, August 18-23, 2019.
• Wang, L., Brooks, C.S., Analysis of wall nucleation modeling for flow boiling in Fluent, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, Oregon, USA, August 18-23, 2019.
• Ooi, Z.J., Kumar, V., Brooks, C.S., Validation of the interfacial area transport equation coupled with the void transport equation for prediction of flashing flows, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, Oregon, USA, August 18-23, 2019.
• Kumar, V., Brooks, C.S., Validation of interfacial area concentration approaches for prediction of gas-dispersed condensing flows, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, Oregon, USA, August 18-23, 2019.
• Chen, J., Brooks, C.S., Experimental study of fluid motion and mass transfer in a cylindrical bubble column, International Topical Meeting on Advances in Thermal Hydraulics, Paris, France, March 31-April 3, 2020.
• Chen, J., Brooks, C.S., CFD Simulation of Xenon removal by Helium sparging in molten salt, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, Oregon, USA, August 18-23, 2019.
• Borowiec, K., Kozlowski, T., Brooks, C.S., Validation and uncertainty quantification for two-phase natural circulation flows using TRACE code, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH), Portland, Oregon, USA, August 18-23, 2019.
• Bottini, J.L., Zhu, L., Ooi, Z.J., Zhang, T., Brooks, C.S., A New Dataset with Local Measurement and Visualization of Subcooled Boiling in an Internally Heated Annulus Channel, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, Oregon, USA, August 18-23, 2019.
• Ooi, Z.J., Kumar, V., Brooks, C.S., Measurement of two-phase natural circulation in a vertical annulus, International Topical Meeting on Advances in Thermal Hydraulics, ANS Winter Meeting, Orlando, FL, November 11-15, 2018.
• Kumar, V., Ooi, Z.J., Brooks, C.S., Measurement of steam-water flow in a vertical annulus, International Topical Meeting on Advances in Thermal Hydraulics, ANS Winter Meeting, Orlando, FL, November 11-15, 2018.
• Bottini, J.L., Hammouti, S., Ruzic, D., Brooks, C.S., Boiling and Critical heat flux on surfaces of modified wettability and roughness, International Topical Meeting on Advances in Thermal Hydraulics, ANS Winter Meeting, Orlando, FL, November 11-15, 2018.
• Bottini, J.L., Kumar, V., Hammouti, S., Ruzic, D., Brooks, C.S., Critical heat flux on laser-textured surface in flow boiling, 3rd Thermal and Fluids Engineering Conference (TFEC), Fort Lauderdale, FL, USA, March 4-7, 2018.
• Colgan, N., Bottini, J.L., Brooks, C.S., Flow boiling at subatmospheric pressure. American Nuclear Society - Nuclear and Emerging Technologies for Space, Las Vegas, NV, February 26 - March 1, 2018.
• Borowiec, K., Wang, C., Kozlowski, T., Brooks, C.S., Uncertainty Quantification for Steady-Steady PSBT Benchmark using Surrogate Models, 2017 ANS Winter Meeting, Washington, DC, October 29 - November 2, 2017
• Zou, L., Zhao, H., Zhang, H., Brooks, C.S., A Revisit to the Hicks Hyperbolic Two-pressure Two-phase Flow Model, The 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 3-8, 2017.
• Ooi, Z.J., Kumar, V., Bottini, J., Brooks, C.S., Experimental Investigation of Variability in Bubble Departure Diameter and Bubble Departure Frequency Between Nucleation Sites, The 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xian, China, September 3 - 8, 2017
• Kumar, V., Brooks, C.S., Validation of the Interfacial Area Transport Equation Coupled with Mass Continuity for Prediction of Condensing Flows, The 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xian, China, September 3 - 8, 2017
• Bottini, J., Kumar, V., Brooks, C.S., Critical Heat Flux Experiments Under Low Flow Conditions in a Vertical Rectangular Channel, The 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xian, China, September 3 - 8, 2017
• Kumar, V., & Brooks, C.S., The two-group two-fluid model with interfacial area transport equation in condensing flow, 2017 Japan-U.S. seminar on Two-Phase flow Dynamics, Hokkaido, Japan, June 22-24, 2017.
• Sharma, S.L., Brooks, C.S., Schlegel, J., Hibiki, T., Ishii, M., Buchanan, J.R., Turbulent induced bubble collision force model development and assessment for adiabatic dispersed air-water two-phase flow with two-fluid model, The 16th International Topical Meeting of Reactor Thermal Hydraulics (NURETH-16), Chicago, IL, USA, August 30-September 4, 2015.
• Guojun, H., Kozlowski, T., Brooks, C.S., Uncertainty quantification of TRACE subcooled boiling model using BFBT experiments, The 16th International Topical Meeting of Reactor Thermal Hydraulics (NURETH-16), Chicago, IL, USA, August 30-September 4, 2015.
• Brooks, C.S., Lietwiler, C.D., Fullmer, W.D., Assessment of RELAP5/MOD3.3 for subcooled boiling, flashing and condensation in a vertical annulus, The 16th International Topical Meeting of Reactor Thermal Hydraulics (NURETH-16), Chicago, IL, USA, August 30-September 4, 2015.
• Brooks, C.S., Hibiki, T., Ishii, M., The Interfacial Area Transport Equation and Boundary Condition Sensitivity in Subcooled Boiling Flow, Japan-U.S. Seminar on Two-phase Flow Dynamics, West Lafayette, IN, May 10-15, 2015.
• Shi, S., Brooks, C.S., Eoh, J., Ishii, M., Pressurized startup transient analyses for the BWR-type NMR-50, American Nuclear Society Winter Meeting, Anaheim, CA, USA, November 9-13, 2014.
• Shi, S., Brooks, C.S., Lin, Y.-C., Schlegel, J.P., Hibiki, T., Ishii, M., Experimental investigation of natural circulation instability in a BWR-type small modular reactor, ASME 2014 Small Modular Reactors Symposium, Washington, DC, USA, April 15-17, 2014.
• Brooks, C.S., Silin, N., Hibiki, T., Ishii, M., Experimental investigation of bubble departure diameter and bubble departure frequency in sub-cooled flow boiling in a vertical annulus, Proceedings of the ASME Summer Heat Transfer Conference, Minneapolis, MN, USA, July 14-19, 2013.
• Chen, S.W., Brooks, C.S., Hibiki, T., Ishii, M., Mori, M., Macke, C., Experiment of adiabatic two-phase flow in an annulus under low-frequency vibration, Proceedings of the 20th International Conference on Nuclear Engineering, Anaheim, CA, USA, July 30-August 3, 2012.
• Brooks, C.S., Ozar, B., Hibiki, T., Ishii, M., Two-group relative velocity in boiling two-phase flow, Proceedings of the 20th International Conference on Nuclear Engineering, Anaheim, CA, USA, July 30-August 3, 2012.
• Brooks, C.S., Liu, Y., Hibiki, T., Ishii, M., Void fraction covariance in two-phase flows, Proceedings of the 20th International Conference on Nuclear Engineering, Anaheim, CA, USA, July 30-August 3, 2012.
• Ishii, M., Brooks, C.S., Ozar, B., Hibiki, T., Interfacial area transport of subcooled boiling flow in a vertical annulus, Japan-U.S. Seminar on Two-phase Flow Dynamics, Tokyo, Japan, June 7-12, 2012.
• Ozar, B., Brooks, C.S., Hibiki, T., Ishii, M. Interfacial area transport of steam-water two-phase flow in a vertical annulus at elevated pressures during sub-cooled boiling, The 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Toronto, Ontario, Canada, September 25-29, 2011.
• Hibiki, T., Ishii, M., Liu, Y., Brooks, C.S., Overview of interfacial area transport equation development, American Nuclear Society Winter Meeting, Las Vegas, NV, USA, November 7-11, 2010.
• Hibiki, T., Ishii, M., Brooks, C.S., Overview of interfacial area transport data development, American Nuclear Society Winter Meeting, Las Vegas, NV, USA, November 7-11, 2010.

Professional Societies

• American Society of Thermal and Fluids Engineers (ASTFE) Member
• American Nuclear Society (ANS) Member
• Atomic Energy Society of Japan (AESJ)
• American Society of Mechanical Engineers (ASME) Member
• Alpha Nu Sigma National Honor Society Member

Honors

• ANS Landis Young Member Engineering Achievement Award (June 2022)
• AESJ Thermal Hydraulics Division Shorei-sho Award (young member research award) (March 2018)
• AESJ Society-wide Shorei-sho Award (young member research award) (March 2017)
• Purdue University College of Engineering Outstanding Research Award (April 2013)
• Purdue University College of Engineering Outstanding Service Award (April 2013)