Bren Phillips

Massachusetts Institute of Technology — United States

Engineering · Physical Sciences

16h-index891citations58works4.52yr avg
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Research Topics

Heat Transfer and Boiling Studies(30), Fluid Dynamics and Mixing(16), Nuclear Materials and Properties(12), Heat Transfer and Optimization(10), Nuclear reactor physics and engineering(8)

Publications58 total

Mechanisms of carbon dioxide fouling formation and growth during boiling of liquid nitrogen on nano-smooth surfaces and its effect on heat transfer
Applied Thermal Engineering·2025· 2 cited
Mechanisms of Carbon Dioxide Fouling Formation and Growth During Boiling of Liquid Nitrogen on Nano-Smooth Surfaces and its Effect on Heat Transfer
SSRN Electronic Journal·2025Open Access
Bubble departure and sliding in high-pressure flow boiling of water
Journal of Fluid Mechanics·2024· 16 cited
Bubble dynamics in high-pressure flow boiling conditions
Journal of Physics Conference Series·2024Open Access
Experimental demonstration of a data-driven control system for subcritical nuclear facility
Progress in Nuclear Energy·2023· 1 citedOpen Access
Bubble departure and sliding in high-pressure flow boiling of water
arXiv (Cornell University)·2023Open Access
A unifying criterion of the boiling crisis
Nature Communications·2023· 79 citedOpen Access
Autonomous and online detection of dry areas on a boiling surface using deep learning and infrared thermometry
Experimental Thermal and Fluid Science·2023· 16 cited
A unifying criterion of the boiling crisis
2023· 3 citedOpen Access
Automated bubble analysis of high-speed subcooled flow boiling images using U-net transfer learning and global optical flow
International Journal of Multiphase Flow·2022· 35 citedOpen Access
Experimental validation of a high fidelity Monte Carlo neutron transport model of the MIT graphite exponential pile
Progress in Nuclear Energy·2022· 7 citedOpen Access
Wettability and CHF limits of Accident-Tolerant nuclear fuel cladding materials in light water reactor conditions
Applied Thermal Engineering·2022· 25 citedOpen Access
Effect of PVD-coated chromium on the subcooled flow boiling performance of nuclear reactor cladding materials
Applied Thermal Engineering·2022· 23 citedOpen Access
Separate effect of oxidation on the subcooled flow boiling performance of Zircaloy-4 at atmospheric pressure
International Journal of Heat and Mass Transfer·2022· 15 cited
Wettability and Chf Limits of Accident-Tolerant Nuclear Fuel Cladding Materials in Light Water Reactor Conditions
SSRN Electronic Journal·2022· 3 citedOpen Access
Automated Bubble Analysis of High-Speed Subcooled Flow Boiling Images Using U-Net Transfer Learning and Global Optical Flow
SSRN Electronic Journal·2022· 3 citedOpen Access
Post-LOCA ductility of Cr-coated cladding and its embrittlement limit
Journal of Nuclear Materials·2021· 44 citedOpen Access
Impact of nuclear environment on hydrothermal corrosion and silica transport for CVD SiC in light water reactors
Journal of Nuclear Materials·2021· 24 cited
Decrypting the boiling crisis through data-driven exploration of high-resolution infrared thermometry measurements
Applied Physics Letters·2021· 29 citedOpen Access
Empirical Models for Multidimensional Regression of Fission Systems
arXiv (Cornell University)·2021· 3 citedOpen Access
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Frequent Co-authors

Matteo Bucci(18), Jacopo Buongiorno(10), Guanyu Su(9), Artyom Kossolapov(9), Jee Hyun Seong(8), Chi Wang(6), Koroush Shirvan(5), Florian Chavagnat(5), Thomas McKrell(5), Francesco Paolo D’Aleo(5), Horst-Michael Prasser(5), Jiankai Yu(5), Akshay J. Dave(5), Arunkumar Seshadri(4), Madhumitha Ravichandran(4), Eissa Al‐Safran(4), Gustavo Aguiar(3), Md Mahamudur Rahman(3), Jarod Wilson(3), Benoit Forget(3)