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 …
reactors to significantly more oxidation-resistant materials, thereby enhancing safety …
[HTML][HTML] Current state and prospect on the development of advanced nuclear fuel system materials: A review
The intricate balance between reactor economics and safety necessitates the emergence of
new and advanced nuclear systems and, very importantly, advanced materials, which can …
new and advanced nuclear systems and, very importantly, advanced materials, which can …
BISON: A flexible code for advanced simulation of the performance of multiple nuclear fuel forms
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 …
Simulation Environment (MOOSE) finite element library. One of its major goals is to have a …
[HTML][HTML] 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 …
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
FeCrAl alloys are currently under consideration for accident-tolerant fuel cladding
applications in light water reactors owing to their superior high-temperature oxidation and …
applications in light water reactors owing to their superior high-temperature oxidation and …
Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys
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 …
FeCrAl alloys is increasingly a critical need as these alloys continue to become more mature …
Mechanical and high-temperature corrosion properties of AlTiCrNiTa high entropy alloy coating prepared by magnetron sputtering for accident-tolerant fuel cladding
S Zhao, C Liu, J Yang, W Zhang, L He, R Zhang… - Surface and Coatings …, 2021 - Elsevier
A high-entropy alloy (HEA) AlTiCrNiTa coating with near-equal molar ratio was prepared on
the base of zircaloy-4 substrates using radio frequency (RF) magnetron sputtering (MS) …
the base of zircaloy-4 substrates using radio frequency (RF) magnetron sputtering (MS) …
[HTML][HTML] A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2 for ATF cladding
At present, the Department of Energy (DOE) in Unite State are directing the efforts of
developing accident tolerant fuel (ATF) technology. As the first barrier of nuclear fuel system …
developing 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
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 …
during accident scenarios in water-cooled reactors. These ATF cladding should also perform …
An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions
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 …
cladding for increased accident tolerance. An analysis of the response of FeCrAl under …