The Diffusion of Hydrogen in Zirconium Hydride

Albrecht, W.M.; Goode, W.D.

doi:10.2172/4185688

Cited by 6 publications

(2 citation statements)

References 1 publication

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“…A comprehensive examination has been made in elements are present at temperatures far below the the Metals Processing Laboratory at M.I.T. (1)(2)(3)(4)(5) equilibrium melting point of the respective alloy into the fundamental mechanism behind the striking systems involved (6,7). This investigation has led increase in tungsten sintering rates when Group VIII to the concept of a carrier phase sintering mech-…”

Section: The Activated Sintering Of Tungsten With Group VIII Elementsmentioning

confidence: 99%

The Diffusion Coefficients for Hydrogen in β-Zirconium

Gelezunas¹,

Conn²,

Price³

1963

J. Electrochem. Soc.

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The diffusion coefficients of hydrogen in β‐zirconium were calculated from experimental hydrogen sorption curves. The results were D false(cm2/secfalse)=5.32×10−3expfalse(−8320/RTfalse) , (760°–1010°C). This relationship was independent of hydrogen concentrations (to 41 a/o H) and oxygen concentrations (to 4.2 a/o O) in β ‐zirconium. Oxygen in solid solution with zirconium and surface films on the zirconium reduced the rate of hydrogen sorption by zirconium. The effect of oxygen in solid solution with zirconium was observed to be related to the α to β transformation, while the effect of surface films was related to the hydrogen concentration at the film ‐zirconium interface.

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Section: The Activated Sintering Of Tungsten With Group VIII Elementsmentioning

confidence: 99%

The Diffusion Coefficients for Hydrogen in β-Zirconium

Gelezunas¹,

Conn²,

Price³

1963

J. Electrochem. Soc.

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“…The matrix thermal resistivity as a function of burnup is plotted in Figure 11, where FIMA, Fissions per Initial Metal Atom [29], is the unit of burnup most appropriate for this fuel. Burnup calculations for hydride fuel and equivalent parameters for meaningful comparisons to the conventional oxide fuel are discussed in detail in ref.…”

Section: Determination Of In-pile Thermal Conductivitymentioning

confidence: 99%

Irradiation effects on thermal properties of LWR hydride fuel

Terrani

Balooch

Carpenter

et al. 2017

Journal of Nuclear Materials

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Three hydride mini-fuel rods were fabricated and irradiated at the MIT nuclear reactor with a maximum burnup of 0.33% FIMA or ~5 MWd/kgU equivalent oxide fuel burnup. Fuel rods consisted of uranium-zirconium hydride (U(30wt%)ZrH1.6) pellets clad inside a LWR Zircaloy-2 tubing. The gap between the fuel and the cladding was filled with lead-bismuth eutectic alloy to eliminate the gas gap and the large temperature drop across it. Each minifuel rod was instrumented with two thermocouples with tips that are axially located halfway through the fuel centerline and cladding surface. In-pile temperature measurements enabled calculation of thermal conductivity in this fuel as a function of temperature and burnup. In-pile thermal conductivity at the beginning of test agreed well with out-of-pile measurements on unirradiated fuel and decreased rapidly with burnup.

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Zirconium Hydrides and Hafnium Hydrides

Beck¹,

Mueller²

1968

Metal Hydrides

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The Diffusion of Hydrogen in Zirconium Hydride

Cited by 6 publications

References 1 publication

The Diffusion Coefficients for Hydrogen in β-Zirconium

The Diffusion Coefficients for Hydrogen in β-Zirconium

Irradiation effects on thermal properties of LWR hydride fuel

Zirconium Hydrides and Hafnium Hydrides

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