Mechanism of zircaloy nodular corrosion

Kuwae, Ryosho; Sato, Kanemitsu; Higashinakagawa, Emiko; Kawashima, Junko; Nakamura, Shigenari

doi:10.1016/0022-3115(83)90199-x

Cited by 82 publications

(28 citation statements)

References 13 publications

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“…As the Fe/Ni largely decreases towards the SPP edge with increasing dose, we believe that the solute is being dispersed into the matrix. While Zu et al did not demonstrate chemical evolution within SPPs in Zircaloy-4, this could be due to either a better stability because of the higher Fe/Cr ratio in Zircaloy-2 Fe-Cr SPPs [5,6,41,50,58] or due to the limitations associated with single-point EDS sampling or line scans. However, the authors presented energy-filtered TEM, which suggested the possibility of post-irradiation Fe segregation to the matrix-SPP interfacial region for an Fe-Cr SPP and to that of a small SPP the authors referred to as ZrFe 2 [47].…”

Section: Spp Dissolution and Amorphisationmentioning

confidence: 93%

“…Due to their limited solubility in hcp α-Zr [2][3][4], the common alloying elements Fe, Cr and Ni precipitate as thermodynamically stable second phase particles (SPPs) in both the matrix and at grain boundaries [5][6][7][8]. In Zircaloy-2, the major intermetallic secondary phases are Zr(Fe,Cr) 2 and Zr 2 (Fe,Ni) with size ranges 20-170 nm for Fe-Cr SPPs and 30-650 nm for Fe-Ni SPPs [9].…”

Section: Introductionmentioning

confidence: 99%

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Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy

Harte

Topping

Frankel

et al. 2017

Journal of Nuclear Materials

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A. Harte et al., Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy J. Nucl. Mater. Accepted Jan. 2017 Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy (Fe,Ni). This is accomplished through ultra-high spatial resolution scanning transmission electron microscopy and the use of energy-dispersive X-ray spectroscopic methods. Fe-depletion is observed from both SPP types after irradiation with both irradiative species, but is heterogeneous in the case of Zr(Fe,Cr) 2 , predominantly from the edge region, and homogeneously in the case of Zr 2 (Fe,Ni). Further, there is evidence of a delay in the dissolution of the Zr 2 (Fe,Ni) SPP with respect to the Zr(Fe,Cr) 2 . As such, SPP dissolution results in matrix supersaturation with solute under both irradiative species and proton irradiation is considered well suited to emulate the effects of neutron irradiation in this context. The mechanisms of solute redistribution processes from SPPs and the consequences for irradiation-induced growth phenomena are discussed.

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Section: Spp Dissolution and Amorphisationmentioning

confidence: 93%

Section: Introductionmentioning

confidence: 99%

Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy

Harte

Topping

Frankel

et al. 2017

Journal of Nuclear Materials

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“…Table 1). Among the literature many reports exist of both the cubic C15 [13][14][15][16][17][18] and the two hexagonal C14 and C36 [13,[16][17][18][19][20][21][22][23] Laves phases. Due to the nominal composition of commercial alloys, these SPPs have mostly been identified as Zr(Cr,Fe) 2 and Zr(Nb,Fe) 2 , however, they are also known to form with Mo and V additions [13,[24][25][26][27].…”

Section: Crystallography Of Intermetallic Phasesmentioning

confidence: 99%

Hydrogen solubility in zirconium intermetallic second phase particles

Burr

Murphy

Lumley

et al. 2013

Journal of Nuclear Materials

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The enthalpies of solution of H in Zr binary intermetallic compounds formed with Cu, Cr, Fe, Mo, Ni, Nb, Sn and V were calculated by means of density functional theory simulations and compared to that of H in α-Zr. It is predicted that all Zr-rich phases (formed with Cu, Fe, Ni and Sn), and those phases formed with Nb and V, offer lower energy, more stable sites for H than α-Zr. Conversely, Mo and Cr containing phases do not provide preferential solution sites for H. In all cases the most stable site for H are those that offer the highest coordination fraction of Zr atoms. Often these are four Zr tetrahedra but not always. Implications with respect to H-trapping properties of commonly observed ternary phases such as Zr(Cr,Fe) 2 , Zr 2 (Fe,Ni) and Zr(Nb,Fe) 2 are also discussed.

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“…(11) shows what kind of perturbations in the oxide film can be stabilized with one or another alloying element. Assume that some external factors lead to enhancement of perturbations of the oxide/metal interface at a rate higher than decrements in Eq.…”

Section: Basic Equations Theoretical Analysismentioning

confidence: 99%

“…Kuwae et al [11] suggested that hydrogen gas could accumulate at the oxide/metal interface due to migration of protons being released from the water molecules and balancing the charge transport in low-conductivity ZrO 2 . When the H 2 pressure exceeds the mechanical strength of zirconia, the film breaks and nodular corrosion is initiated.…”

Section: Possible Mechanisms Of Nodular Corrosionmentioning

confidence: 99%