Corrosion of zirconium alloys demonstrated by using impedance spectroscopy

Renčiuková, Veronika; Macák, Jan; Sajdl, Petr; Novotný, Radek; Krausová, Aneta

doi:10.1016/j.jnucmat.2018.08.005

Cited by 26 publications

(14 citation statements)

References 34 publications

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Section: Corrosion Resistancementioning

confidence: 61%

“…It is well known that Cr is a useful element to improve corrosion resistance, and this result has also been verified for many HEA systems [210] . Thus, a Cr-containing HEA system with elements that show a low thermal neutron absorption cross-section is a prime candidate for nuclear applications [210] . Xiang et al studied the effect of Cr addition in a Mo 0.5 VNbTi system on the microstructure and properties, including corrosion resistance [210] .…”

Section: Corrosion Resistancementioning

confidence: 61%

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A review on high-throughput development of high-entropy alloys by combinatorial methods

Mooraj¹,

Chen²

2023

J Mater Inf

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High-entropy alloys (HEAs) are an emerging class of alloys with multi-principal elements that greatly expands the compositional space for advanced alloy design. Besides chemistry, processing history can also affect the phase and microstructure formation in HEAs. The number of possible alloy compositions and processing paths gives rise to enormous material design space, which makes it challenging to explore by traditional trial-and-error approaches. This review highlights the progress in combinatorial high-throughput studies towards rapid prediction, manufacturing, and characterization of promising HEA compositions. This review begins with an introduction to HEAs and their unique properties. Then, this review describes high-throughput computational methods such as machine learning that can predict desired alloy compositions from hundreds or even thousands of candidates. The next section of this review presents advances in combinatorial synthesis of material libraries by additive manufacturing for efficient development of high-performance HEAs at bulk scale. The final section of this review discusses the high-throughput characterization techniques that are used to accelerate the material property measurements for systematic understanding of the composition-processing-structure-property relationships in combinatorial HEA libraries.

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Section: Corrosion Resistancementioning

confidence: 61%

Section: Corrosion Resistancementioning

confidence: 61%

A review on high-throughput development of high-entropy alloys by combinatorial methods

Mooraj¹,

Chen²

2023

J Mater Inf

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“…In this case, the average layer thickness can be obtained from the relation

where ∆ G is the weight gain in g·dm −2 , M ZrO2 and M O are the molecular weight of the oxide and atomic weight of oxygen in g·mol −1 , respectively, n is the oxygen stoichiometric coefficient ( n = 2 in the case of ZrO 2 ), and ρ ZrO 2 is the zirconium oxide density = 5.71 g·cm −3 . This relation was successfully applied in Zr corrosion studies [ 34 , 35 ] and gives reasonable results for zirconium oxide layers with thicknesses up to 30 μm. In our case, the results for the diamond-covered sample may have been slightly affected by the physical–chemical changes of the diamond layer during exposure to hot steam.…”

Section: Resultsmentioning

confidence: 99%

Diamond Coating Reduces Nuclear Fuel Rod Corrosion at Accidental Temperatures: The Role of Surface Electrochemistry and Semiconductivity

et al. 2021

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If we want to decrease the probability of accidents in nuclear reactors, we must control the surface corrosion of the fuel rods. In this work we used a diamond coating containing <60% diamond and >40% sp2 “soft” carbon phase to protect Zr alloy fuel rods (ZIRLO ®) against corrosion in steam at temperatures from 850 °C to 1000 °C. A diamond coating was grown in a pulse microwave plasma chemical vapor deposition apparatus and made a strong barrier against hydrogen uptake into ZIRLO® (ZIRLO) under all tested conditions. The coating also reduced ZIRLO corrosion in hot steam at 850 °C (for 60 min) and at 900 °C (for 30 min). However, the protective ability of the diamond coating decreased after 20 min in 1000 °C hot steam. The main goal of this work was to explain how diamond and sp2 “soft” carbon affect the ZIRLO fuel rod surface electrochemistry and semi conductivity and how these parameters influence the hot steam ZIRLO corrosion process. To achieve this goal, theoretical and experimental methods (scanning electron microscopy, Raman spectroscopy, electrochemical impedance spectroscopy, carrier gas hot extraction, oxidation kinetics, ab initio calculations) were applied. Deep understanding of ZIRLO surface processes and states enable us to reduce accidental temperature corrosion in nuclear reactors.

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“…Zirconium has good properties to be used in nuclear reactors, especially as cladding. Nuclear power consumes 90% of metal zirconium industry due to its excellent corrosion resistance, high thermal conductivity, suitable mechanical behavior and low neutron absorption cross‐section in the low and the thermal energy range 19‐23 . The basic idea of using Zr rods as water displacer inside the fuel assembly is to displace a part of the water in order to decrease the moderator‐to‐fuel ratio and the moderation process and thereafter the reactor reactivity 24 .…”

Section: Introductionmentioning

confidence: 99%

Study the neutronic feasibility of using Zr as an energy regulator instead of traditional methods

2021

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Summary The control of the reactor energy increases the reactor fuel cycle time. In this work, a new method has been investigated to control the reactor energy instead of traditional methods. SERPENT2 version 2.1.30 was used to investigate the possibility of using Zirconium rods as an energy regulator in the VVER‐1000. Zirconium rods were used as water displacers. The effect of different Zr rod diameter on the infinite multiplication factor (k∞) of the reactor and the fuel concentration at different fuel burnup steps has been analyzed. Larger fuel pitches have been investigated to increase the Zr rod diameter. The main safety parameters such as the void volume reactivity coefficients, the Doppler reactivity coefficients and the Moderator temperature coefficient have been studied at different fuel pitch and different Zr rod diameter. A comparison between the effect of Zr rods and boric acid on the reactor reactivity proved the efficiency of using Zr rods as reactivity regulation.

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Corrosion of zirconium alloys demonstrated by using impedance spectroscopy

Cited by 26 publications

References 34 publications

A review on high-throughput development of high-entropy alloys by combinatorial methods

A review on high-throughput development of high-entropy alloys by combinatorial methods

Diamond Coating Reduces Nuclear Fuel Rod Corrosion at Accidental Temperatures: The Role of Surface Electrochemistry and Semiconductivity

Study the neutronic feasibility of using Zr as an energy regulator instead of traditional methods

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