Influence of chemical composition of zirconium alloy E110 on embrittlement under LOCA conditions – Part 1: Oxidation kinetics and macrocharacteristics of structure and fracture

Nikulin, S.; Рожнов, А. Б.; Белов, В. А.; Li, E.V.; Glazkina, V.S.

doi:10.1016/j.jnucmat.2011.07.017

Cited by 33 publications

(5 citation statements)

References 3 publications

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“…Extensive investigations have been carried out to find out the mechanisms of the hightemperature zirconium alloy oxidation in different media [1][2][3][4][5][6][7] and to develop the zirconium alloy protection techniques [8][9][10][11][12][13][14]. It has been established that the ion implantation of different elements can change the structure and the composition of the zirconium oxide and thus improve its protective properties [8,9].…”

Section: Introductionmentioning

confidence: 99%

Vacuum-arc chromium-based coatings for protection of zirconium alloys from the high-temperature oxidation in air

Куприн

Белоус

Voyevodin

et al. 2015

Journal of Nuclear Materials

135

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Section: Introductionmentioning

confidence: 99%

Vacuum-arc chromium-based coatings for protection of zirconium alloys from the high-temperature oxidation in air

Куприн

Белоус

Voyevodin

et al. 2015

Journal of Nuclear Materials

135

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“…In the new E110G cladding, 70% of the zirconium metal comes from this 'sponge', with the residual 30% made by the iodide process. The main chemical composition of E110G alloy remains the same, 99% zirconium and 1% niobium, but permissible levels of certain trace element concentrations are upgraded (Nikulin et al, 2011).…”

Section: Experimental Investigations 31 Samples Investigatedmentioning

confidence: 99%

Evolution of dislocation microstructure in irradiated Zr alloys determined by X-ray peak profile analysis

et al. 2021

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During neutron irradiation of metals, owing to the enhanced number of vacancies and interstitial atoms, the climb motion of dislocations becomes significant at room temperature, leading to a recrystallization of the material. Moreover, the vacancies and interstitial atoms tend to form prismatic dislocation loops that play a crucial role in the plastic properties of the materials. X-ray peak profile analysis is an efficient nondestructive method to determine the properties of dislocation microstructure. In the first half of this article, the foundation of the asymptotic peak broadening theory and the related restricted-moments peak-evaluation method is summarized. After this, the microstructural parameters obtained by X-ray peak profile analysis are reported for irradiated E110 and E110G Zr alloys used as cladding material in the nuclear industry.

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“…Zr-Nb alloys , Zirlo, M5 are develop for application in the water cooled reactor. It has been understood that Zirconium added with Nb show the better corrosion resistance when Nb content is less than 5wt.% by optimizing the heat-treatment [9,10]. Depending on the composition and the oxidation conditions, three crystallographic structures have been reported for the ZrO 2 layer: monoclinic, tetragonal and in rare cases cubic zirconia.…”

Section: David Publishingmentioning

confidence: 99%

High Temperature Oxidation of Zr-2.5%wt Nb Alloys Doped with Yttrium

Prajitno¹,

Soepriyanto²,

Basuki³

et al. 2013

JMSE-B

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Zirconium base alloys have been utilized in LWRs (light water reactors) as fuel element cladding tubes, fuel assembly spacer grids, guide tubes in PWRs (pressurized water reactors) due to their low neutron absorption and good corrosion resistance. The oxidation resistance of Zr alloys are strongly controlled by the phase presence and composition of the alloys. The beneficial effect of yttrium content on isothermal oxidation behavior of Zr-2.5%Nb-Y(Y = 0, 0.5, 1, 1.5)in wt % alloy at high temperature has been studied. High temperature oxidation carried out in air furnace at 600,700 and 800 o C for 1, 4, and 9 h. Characterization by optical microscope showed that microstructure of Zr-2.5%Nb-Y alloys relatively unchanged. X-ray diffraction of the alloys depicted that the oxide scale formed during oxidation of zirconium alloys is monoclinic ZrO 2 and minor of tetragonal ZrO 2 , while unoxidized alloy showed two phase α and β phase. SEM-EDS examination shows that depletion of Zr composition took place under the oxide layer. Kinetic rate of oxidation of zirconium alloy showed that increasing oxidation temperature will increase oxidation rate but increasing yttrium content in the alloys will decrease oxidation rate. The parabolic rate constant value decreasing with increasing yttrium in Zr-2.5%Nb alloys.

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Influence of chemical composition of zirconium alloy E110 on embrittlement under LOCA conditions – Part 1: Oxidation kinetics and macrocharacteristics of structure and fracture

Cited by 33 publications

References 3 publications

Vacuum-arc chromium-based coatings for protection of zirconium alloys from the high-temperature oxidation in air

Vacuum-arc chromium-based coatings for protection of zirconium alloys from the high-temperature oxidation in air

Evolution of dislocation microstructure in irradiated Zr alloys determined by X-ray peak profile analysis

High Temperature Oxidation of Zr-2.5%wt Nb Alloys Doped with Yttrium

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