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 …

Corrosion of FeCrAl alloys used as fuel cladding in nuclear reactors

G Jiang, D Xu, P Feng, S Guo, J Yang, Y Li - Journal of Alloys and …, 2021 - Elsevier
The safety of nuclear power plants has put forward new requirements for the corrosion
resistance of fuel cladding with the advancement of industrialization. FeCrAl alloys are …

BISON: A flexible code for advanced simulation of the performance of multiple nuclear fuel forms

RL Williamson, JD Hales, SR Novascone… - Nuclear …, 2021 - Taylor & Francis
BISON is a nuclear fuel performance application built using the Multiphysics Object-Oriented
Simulation Environment (MOOSE) finite element library. One of its major goals is to have a …

Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings

C Tang, M Stueber, HJ Seifert, M Steinbrueck - Corrosion reviews, 2017 - degruyter.com
Chongchong Tang received his Master's degree in metallurgical engineering from the
Northeastern University, China, in 2014. He is currently a PhD student in the IAM-AWP of the …

A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys

SA Briggs, PD Edmondson, KC Littrell, Y Yamamoto… - Acta Materialia, 2017 - Elsevier
FeCrAl alloys are currently under consideration for accident-tolerant fuel cladding
applications in light water reactors owing to their superior high-temperature oxidation and …

An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions

KA Gamble, T Barani, D Pizzocri, JD Hales… - Journal of nuclear …, 2017 - Elsevier
Abstract Iron-chromium-aluminum (FeCrAl) alloys are candidates to be used as nuclear fuel
cladding for increased accident tolerance. An analysis of the response of FeCrAl under …

Corrosion behaviors of FeCrAl alloys exposed to oxygen-saturated static lead bismuth eutectic at 550° C

Z Zhu, J Tan, X Wu, Z Zhang, EH Han, X Wang - Corrosion Science, 2022 - Elsevier
The corrosion behaviors of two types of FeCrAl alloys were investigated in static oxygen-
saturated lead bismuth eutectic (LBE) at 550° C for up to 8000 h. It was found that the oxide …

Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys

KG Field, SA Briggs, K Sridharan, RH Howard… - Journal of Nuclear …, 2017 - Elsevier
The development and understanding of the mechanical properties of neutron-irradiated
FeCrAl alloys is increasingly a critical need as these alloys continue to become more mature …

[HTML][HTML] A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2 for ATF cladding

B Qiu, J Wang, Y Deng, M Wang, Y Wu… - Nuclear Engineering and …, 2020 - Elsevier
At present, the Department of Energy (DOE) in Unite State are directing the efforts of
develo** accident tolerant fuel (ATF) technology. As the first barrier of nuclear fuel system …

Mechanical and chemical properties of PVD and cold spray Cr-coatings on Zircaloy-4

RV Umretiya, B Elward, D Lee, M Anderson… - Journal of Nuclear …, 2020 - Elsevier
Accident-tolerant fuel (ATF) cladding materials aim to improve fuel reliability and safety
during accident scenarios in water-cooled reactors. These ATF cladding should also perform …