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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 …
Corrosion of FeCrAl alloys used as fuel cladding in nuclear reactors
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 …
resistance of fuel cladding with the advancement of industrialization. FeCrAl alloys are …
Development of accident tolerant FeCrAl-ODS fuel cladding for BWRs in Japan
K Sakamoto, Y Miura, S Ukai, NH Oono… - Journal of Nuclear …, 2021 - Elsevier
The FeCrAl-oxide dispersion strengthened (ODS) alloy is a promising candidate alloy for the
accident tolerant fuel (ATF) cladding of light water reactors (LWRs) and has been recently …
accident tolerant fuel (ATF) cladding of light water reactors (LWRs) and has been recently …
Laser-clad FeCrAl/TiC composite coating on ferrite/martensitic steel: Significant grain refinement and wear resistance enhancement induced by adding TiC
By employing laser cladding, the surface of a ferritic/martensite (F/M) steel was coated with
FeCrAl metallic and FeCrAl/TiC composite coatings with their microstructures and wear …
FeCrAl metallic and FeCrAl/TiC composite coatings with their microstructures and wear …
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 …
saturated lead bismuth eutectic (LBE) at 550° C for up to 8000 h. It was found that the oxide …
[HTML][HTML] Additive manufacturing of FeCrAl alloys for nuclear applications-A focused review
FeCrAl alloys exhibit outstanding high-temperature oxidation resistance and impressive
mechanical strength, rendering them as forefront materials with broad applicability across …
mechanical strength, rendering them as forefront materials with broad applicability across …
[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 …
[PDF][PDF] Handbook on the material properties of FeCrAl alloys for nuclear power production applications
FeCrAl alloys are a class of alloys that have seen increased interest for nuclear power
applications including accident tolerant fuel cladding, structural components for fast fission …
applications including accident tolerant fuel cladding, structural components for fast fission …
Improved irradiation resistance of accident-tolerant high-strength FeCrAl alloys with heterogeneous structures
Post–neutron irradiation examination is performed on advanced accident-tolerant fuel (ATF)
cladding iron-chromium-aluminum (FeCrAl) alloys with∼ 10–13at.% Cr,∼ 10–12 at.% Al,∼ …
cladding iron-chromium-aluminum (FeCrAl) alloys with∼ 10–13at.% Cr,∼ 10–12 at.% Al,∼ …
[KNJIGA][B] Accident-tolerant materials for light water reactor fuels
RB Rebak - 2020 - books.google.com
Accident Tolerant Materials for Light Water Reactor Fuels provides a description of what an
accident tolerant fuel is and the benefits and detriments of each concept. The book begins …
accident tolerant fuel is and the benefits and detriments of each concept. The book begins …