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[PDF][PDF] 5.03 corrosion of zirconium alloys
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 …
(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 …
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
Radiation effects in materials often compound and accelerate other detrimental phenomena
such as embrittlement, oxidation and creep. However, irradiation can also decrease the …
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 …
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
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 …
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 …
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
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 …
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 …
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
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 …
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
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 …
(ACC) environment at 21–300° C was evaluated using polarization curve, secondary ion …