Modelling of hydrogen absorption by zirconium alloys during high temperature oxidation in steam

Veshchunov, M.S.; Berdyshev, A. V.

doi:10.1016/s0022-3115(98)00018-x

Cited by 26 publications

(22 citation statements)

References 5 publications

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“…In our model, hydrogen diffusion through the dense barrier oxide layer is taken as the rate-limiting step for H pickup [5][6][7] . The hydrogen diffusion follows the equation ) , (0 ≤ ≤ ( )) E represents the electric filed across the Zr oxide film and is calculated by…”

Section: Methodsmentioning

confidence: 99%

“…It is usually proposed that H pickup proceeds in three steps 4,5 . First, H 2 O molecules adsorbed at the oxide/water interface react with anion oxygen vacancies to leave protons (H + ) on the oxide surface.…”

Section: Introductionmentioning

confidence: 99%

“…Many studies have focused on understanding the transport of hydrogen through the barrier oxide layer, as this transport is often regarded as the rate-limiting step for H pickup [5][6][7] . A number of factors, including oxide morphology, alloy additive elements and local stress, play important roles in the hydrogen transport process.…”

Section: Introductionmentioning

confidence: 99%

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Continuum model for hydrogen pickup in zirconium alloys of LWR fuel cladding

Wang

Zheng

Szlufarska

et al. 2017

Journal of Applied Physics

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A continuum model for calculating the time-dependent hydrogen pickup fractions in various Zirconium alloys under steam and pressured water oxidation has been developed in this study. Using only one fitting parameter, the effective hydrogen gas partial pressure at the oxide surface, a qualitative agreement is obtained between the predicted and previously measured hydrogen pickup fractions. The calculation results therefore demonstrate that H diffusion through the dense oxide layer plays an important role in the hydrogen pickup process. The limitations and possible improvement of the model are also discussed.

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Section: Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Continuum model for hydrogen pickup in zirconium alloys of LWR fuel cladding

Wang

Zheng

Szlufarska

et al. 2017

Journal of Applied Physics

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“…A theoretical description of hydrogen uptake during steam oxidation is given in [10]. As a consequence of the high oxidation rate in the beginning, hydrogen partial pressure, p H , in the gas phase on the sample surface is relatively high in the initial phase and low in the metal:…”

Section: Introductionmentioning

confidence: 99%

“…For this phase hydrogen concentration in the metal, C m ð Þ H ; increases with oxidation time, t [10]:…”

Section: Introductionmentioning

confidence: 99%

Kinetics of Hydrogen Absorption and Release in Zirconium Alloys During Steam Oxidation

Große¹,

Steinbrueck²,

Lehmann

et al. 2008

Oxid Met

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The kinetics of hydrogen absorption during steam oxidation in Zr-Sn and Zr-Nb alloys in the temperature range of 1,000-1,400°C was investigated by neutron radiography. Hydrogen uptake can be subdivided into two steps: an initial phase and a state of equilibrium. The initial phase is controlled by the kinetics of hydrogen diffusion through the growing oxide layer. In the state of equilibrium, transport kinetics does not determine the hydrogen content of the material. An equilibrium is established between the hydrogen content of the gas environment and the metal phases. The temperature dependence of hydrogen absorption is Arrheniuslike at temperatures between 1,100 and 1,300°C.

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Advance in and prospect of moderator materials for space nuclear reactors

et al. 2021

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Summary Since 1960s, many countries led by the United States and Russia have done a lot of research on space nuclear reactor power. Moderator is an important functional component in a nuclear reactor operating with a thermal neutron spectrum. This paper reviews the moderation principle, main existing problems, research status as well as main challenges ahead and possible solutions of moderator materials in space nuclear reactor. Aiming at the problems of hydrogen cracking, the low utilization rate of nuclear fuel and hydrogen loss of moderator materials, the assumption of using high entropy alloy hydride as a moderator material is put forward. Moreover, this paper also points out the metal elements suitable for nuclear reactor, while discussing the advantages and disadvantages of several typical elements, hoping to provide a reference for the selection and fabrication of moderator materials. Highlights Sketch the moderating mechanism and the moderator selection principle. Summarize the problems and solutions in the preparation of metal hydride. Summarize the application status of zirconium hydride and yttrium hydride moderator materials. Predict the future development trend and feasible methods of moderator materials.

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Modelling of hydrogen absorption by zirconium alloys during high temperature oxidation in steam

Cited by 26 publications

References 5 publications

Continuum model for hydrogen pickup in zirconium alloys of LWR fuel cladding

Continuum model for hydrogen pickup in zirconium alloys of LWR fuel cladding

Kinetics of Hydrogen Absorption and Release in Zirconium Alloys During Steam Oxidation

Advance in and prospect of moderator materials for space nuclear reactors

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