Jacob P. Gorton

Surface wettability and pool boiling Critical Heat Flux of Accident Tolerant Fuel cladding-FeCrAl alloys

Amir Ali, Jacob P. Gorton, Nicholas R. Brown et al. · Nuclear Engineering and Design · 2018 · 41 citations · Full text

Materials Science, Materials Engineering, Critical Heat Flux +10

Review of pool boiling critical heat flux (CHF) and heater rod design for CHF experiments in TREAT

Richard Hernandez, Charles P Folsom, Nicolas Woolstenhulme et al. · Progress in Nuclear Energy · 2020 · 32 citations · Full text

Critical Heat Flux, Heat Transfer Process, Engineering +10

Deformation analysis of SiC-SiC channel box for BWR applications

Gyanender Singh, Jacob P. Gorton, Danny Schappel et al. · Journal of Nuclear Materials · 2018 · 25 citations · Full text

Engineering, Bias Temperature Instability, Power Semiconductor Device +3

Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR

Jacob P. Gorton, Benjamin Collins, Andrew Nelson et al. · Nuclear Engineering and Design · 2019 · 24 citations · Full text

Safety Characteristics, Engineering, Nuclear Fuel +7

Comparison of experimental and simulated critical heat flux tests with various cladding alloys: Sensitivity of iron-chromium-aluminum (FeCrAl) to heat transfer coefficients and material properties

Jacob P. Gorton, Soon Lee, Youho Lee et al. · Nuclear Engineering and Design · 2019 · 18 citations · Full text

Materials Science, Engineering, Material Properties +10