Caleb Brooks
· Professor and Donald Biggar Willett Faculty ScholarUniversity of Illinois Urbana-Champaign · Statistics and Computer Science
Active 2010–2026
About
Caleb Brooks is a professor and Donald Biggar Willett Faculty Scholar at the University of Illinois Urbana-Champaign, affiliated with the Grainger College of Engineering. He serves as the Director of the Illinois Nuclear Power Institute and holds a courtesy appointment as a WPI Professor at Kyushu University’s International Institute for Carbon-Neutral Energy Research. Brooks earned his Ph.D. and B.S. in Nuclear Engineering from Purdue University in 2014 and 2008, respectively. His research areas include advanced reactor designs, reactor physics, reactor thermal-hydraulics, and two-phase flow and heat transfer. Brooks has contributed to the understanding of nuclear microreactors, energy systems with nuclear reactor coupling, and transient local two-phase flow data analysis. His work involves modeling and simulation of nuclear reactor behavior, interfacial area transport, and the development of computational methods for nuclear energy applications. Brooks has published extensively in journals such as Nuclear Technology, Nuclear Science and Engineering, and Applied Thermal Engineering, among others.
Research topics
- Physics
- Sociology
- Computer Science
- Artificial Intelligence
- Mechanics
- Political Science
- Psychology
- Demography
- Thermodynamics
- Public economics
- Materials science
- Economics
- Economic growth
- Engineering
Selected publications
Nuclear Technology · 2026-05-05
articleOpen accessElsevier eBooks · 2026-01-01
book-chapter1st authorCorrespondingModified Conductivity Probe Design for Two-Phase Flow Measurement in Very Narrow Channels
Nuclear Technology · 2026-02-10
articleSenior authorCorrespondingReconstruct In-Core Neutron Flux Distribution Using Ex-Core Detectors
2025-01-01
articleAdvanced Nuclear Reactor Driven Direct Air Capture for Achieving Net-Negative Emissions
SSRN Electronic Journal · 2025-01-01
preprintOpen accessNuclear Science and Techniques · 2025-04-18 · 1 citations
articleSenior authorCoupling and economic analysis of nuclear microreactor enabled ammonia production
Progress in Nuclear Energy · 2025-10-31 · 1 citations
articleSenior authorCorrespondingApplied Thermal Engineering · 2024-09-21 · 4 citations
articleSenior authorCorrespondingModeling Microreactor Requirements for High-Performance Computing
Nuclear Technology · 2024-02-23 · 4 citations
articleCorrespondingThe potential deployment of microreactors as a zero-emission source for critical applications within integrated energy systems such as microgrids has been gaining interest in recent years owing to the microreactors' dispatchable nature, modular design, small site footprint, and carbon-free generation. A particularly high-value but challenging application with rapidly growing demand is in the deployment of high-performance computing (HPC) clusters within microgrids. In this work, a model of a HPC cluster in an energy-diverse microgrid is developed to determine the requirements of a technology-agnostic microreactor deployed for such a challenging application. The minute-resolution simulations revealed that the cluster's electrical load fluctuation of up to 4.1 MW/min required a fast and responsive load-following capability. When the load-following capability of the microreactor was perturbed, the required microgrid storage capacity associated with having a 0.1 MW/min dispatchable microreactor decreased by two orders of magnitude as compared with load-following solely by energy storage devices, indicating that load-following capability in microreactors is of great value in such applications. The analysis methods described in this work can be extended to other microgrids, other HPC clusters, or other types of challenging applications, and can help microgrid planners in determining the storage size, output capacity, and ramping capabilities of the storage devices required for a given microgrid configuration.
Validation of two-group interfacial area transport equation in boiling flow
International Journal of Heat and Mass Transfer · 2024-04-06 · 2 citations
articleOpen accessSenior authorCorrespondingThe Two-Fluid Model is the backbone of thermal-hydraulics and system-analysis codes for nuclear design. The Two-Fluid Model tracks the transfer of conserved quantities—mass, momentum, and energy—without the need for bubble interface tracking. However, two-phase flows are characterized by their different flow regimes which change as more vapor is present in the flow, from bubbly flow to cap/slug flow to annular flow. The two-group Two-Fluid Model can track the progression of boiling flows beyond the bubbly region without the need for flow-regime maps. A two-group wall-boiling model is implemented and coupled with the two-group Interfacial Area Transport Equation. The resulting model is compared against experimental data and predicts the growth in cap/slug bubbles through interaction models rather than through flow-regime maps. The coupled model can predict the growth in void fraction and interfacial area concentration beyond the capability of the one-group model, demonstrating the applicability of a coupled two-group approach to modeling boiling flow.
Frequent coauthors
- 23 shared
Zhiee Jhia Ooi
Argonne National Laboratory
- 22 shared
Takashi Hibiki
- 20 shared
Joseph L. Bottini
United States Military Academy
- 17 shared
Longxiang Zhu
- 17 shared
Vineet Kumar
Oak Ridge National Laboratory
- 15 shared
Taiyang Zhang
- 10 shared
Yang Liu
Kunming University of Science and Technology
- 9 shared
Mamoru Ishii
National Institute of Information and Communications Technology
Labs
Illinois Nuclear Power InstitutePI
Awards & honors
- Donald Biggar Willett Faculty Scholar (2024)
- WPI Professor, International Institute for Carbon-Neutral En…
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