High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process
JC Brachet, E Rouesne, J Ribis, T Guilbert, S Urvoy… - Corrosion …, 2020 - Elsevier
The oxidation of chromium-coated zirconium-based alloys is studied under steam at
temperatures ranging from 800° C up to 1500° C and for oxidation times ranging from a few …
temperatures ranging from 800° C up to 1500° C and for oxidation times ranging from a few …
High-temperature oxidation and quenching of chromium-coated zirconium alloy ATF cladding tubes with and w/o pre-damage
M Steinbrück, U Stegmaier, M Große, L Czerniak… - Journal of Nuclear …, 2022 - Elsevier
Chromium-coated zirconium alloys are one of the promising candidates for accident-tolerant
fuel cladding (ATF) tubes for light water reactors (LWRs). In this study, the high temperature …
fuel cladding (ATF) tubes for light water reactors (LWRs). In this study, the high temperature …
Diffusion of chromium of Cr-coated Zircaloy accident tolerant fuel cladding: Model development and experimental validation
D Kim, Y Lee - Surface and Coatings Technology, 2023 - Elsevier
A mechanistic model that calculates Cr diffusion for Cr-coated Zircaloy cladding based on
Finite Difference Method (FDM) has been developed and validated. The developed model …
Finite Difference Method (FDM) has been developed and validated. The developed model …
Eutectic reaction and oxidation behavior of Cr-coated Zircaloy-4 accident-tolerant fuel cladding under various heating rates
D Kim, M Steinbrück, M Grosse, C Tang… - Journal of Nuclear …, 2023 - Elsevier
The Cr-coated zirconium alloy claddings are near-term approach for accident tolerant fuel
(ATF) claddings. The performance of magnetron-sputtered Cr-coated zirconium alloys is …
(ATF) claddings. The performance of magnetron-sputtered Cr-coated zirconium alloys is …
[HTML][HTML] Characterization of eutectic reaction of Cr and Cr/CrN coated zircaloy accident tolerant fuel cladding
D Kim, M Ševeček, Y Lee - Nuclear Engineering and Technology, 2023 - Elsevier
Eutectic reactions of five kinds of Cr-coated Zr alloy cladding with different base materials (Zr–
Nb–Sn alloy or Zr–Nb alloy), different coating thicknesses (6∼ 22.5 μm), and different …
Nb–Sn alloy or Zr–Nb alloy), different coating thicknesses (6∼ 22.5 μm), and different …
Isothermal experiments on eutectic and oxidation reactions of Cr-coated Zr alloy cladding in steam at 1350℃: Behavior, mechanism and kinetics
X Wu, D Wang, Y Zhang, X Li, S Wu, GH Su… - Journal of Alloys and …, 2024 - Elsevier
The isothermal steam oxidation experiments of Cr-coated Zr alloy cladding at 1350℃ were
conducted, and the influence of Cr-Zr eutectic reaction on the oxidation behavior was …
conducted, and the influence of Cr-Zr eutectic reaction on the oxidation behavior was …
The Effect of Chromium Coatings on Hydrogen Uptake in Zirconium Alloy Nuclear Fuel Cladding
JL Walters - 2024 - scholarcommons.sc.edu
The amount of hydrogen in a nuclear reactor can have a profound impact on its performance
and safety when it is absorbed into or released from fuel rods. Hydrogen pickup in modern …
and safety when it is absorbed into or released from fuel rods. Hydrogen pickup in modern …
Current Perspectives on Zirconium Use in Light Water Reactor Fuel and Its Continued Use in Nuclear Power
AM Garde - 2023 - asmedigitalcollection.asme.org
Since the introduction of Zircaloys as light water reactor (LWR) nuclear fuel cladding
materials about 60 years ago, significant irradiation experience has been accumulated on …
materials about 60 years ago, significant irradiation experience has been accumulated on …
Effect of Chromium Content on the On-Cooling Phase Transformations and Induced Prior-β Zr Mechanical Hardening and Failure Mode (in Relation to Enhanced …
JC Brachet, T Guilbert, C Toffolon-Masclet… - … on Zirconium in the …, 2023 - astm.org
Chromium-coated zirconium-based nuclear fuel claddings are studied within the CEA-
Framatome-EDF French nuclear fuel joint program as a short-term “enhanced accident …
Framatome-EDF French nuclear fuel joint program as a short-term “enhanced accident …
Effect of Chromium Content on the On-Cooling Phase Transformations and Induced Prior-bZr Mechanical Hardening and Failure Mode (in Relation to Enhanced …
JC Brachet, P Gokelaere, T Guilbert… - Zirconium in the … - asmedigitalcollection.asme.org
Chromium-coated zirconium-based nuclear fuel claddings are studied within the CEA-
Framatome-EDF French nuclear fuel joint program as a short-term “enhanced accident …
Framatome-EDF French nuclear fuel joint program as a short-term “enhanced accident …