Review on chromium coated zirconium alloy accident tolerant fuel cladding

J Yang, M Steinbrück, C Tang, M Große, J Liu… - Journal of Alloys and …, 2022 - Elsevier
Abstract The Fukushima-Daiichi accident revealed that the zirconium fuel claddings have
the significant safety risk of hydrogen detonation due to the strong oxidation and hydrogen …

Raman imaging in corrosion science: High‐temperature oxidation of the zirconium alloys used in the nuclear industry as an example

M Mermoux, C Duriez - Journal of Raman Spectroscopy, 2021 - Wiley Online Library
Successive technological improvements have made Raman imaging systems very efficient.
Raman imaging applications now cover a wide range of scientific fields, including high …

Breakaway oxidation of zirconium alloys exposed to steam around 1000 C

M Le Saux, JC Brachet, V Vandenberghe, A Ambard… - Corrosion …, 2020 - Elsevier
The breakaway oxidation of Zircaloy-4 and M5 Framatome alloys oxidized in flowing steam
around 1000° C was studied. The influences of oxidation temperature between 950 and …

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

Z Cui, J Liu, G Liu, G Tang, X Liu, R Meng… - Acta Materialia, 2024 - Elsevier
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 …

Variant selection and morphology by the different cooling rates in Zr-xNb-0.4 Mo alloys

Y Cao, L Xia, P Feng, S Wang, W Qin… - Journal of Nuclear …, 2023 - Elsevier
Although many efforts have been made on understanding the variant selection rules, the
interplay of these rules and their combined effects on variant selection have not been well …

Breakaway characterization of Zircaloy-4 oxidized in steam and in oxygen at high temperatures using HT-XRD analysis

R Zino, R Chosson, M Ollivier, E Serris - Corrosion Science, 2020 - Elsevier
HT-XRD analyses were performed on Zircaloy-4 sheet samples in steam and oxygen
mixtures at high temperatures in order to investigate any possible relation between zirconia …

Study of the evolution of stresses and associated mechanisms in zirconia growing at high temperature on Zircaloy-4 by use of synchrotron radiation

A Bouayoune, R Guillou, JL Béchade, E Rouesne… - Corrosion …, 2023 - Elsevier
The present work studied the evolution of stresses and associated mechanisms, related to
viscoplastic behavior during relaxation, in the zirconia layer formed during the oxidation of …

Effects of Bi on microstructure and corrosion behavior of Zr-1 Nb alloy in 500° C/10.3 MPa superheated steam

Z Tian, J Peng, X Lin, Y Hu, M Yao, YP Xie, X Liang… - Corrosion …, 2024 - Elsevier
The effects of Bi on the microstructure and corrosion behavior of Zr-1 Nb alloy in
superheated steam at 500° C/10.3 MPa were investigated. Results revealed that addition of …

[HTML][HTML] Decoding the oxidation mechanism of Zircaloy-4 via in situ synchrotron X-ray diffraction and computational elucidation

S Wang, L Lu, A Rahemtulla, M Huttula… - Journal of Alloys and …, 2024 - Elsevier
Comprehensive understanding of the oxidation behavior of Zr alloys, a vital cladding
material in nuclear power plants, is essential for developing improved materials and …

[HTML][HTML] A thermogravimetric comparative study of the high temperature steam oxidation of bare and pre-oxidized Zircaloy-4, M5Framatome and Optimized ZIRLO™

C Duriez, H Richez, C Eymery, J Desquines… - Journal of Nuclear …, 2024 - Elsevier
Abstract For Loss of Coolant Accident (LOCA) analysis, high-temperature oxidation kinetics
in steam of Zircaloy-4 and the two Nb-bearing alloys used in French Pressurized Water …