High-temperature corrosion of Zr–Nb alloy for nuclear structural materials
Zr–Nb alloy is successfully used as structural materials in nuclear reactors. However, its
widespread application is restricted by corrosion due to complex in-pile environments. This …
widespread application is restricted by corrosion due to complex in-pile environments. This …
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 …
[HTML][HTML] High temperature zirconium alloys for fusion energy
This review considers current Zr alloys and opportunities for advanced zirconium alloys to
meet the demands of a structural material in fusion reactors. Zr based materials in the …
meet the demands of a structural material in fusion reactors. Zr based materials in the …
Compact size Zr–Fe2O3 inspired metal-dielectric angle and polarization insensitive nanostructure for efficient solar energy absorption
We exhibit the perfect solar design by using Ferric Oxide (Fe 2 O 3) as the substrate layer,
and the Zirconium (Zr) material based resonator. The overall solar absorption is 95.79% and …
and the Zirconium (Zr) material based resonator. The overall solar absorption is 95.79% and …
Corrosion of Zircaloy-4, Zr-1Nb and FeCrAl alloys in deaerated water at 330 C and 14 MPa: Superior corrosion resistance and corrosion mechanism of FeCrAl alloy by …
After the Fukushima explosion, the research and development of accident tolerant fuel (ATF)
cladding has become a hot spot in the nuclear field. In this work, corrosion behavior of …
cladding has become a hot spot in the nuclear field. In this work, corrosion behavior of …
Susceptibility of Zr-2.5 (wt.%) Nb alloy to undergo nodular corrosion in water and steam environments: Effect of surface, cold work, temperature
A Samanta, TK Sawarn, S Banerjee, AK Tyagi… - Progress in Nuclear …, 2023 - Elsevier
Nodular corrosion can severely affect the service life of zirconium alloys in water cooled
nuclear reactors. In this study, the susceptibility of pressure tube alloy to undergo nodular …
nuclear reactors. In this study, the susceptibility of pressure tube alloy to undergo nodular …
Oxidation of typical Zr-1 Nb alloy in high-temperature air under 700–900 C
In order to promote the understanding of Zirconium alloy cladding failure under loss of
coolant accidents (LOCA), air oxidation behavior of Zr-1 Nb-0.12 O (M5) alloy at 700–900° C …
coolant accidents (LOCA), air oxidation behavior of Zr-1 Nb-0.12 O (M5) alloy at 700–900° C …
Understanding the oxidation resistance of zirconium alloy at 1000° C based on the formation of a Zr-Sn intermetallic phase and co-precipitation of Sn and Nb
The oxidation behavior of zirconium alloy in high-temperature steam plays a dominant role
in the operation of nuclear reactors under accident conditions. The present work …
in the operation of nuclear reactors under accident conditions. The present work …
Effect of adding Ta on the tribological behavior of Zr alloy after β-quenching and annealing
In the current research, the wear properties of the Zr alloys at temperatures of 25, 300, and
600° C under loads of 50, 100, and 150 N were investigated. For this purpose, vacuum arc …
600° C under loads of 50, 100, and 150 N were investigated. For this purpose, vacuum arc …
Effect of Zr and C co-addition on the characteristics of ZrB2-based ceramics: role of spark plasma sintering temperature
This study investigates the effect of Zr and C co-addition on the spark plasma sintered ZrB 2-
5 vol% Zr/graphite composites. Spark plasma sintering method was applied to consolidate …
5 vol% Zr/graphite composites. Spark plasma sintering method was applied to consolidate …