[PDF][PDF] 5.03 corrosion of zirconium alloys

TR Allen, RJM Konings, AT Motta - Comprehensive nuclear materials, 2012 - nuce.psu.edu
Zirconium alloys are widely used for fuel cladding and in pressure tubes, fuel channels
(boxes), and fuel spacer grids in almost all water-cooled reactors: light water reactors such …

Investigating radiation damage in nuclear energy materials using JANNuS multiple ion beams

A Gentils, C Cabet - Nuclear Instruments and Methods in Physics Research …, 2019 - Elsevier
Ion accelerators have been used by material scientists for decades to investigate radiation
damage formation in nuclear materials and thus to emulate neutron-induced changes. The …

Irradiation damage reduces alloy corrosion rate via oxide space charge compensation effects

Z Yu, E Kautz, H Zhang, A Schneider, T Kim, Y Zhang… - Acta Materialia, 2023 - Elsevier
Radiation effects in materials often compound and accelerate other detrimental phenomena
such as embrittlement, oxidation and creep. However, irradiation can also decrease the …

Hydrogen diffusion process in the oxides formed on zirconium alloys during corrosion in pressurized water reactor conditions

M Tupin, F Martin, C Bisor, R Verlet, P Bossis, J Chene… - Corrosion …, 2017 - Elsevier
During the corrosion in primary water of zirconium alloys, a fraction of hydrogen from the
water diffuses through the oxide into the alloy. To better understand the hydriding process …

Raman spectra analysis of ZrO2 thermally grown on Zircaloy substrates irradiated with heavy ion: Effects of oxygen isotopic substitution

C Ciszak, M Mermoux, G Gutierrez… - Journal of Raman …, 2019 - Wiley Online Library
Recently, unusual Raman signals were observed in different works conducted on thin
zirconia layers grown on zirconium alloys simulating in‐reactor materials after high fluence …

A mechanism assessment for the anti-corrosion of zirconia coating under the condition of subcritical water corrosion

G Cao, Y Yun, H Xu, G Yuan, J Hu, G Shao - Corrosion Science, 2019 - Elsevier
Natural grown ZrO 2 cannot effectively protect Zr alloy due to the poor phase stability. In this
work, a pre-defected ZrO 2 coating was fabricated on Zr alloy and further bombarded by Ar …

Micro-Raman analysis of the fuel-cladding interface in a high burnup PWR fuel rod

C Ciszak, M Mermoux, S Miro, G Gutierrez… - Journal of Nuclear …, 2017 - Elsevier
New insights on the fuel-cladding bonding layer in high burnup nuclear fuel were obtained
using micro-Raman spectroscopy. A specimen was specifically prepared from a cladded …

Corrosion of titanium alloys in pressurised water at 300° C: Kinetics and modelling

S Selva, Q Bignon, A Raynal, F Martin, Q Auzoux… - Corrosion …, 2021 - Elsevier
The corrosion of titanium alloys in primary water at 300° C led to a global weight gain due to
oxidation and surface precipitation, despite some dissolution. A model was proposed, taking …

Corrosion and high-temperature steam oxidation of E110 alloy and its laser welds after ion irradiation

MS Slobodyan, SK Pavlov, GE Remnev - Corrosion Science, 2019 - Elsevier
Corrosion and high-temperature steam oxidation of E110 alloy and its pulsed laser welds
were investigated. An attempt to improve performance properties has been made by …

A mechanistic study on sulfur-induced passivity degradation on Alloy 800 in simulated alkaline crevice chemistries at temperatures ranging from 21 C to 300 C

DH **a, YF Sun, C Shen, XY Chen, HQ Fan, JL Luo - Corrosion Science, 2015 - Elsevier
Sulfur-induced degradation of the passive film on Alloy 800 in a simulated alkaline crevice
(ACC) environment at 21–300° C was evaluated using polarization curve, secondary ion …