Accident tolerant fuel cladding development: Promise, status, and challenges

KA Terrani - Journal of Nuclear Materials, 2018 - Elsevier
The motivation for transitioning away from zirconium-based fuel cladding in light water
reactors to significantly more oxidation-resistant materials, thereby enhancing safety …

[HTML][HTML] A review of fuel performance modelling

P Van Uffelen, J Hales, W Li, G Rossiter… - Journal of Nuclear …, 2019 - Elsevier
Dr. Paul Van Uffelen graduated from the Vrije Universiteit Brussel (Belgium) and the Ecole
Nationale Supérieure Polytechnique de Grenoble (France) with a master degree in …

Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel

SK Lee, M Liu, NR Brown, KA Terrani… - International Journal of …, 2019 - Elsevier
Steady and transient (with a heating rate of 685° C/s) internal-flow CHF (Critical Heat Flux)
experiments were conducted under atmospheric pressure at a fixed inlet temperature (40° C …

Surface wettability and pool boiling critical heat flux of accident tolerant fuel cladding-FeCrAl alloys

AF Ali, JP Gorton, NR Brown, KA Terrani… - … engineering and design, 2018 - Elsevier
Surface wettability analysis, including measurements of static (θ) advance (θ A), and
receding (θ r) contact angles, and surface roughness, Ra, are effective parameters used in …

Experimental study of saturated pool boiling heat transfer with FeCrAl-and Cr-layered vertical tubes under atmospheric pressure

HH Son, YS Cho, SJ Kim - International Journal of Heat and Mass Transfer, 2019 - Elsevier
This study compares the nucleate boiling heat transfer coefficient (NBHTC) and critical heat
flux (CHF) of two candidate coatings, FeCrAl and Cr, being considered for accident-tolerant …

Elucidating the impact of flow on material-sensitive critical heat flux and boiling heat transfer coefficients: an experimental study with various materials

SK Lee, Y Lee, NR Brown, KA Terrani - … Journal of Heat and Mass Transfer, 2020 - Elsevier
Steady-state internal flow boiling critical heat flux (CHF) experiments were carried out at
10℃ inlet subcooling and atmospheric pressure (84 kPa at an altitude of about 5300 feet) …

Influence of wettability due to laser-texturing on critical heat flux in vertical flow boiling

JL Bottini, V Kumar, S Hammouti, D Ruzic… - International Journal of …, 2018 - Elsevier
The critical heat flux (CHF) marks the upper limit of safe operation of heat transfer systems
that utilize two-phase boiling heat transfer. In a heat-flux-controlled system, exceeding the …

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

JP Gorton, SK Lee, Y Lee, NR Brown - Nuclear Engineering and Design, 2019 - Elsevier
In this work we analyze the differences between previous transient critical heat flux (CHF)
experiments using iron-chromium-aluminum (FeCrAl), Inconel 600, and stainless steel 316 …

Implementation of fiber optic temperature sensors in quenching heat transfer analysis

P Hurley, JP Duarte - Applied Thermal Engineering, 2021 - Elsevier
The minimum film boiling temperature (T min) is one of the primary factors that influence the
efficiency of rewetting of nuclear fuel rods after a loss-of-coolant accident (LOCA) in a light …

Experimental study on the natural circulation behavior of a full-scale PWR fuel assembly

M Liu, S Ni, X Wang, L Liu, H Gu - Annals of nuclear energy, 2022 - Elsevier
During a loss-of-coolant accident in spent fuel pools, the fuel assembly will be exposed to
the air environment and decay heat will be removed through the natural circulation of air …