Faculty Profile

Caleb Brooks

Nuclear, Plasma, and Radiological Engineering
Caleb Brooks
Caleb Brooks
Assistant Professor
(217) 265-0519

Primary Research Area

  • Nuclear Power

Education

  • Ph.D., School of Nuclear Engineering, Purdue University, 2014
  • M.S., School of Nuclear Engineering, Purdue University, 2012
  • B.S., School of Nuclear Engineering, Purdue University, 2008

Academic Positions

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

For more information

Resident Instruction

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

Research Interests

  • Experimental two-phase flow and heat transfer
  • Nuclear reactor thermal hydraulics
  • Computational fluid dynamics code validation
  • Research and development of small modular reactors
  • Modeling and development of safety analysis codes

Research Areas

  • Advanced Reactor Designs
  • Interfacial Area Transport
  • Nuclear Power
  • Reactor Thermal-Hydraulics
  • Reactor Transient and Accident Analysis
  • Two‐Phase Flow and Heat Transfer

Selected Articles in Journals

Articles in Conference Proceedings

  • 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
  • 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), Xi￿an, 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), Xi￿an, 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), Xi￿an, China,September 3 - 8, 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.
  • 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.
  • Guojun, H., Kozlowski, T., Brooks, C.S., 2015. Uncertainty quantification of TRACE sucbooled boiling model using BFBT experiments, The 16th International Topical Meeting of Reactor Thermal Hydraulics (NURETH-16), Chicago, IL, USA, August 30-September 4.
  • Brooks, C.S., Lietwiler, C.D., Fullmer, W.D., 2015. 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.
  • Sharma, S.L., Brooks, C.S., Schlegel, J., Hibiki, T., Ishii, M., Buchanan, J.R., 2015. 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.
  • Brooks, C.S., Hibiki, T., Ishii, M., 2015. 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.
  • Shi, S., Brooks, C.S., Eoh, J., Ishii, M., 2014. Pressurized startup transient analyses for the BWR-type NMR-50, American Nuclear Society Winter Meeting, Anaheim, CA, USA, November 9-13.
  • Brooks, C.S., Silin, N., Hibiki, T., Ishii, M., 2013. 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.
  • Brooks, C.S., Ozar, B., Hibiki, T., Ishii, M., 2012. 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.
  • Brooks, C.S., Liu, Y., Hibiki, T., Ishii, M., 2012. Void fraction covariance in two-phase flows￿, Proceedings of the 20th International Conference on Nuclear Engineering, Anaheim, CA, USA, July 30-August 3.
  • Chen, S.W., Brooks, C.S., Hibiki, T., Ishii, M., Mori, M., Macke, C., 2012. 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.
  • Ishii, M., Brooks, C.S., Ozar, B., Hibiki, T., 2012. 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.
  • Ozar, B., Brooks, C.S., Hibiki, T., Ishii, M., 2011. 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.
  • Hibiki, T., Ishii, M., Brooks, C.S., 2010. Overview of interfacial area transport data development, American Nuclear Society Winter Meeting, Las Vegas, NV, USA, November 7-11.
  • Hibiki, T., Ishii, M., Liu, Y., Brooks, C.S., 2010. Overview of interfacial area transport equation development, American Nuclear Society Winter Meeting, Las Vegas, NV, USA, November 7-11.

Reports

  • Brooks, C.S., Kozlowski, T., Zou, L., Golchert, B., Borowiec, K., Wang, C., Ooi, Z.J., Kumar, V., "Validation of RELAP-7 for Forced Convective and Natural Circulation Reactor Flows: Task 1.1 Synthesis of existing forced convective two-phase flow datasets for validation of RELAP7" Technical Report, Project ID: DOE-16-10630, Milestone ID: M2NU-16-IL-UIUC-030401-062.
  • Ishii, M., Hibiki, T., Yang, W.S., Schlegel, J.P., Wu, Z., Shi, S., Y.C., Lin, Eoh, J.H., Brooks, C.S., Clark, C. ￿Investigation of natural circulation instability and transients in passively safe modular reactors￿ Purdue Technical Report PU/NE-13-10, 2013
  • Brooks, C.S., Hibiki, T., Ishii, M. ￿Two-group Drift Flux Model￿ Purdue Technical Report PU/NE-12-04, 2012
  • Brooks, C.S., Hibiki, T., Ishii, M. ￿Foundation and Treatment of the Four-field Two-fluid Model in Annular Flows￿ Purdue Technical Report PU/NE-12-26, 2012
  • Ishii, M., Hibiki, T., Liu, Y., Sharma, S.L., Lee, D.Y., Brooks, C.S. ￿Implementation of interfacial area transport equation into 3-D CFD code, task 1: spatial benchmarking of interfacial area transport equation, subtask 1f: Additional Diffusion Force Model Development and Near Wall Treatment of Two-Fluid Model.￿ Purdue Technical Report PU/NE-12-20, 2012
  • Ishii, M., Hibiki, T., Liu, Y., Sharma, S.L., Lee, D.Y., Brooks, C.S. ￿Implementation of interfacial area transport equation into 3-D CFD code, task 1: spatial benchmarking of interfacial area transport equation, subtask 1f: Systematic Benchmarking of the Two-group IATE with Two Gas Momentum Equations for Uniform and Non-Uniform Inlet Boundary Conditions.￿ Purdue Technical Report PU/NE-12-07, 2012
  • Brooks, C.S., Hibiki, T., Ishii, M. ￿Interfacial drag force in one-dimensional two-fluid model￿ Purdue Technical Report PU/NE-11-07, 2011
  • Ishii, M., Hibiki, T., Ozar, B., Brooks, C.S. ￿Data Report for Steam-Water Boiling Flow in a Vertical Annulus￿ Purdue Technical Report PU/NE-09-57, 2009
  • Ishii, M., Hibiki, T., Ozar, B., Brooks, C.S. ￿Interfacial Area Transport with Boiling and Condensation in an Annulus￿ Purdue Technical Report PU/NE-09-62, 2009
  • Ishii, M., Liu, Y., Brooks, C.S. ￿Scaling Analysis of Air Entrainment Tests￿ Purdue Technical Report PU/NE-09-66, 2009
  • Ishii, M., Brooks, C.S., Schlegel, J.P. ￿PWROG Air Entrainment Tests Data Report for 4 Inch Heated Test Section￿ Purdue Technical Report PU/NE-09-63, 2009
  • Ishii, M., Brooks, C.S., Schlegel, J.P., Chen, S.W. ￿PWROG Air Entrainment Tests Data Report for 4 Inch Test Section￿ Purdue Technical Report PU/NE-09-56, 2009
  • Ishii, M., Brooks, C.S., Schlegel, J.P. ￿Air Entrainment in Nuclear Safety System Suction Piping: Test Procedures and Shakedown Test Planning for 4 inch Tests￿ Purdue Technical Report PU/NE-09-55, 2009
  • Ishii, M., Brooks, C.S., Paranjape, S.S. ￿Air Entrainment in Nuclear Safety System Suction Piping: Design Drawings, Equipment and Instrument Specifications, and Test Plan for 4 inch Tests￿ Purdue Technical Report PU/NE-09-54, 2009
  • Ishii, M., Brooks, C.S., Paranjape, S.S., Ozar, B. ￿PWROG Air Entrainment Tests Data Report for 12 Inch Test Section￿ Purdue Technical Report PU/NE-09-53, 2009
  • Ishii, M., Liu, Y., Brooks, C.S. ￿Scaling Analysis and Model Development of Air Entrainment before the ECCS Pump Suction Section￿ Purdue Technical Report PU/NE-09-52, 2009
  • Ishii, M., Brooks, C.S., Sawant, P.H., Paranjape, S.S. ￿Air entrainment in the flow of an emergency core cooling suction: Design Drawings, Equipment and Instrumentation Specifications, and Test Plan￿ Purdue Technical Report PU/NE-08-31, 2008
  • Ishii, M., Brooks, C.S., Sawant, P.H., Paranjape, S.S. "Air entrainment in the flow of an emergency core cooling suction: Test Procedures and Shake-down Test Planning" Purdue Technical Report PU/NE-08-30, 2008

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

  • 2017 AESJ Shorei-sho Award (society-wide 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)