Impact of intermetallic precipitates on hydrogen distribution in the oxide layers formed on zirconium alloys in a steam atmosphere: a 2D(3He,p)α nuclear analysis study in microbeam mode

G, Lelièvre; Tessier, Christine; Iltis, X.; Berthier, B.; Lefebvre, F.

doi:10.1016/s0925-8388(97)00608-7

Cited by 14 publications

(4 citation statements)

References 24 publications

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“…Lelièvre et al[8]. Conversely, Zr 2 Fe and Zr 2 Ni, which relate to the Zr-rich SPPs found in Zry-2, provide sites with low H solution enthalpy: Zr 2 Fe similar to α-Zr but Zr 2 Ni significantly lower than either α or β-Zr.…”

mentioning

confidence: 95%

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Hydrogen accommodation in Zr second phase particles: Implications for H pick-up and hydriding of Zircaloy-2 and Zircaloy-4

et al. 2013

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mentioning

confidence: 95%

“…There are many theories as to how intermetallics influence corrosion and H pickup but all are subject to challenge [4][5][6][7][8]. Hatano et al [4] suggested that as the oxide layer thickens, the larger SPPs residing at the oxide-metal interface will oxidise more slowly than the surrounding Zr.…”

Section: Introductionmentioning

confidence: 99%

Hydrogen accommodation in Zr second phase particles: Implications for H pick-up and hydriding of Zircaloy-2 and Zircaloy-4

et al. 2013

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“…Let us consider the corrosion of zirconium alloy, or Zircaloy for two different stages: pre-transition and post-transition. This stage of corrosion is accompanied by oxide dissolution (Lelievre et al, 1998). When the oxygen concentration in the film reaches stoichiometry, the zirconium oxide does not have a passive property anymore and grows as a white porous layer on top of the black film from the pre-transition.…”

Section: 9mentioning

confidence: 99%

A study of solute transport of radiolysis products in crud and its effects on crud growth on PWR fuel pin

Joe¹,

Kim

Jones

2016

Nuclear Engineering and Design

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This research examines the effect of radiolysis species (H 2 , O 2 , and H 2 O 2 ) upon crud deposition and growth and also the effect of their concentration within the crud. A 3-D transient diffusion model has been developed to simulate solute transport of these radiolysis products in porous crud layer. It attempts to explain the behavior of the porous crud growth on PWR fuel pins. This model employs a system of coupled mass transport and chemical interactions as the source term, which make the problem non-linear. A Monte Carlo technique is adopted to simulate the behavior of the different species.The direct application of this study to nuclear engineering research is to aid in the design of reactors with higher performance. With the deregulation of the U.S. power market, there is an incentive to extend the life and to enhance the performance and For the modeling of solute transport of radiolysis products, the present analysis considered two competing solute transport mechanisms within the porous crud deposits: molecular diffusion with a source term from the radiolysis and mass convection. Initially, the analytical model for the equilibrium state using the Laplace equation is summarized from the author's earlier work. Later, a transient diffusion equation was introduced using a random walk Monte Carlo technique coupled with a constant source term from radiolysis. This procedure by Ragheb was modified from a cartesian to a cylindrical geometry random walk. The molecular radiolysis species of hydrogen, oxygen, and hydrogen peroxide are the most stable radiolysis products that directly affect: (1) the oxidation-reduction reactions at the interface of crud/cladding and (2) the formation of nickel ferrite within the crud deposit. In a post-AOA crud, Bonaccordite (Ni 2 FeBO 5 ) is also observed in the nickel-ferrite. It is recommended that further investigations be performed incorporating the electrochemical interactions of these electroactive species.More detailed consideration of convective transport should be coupled with diffusion with a source term of radiolysis.

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“…Transmission electron microscopy (TEM) observations of oxide films on Zircaloy-4 showed that oxidation rate of Zr(Fe,Cr) 2 precipitates was slower than that of the zirconium matrix [19]. Tägtstrom et al [9] and Leliëvre et al [20] proposed that SPPs offered sites where hydrogen could easily be absorbed into the Zr-based material. Therefore, it's reasonable to propose that the presence of Zr(Fe,Cr) 2 SPPs is responsible for the increase in the amount of hydrogen uptake, as Zr(Fe,Cr) 2 SPPs embedded in a-Zr matrix and exposed at the metal/oxide interface could act as a preferred path for hydrogen uptake.…”

Section: The Effect Of Cr Element On the Hydrogen Uptakementioning

confidence: 99%

The effect of alloying modifications on hydrogen uptake of zirconium-alloy welding specimens during corrosion tests

Yao

Zhou

et al. 2006

Journal of Nuclear Materials

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Impact of intermetallic precipitates on hydrogen distribution in the oxide layers formed on zirconium alloys in a steam atmosphere: a 2D(3He,p)α nuclear analysis study in microbeam mode

Cited by 14 publications

References 24 publications

Hydrogen accommodation in Zr second phase particles: Implications for H pick-up and hydriding of Zircaloy-2 and Zircaloy-4

Hydrogen accommodation in Zr second phase particles: Implications for H pick-up and hydriding of Zircaloy-2 and Zircaloy-4

A study of solute transport of radiolysis products in crud and its effects on crud growth on PWR fuel pin

The effect of alloying modifications on hydrogen uptake of zirconium-alloy welding specimens during corrosion tests

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