2013
DOI: 10.2172/1097164
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Modeling of Some Physical Properties of Zirconium Alloys for Nuclear Applications in Support of UFD Campaign

Abstract: Zirconium-based alloys Zircaloy-2 and Zircaloy-4 are widely used in the nuclear industry as cladding materials for light water reactor (LWR) fuels. These materials display a very good combination of properties such as low neutron absorption, creep behavior, stress-corrosion cracking resistance, reduced hydrogen uptake, corrosion and/or oxidation, especially in the case of Zircaloy-4. However, over the last couple of years, in the post-Fukushima Daiichi world, energetic efforts have been undertaken to improve f… Show more

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Cited by 10 publications
(8 citation statements)
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“…In Table 5, the values of the lattice parameter of each cell vary little from one hydride to another. Our results agree very well with the calculations made by Glazoff [41] and with the available experimental data. The hydride formation enthalpy, E x f , is calculated as Glasoff [41].…”
Section: Zirconium Hydridessupporting
confidence: 92%
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“…In Table 5, the values of the lattice parameter of each cell vary little from one hydride to another. Our results agree very well with the calculations made by Glazoff [41] and with the available experimental data. The hydride formation enthalpy, E x f , is calculated as Glasoff [41].…”
Section: Zirconium Hydridessupporting
confidence: 92%
“…Our results agree very well with the calculations made by Glazoff [41] and with the available experimental data. The hydride formation enthalpy, E x f , is calculated as Glasoff [41].…”
Section: Zirconium Hydridessupporting
confidence: 92%
See 1 more Smart Citation
“…In this system in particular, it has been found that H preferentially occupies tetrahedral sites in the Zr lattice, rather than other sites 15,21,22 . Some works have focused on the octahedral site as the main location for H atom solution, however such works appear to be in the minority 23,24 . It has been theoretically predicted that the FCT structure of ZrH 2 can have another stable phase for c/a ¿ 1 25,36 .…”
Section: Introductionmentioning
confidence: 99%
“…[1][2][3][4] Since cadmium has a high neutron absorption cross section and also causes stress corrosion cracking in these alloys, the maximum allowed limit of cadmium in these alloys is restricted to 0.5 mg g À1 for nuclear applications. These materials exhibit a very good combination of properties such as low neutron absorption, high creep resistance, stress-corrosion cracking resistance, reduced hydrogen uptake, corrosion and/or oxidation resistance, especially in the case of Zircaloy-4.…”
Section: Introductionmentioning
confidence: 99%