Surface orientation dependence of irradiation-induced hardening in a polycrystalline zirconium alloy

Yang, Huilong; Kano, Shinzo; McGrady, John; Shen, Jingjie; Matsukawa, Y.; Chen, Dongyue; Murakami, Kenta; Abe, Hiroaki

doi:10.1016/j.scriptamat.2018.11.029

Cited by 15 publications

(8 citation statements)

References 26 publications

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“…C 2 is the concentration of oxygen at the oxide/substrate interface (oxide side). The concentration's value is 1.5494-9.7 × 10 −4 T g/cm 3 [35], where T is the absolute temperature in K. Because T was 633 K in this work, C 2 is equal to 1.486 g/cm 3 . C 3 is the concentration of oxygen at the oxide/substrate interface (substrate side) and can be regarded as the saturation concentration of oxygen in α-Zr.…”

Section: Model and Calculation Methodsmentioning

confidence: 87%

“…The y axis is the concentration of oxygen in the oxide film and the substrate. C 1 is the oxygen concentration at the oxide/environment interface, which equals 1.526 g/cm 3 [35]. C 2 is the concentration of oxygen at the oxide/substrate interface (oxide side).…”

Section: Model and Calculation Methodsmentioning

confidence: 99%

“…C 3 is the concentration of oxygen at the oxide/substrate interface (substrate side) and can be regarded as the saturation concentration of oxygen in α-Zr. For the Zr-O phase diagram [16], C 3 was calculated to be 0.459 g/cm 3 .…”

Section: Model and Calculation Methodsmentioning

confidence: 99%

“…Zirconium (Zr) alloys are widely used as fuel claddings in nuclear reactors due to their adequate mechanical properties, low neutron absorption rate, and excellent corrosion resistance in service environments [1][2][3][4]. Among these properties, corrosion resistance is one of the most important considerations, as corrosion limits the service life of Zr alloys and is related to the safety of nuclear reactors [5][6][7][8].…”

Section: Introductionmentioning

confidence: 99%

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Calculation of Oxygen Diffusion Coefficients in Oxide Films Formed on Low-Temperature Annealed Zr Alloys and Their Related Corrosion Behavior

Zhang

Chen

Zhao³

et al. 2019

Metals

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The growth of oxide film, which results from the inward oxygen diffusion from a corrosive environment, is a critical consideration for the corrosion resistance of zirconium alloys. This work calculates the oxygen diffusion coefficients in the oxide films formed on zirconium alloys annealed at 400~500 °C and investigates the related corrosion behavior. The annealed samples have a close size for the second-phase particles but a distinctive hardness, indicating the difference in substrate conditions. The weight gain of all samples highly follows parabolic laws. The weight gain of the sample annealed at 400 °C has the fastest increase rate at the very beginning of the corrosion test, but its oxide film has the slowest growth rate as the corrosion proceeds. By contrast, the sample annealed at 500 °C shows the lowest weight gain but the highest corrosion rate constant. Such a corrosion behavior is attributed to the amount of defects existing in the oxide film formed on the annealed samples; fewer defects would provide a lower fraction of short-circuit diffusion in total diffusion, resulting in a lower diffusion coefficient of oxygen in the oxide film, thereby producing better corrosion resistance. This is consistent with the calculated diffusion coefficients of oxygen in the oxide films: 3.252 × 10−11 cm2/s, 3.464 × 10−11 cm2/s and 3.740 × 10−11 cm2/s for the samples annealed at 400 °C, 450 °C, and 500 °C, respectively.

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Section: Model and Calculation Methodsmentioning

confidence: 87%

Section: Model and Calculation Methodsmentioning

confidence: 99%

Section: Model and Calculation Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Calculation of Oxygen Diffusion Coefficients in Oxide Films Formed on Low-Temperature Annealed Zr Alloys and Their Related Corrosion Behavior

Zhang

Chen

Zhao³

et al. 2019

Metals

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“…F/M steel have been widely studied by many research groups [11][12][13]. This paper investigates mechanical properties (hardness) of P91 and P92 steels at high temperature.…”

Section: Introductionmentioning

confidence: 99%

Investigation of Long and Short Term Irradiation Hardening of P91 and P92 Ferritic/Martensitic Steels

Hiwa¹,

Ari²

2019

PAST-TF

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The aim of the study was to determine the effect of proton irradiation at room temperature on ferritic/martensitic P91 and P92 steels, in particular on their hardness. In addition, SRIM programme was used to identify the proton penetration depth. The study has found that the hardness of the unirradiated P92 steel is higher than that of unirradiated P91 steel, since P92 steel contains tungsten, which produces higher level of solid solution hardening. P91 and P92 steel samples were irradiated using 1.9-MeV protons to the fluence of 1.3510 17 ion/cm 2 . It was found that Vickers hardness test values increased for both P91 and P92 steels at 0.2 kg loads. For high proton irradiation (long irradiation period) the fluence was 1.10110 18 ion/cm 2 (about ten times higher than at the low proton irradiation). With growth of irradiation fluence, the number of displacements per atom (dpa) went up from 0.043 dpa (for low irradiation) to 0.18 dpa (for high irradiation) and the hardness of steels that were under investigation increased. P91 and P92 steel samples after long irradiation were heat treated for one hour at 700 o C in a vacuum furnace. The study identified that while the chemical composition of P91 and P92 steel were almost identical, irradiated P92 steel requires twice the heat treatment to reduce its hardness to a basic value, as compared with P91 steel samples.Целью данного исследования было определение влияния облучения протонами при комнатной температуре на ферритномартенситные стали Р91 и Р92, в частности, на их твёрдость. Кроме того, для изучения глубины внедрения протонов в стали была использована вычислительная программа SRIM. Обнаружено, что необлучённая сталь Р92 твёрже, чем необлучённая сталь Р91. Сталь Р92 содержит вольфрам, который способствует упрочнению твёрдых растворов. Образцы сталей Р91 и Р92 были кратковременно облучены протонами энергией 1,9 МэВ до флюенса 1,35·10 17 ион/см 2 . Под нагрузкой 200 г их твёрдость по Виккерсу увеличилась. Затем аналогичные образцы были подвергнуты приблизительно в 10 раз более длительному облучению до флюенса 1,101·10 18 ион/см 2 . С увеличением продолжительности облучения увеличилось число смещений на атом с 0,043 до 0,18 млн -1 и увеличилась твёрдость образцов. После более длительного облучения образцы исследуемых сталей были подвергнуты термообработке -помещены на один час в вакуумную печь при температуре 700 ºС. Исследование показало, что, хотя химический состав исследованных сталей почти идентичен, термообработка облучённой стали Р92 для снижения её твёрдости до исходного уровня требует вдвое большего времени, чем термообработка образцов стали Р91.Ключевые слова: программа SRIM, сканирующий электронный микроскоп, смещение на атом, сталь Р91, сталь Р92.

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Radiation Effects in Zirconium Alloys

Onimus

Doriot

Béchade

2020

Comprehensive Nuclear Materials

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Surface orientation dependence of irradiation-induced hardening in a polycrystalline zirconium alloy

Cited by 15 publications

References 26 publications

Calculation of Oxygen Diffusion Coefficients in Oxide Films Formed on Low-Temperature Annealed Zr Alloys and Their Related Corrosion Behavior

Calculation of Oxygen Diffusion Coefficients in Oxide Films Formed on Low-Temperature Annealed Zr Alloys and Their Related Corrosion Behavior

Investigation of Long and Short Term Irradiation Hardening of P91 and P92 Ferritic/Martensitic Steels

Radiation Effects in Zirconium Alloys

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