Influence of additive elements on the terminal solid solubility of hydrogen for Zirconium alloy

Setoyama, Daigo; Matsunaga, Junji; Ito, Masato; Muta, Hiroaki; Kurosaki, Ken; Uno, Masayoshi; Yamanaka, Shinşuke; Takeda, Kenta; Ishii, Yoshinori

doi:10.1016/j.jnucmat.2005.04.057

Cited by 15 publications

(10 citation statements)

References 15 publications

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“…Is this the amount of hydrogen that could be dissolved in the Zr-based solid solution at a given temperature, or the overall hydrogen distributed among solid solution, precipitates of second phases (typically Zr 2 M, FCC, and hexagonal C14 Laves phases [8,9]), and the hydride phase? If the former definition is correct, then the hydride solvus curve should be different for Zr-2 and Zr-4 as a function of temperature.…”

Section: Introductionmentioning

confidence: 99%

Modeling of Some Physical Properties of Zirconium Alloys for Nuclear Applications in Support of UFD Campaign

Glazoff¹

2013

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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 fuel clad oxidation resistance during off-normal temperature excursions. Efforts have also been made to improve upon the already achieved levels of mechanical behavior and reduce hydrogen uptake. In order to facilitate the development of such novel materials, it is very important to achieve not only engineering control, but also a scientific understanding of the underlying material degradation mechanisms, both in working conditions and in storage of used nuclear fuel.This report strives to contribute to these efforts by constructing the thermodynamic models of both alloys; constructing of the respective phase diagrams, and oxidation mechanisms. A special emphasis was placed upon the role of zirconium suboxides in hydrogen uptake reduction and the atomic mechanisms of oxidation. To that end, computational thermodynamics calculations were conducted concurrently with first-principles atomistic modeling.

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Section: Introductionmentioning

confidence: 99%

Modeling of Some Physical Properties of Zirconium Alloys for Nuclear Applications in Support of UFD Campaign

Glazoff¹

2013

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“…• Zirconium alloys such as Zircaloy and Zr-Nb alloys have been widely used in the fuel cladding of nuclear reactors such as light-water nuclear reactors (LWRs) and Canadian deuterium uranium reactors (CANDUs). In recent years, hydrogen behavior has been examined in detail to achieve the extended burn-up of nuclear fuels [4][5][6][7][8][9]. Zirconium alloys are hydrogenated in the reactors, followed by the production of zirconium hydrides; this causes problems such as embrittlement.…”

Section: Introductionmentioning

confidence: 99%

Effect of electronegativity on the mechanical properties of metal hydrides with a fluorite structure

Ito¹,

Setoyama²,

Matsunaga³

et al. 2006

Journal of Alloys and Compounds

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“…A study using the DSC technique was carried out by Setoyama et al [41] on the solvus for unalloyed Zr, Zircaloy-2, and Zr-M (M = Fe, Sn, Cr, Ni) materials for use in integrity assessments of these as choices for fuel cladding material. Only TSSD was measured because of its better reproducibility.…”

Section: Effect Of Manufacturing Variables Microstructure And/or Comentioning

confidence: 99%

Experimental Results and Theoretical Interpretations of Solvus Relationships in the Zr–H System

Püls¹

2012

The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components

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Influence of additive elements on the terminal solid solubility of hydrogen for Zirconium alloy

Cited by 15 publications

References 15 publications

Modeling of Some Physical Properties of Zirconium Alloys for Nuclear Applications in Support of UFD Campaign

Modeling of Some Physical Properties of Zirconium Alloys for Nuclear Applications in Support of UFD Campaign

Effect of electronegativity on the mechanical properties of metal hydrides with a fluorite structure

Experimental Results and Theoretical Interpretations of Solvus Relationships in the Zr–H System

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