Influence of hydrogen content on the strength and the presence of defects in ε-zirconium hydride

Chernikov, A. S.; Syasin, V.A.; Kostin, V.M; Boiko, E. B.

doi:10.1016/s0925-8388(01)01480-3

Cited by 9 publications

(4 citation statements)

References 1 publication

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“…Recently, zirconium hydride is included in the hydride fuels because of its excellent stability under irradiation conditions . Therefore, there are a large number of studies − devoted to the characteristics of zirconium hydrides.…”

Section: Introductionmentioning

confidence: 99%

First-Principles Study of Different Polymorphs of Crystalline Zirconium Hydride

et al. 2010

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We present a detailed study on the electronic structure, mechanical properties, phase stability, and thermodynamic properties of four polymorphs of crystalline zirconium hydride by using density functional theory within the generalized gradient approximation. An analysis of electronic structure shows that the zirconium hydrides retain metallic bonding over the whole hydrogen composition range. The calculated mechanical properties indicate that -Zr 2 H and γ-ZrH are ductile, while δ-ZrH 1.5 and ε-ZrH 2 are brittle compared with R-Zr. The hydrides change from ductile to brittle in the order of -Zr 2 H, γ-ZrH, ε-ZrH 2 , and δ-ZrH 1.5 . The formation enthalpies are negative for the four hydrides at the ambient pressure indicating that they are thermodynamically stable. Only the δ phase is thermodynamically stable in the whole pressure range. As the temperature increases, the decomposition reactions of the four hydrides are more and more favorable thermodynamically. The δ phase is thermodynamically easier to decompose than the others in the whole temperature range.

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Section: Introductionmentioning

confidence: 99%

First-Principles Study of Different Polymorphs of Crystalline Zirconium Hydride

et al. 2010

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“…As the hydrogenation continues, cracks appear around the dislocation. Chernikov 29 study the transition from δ‐ZrHx to ε‐ZrHx further supports this idea. Yamanaka 30 prepared crack free yttrium hydride at 800°C for 12 hours, then slowly cool down at the rate of 1 K/h.…”

Section: Main Problems Of Moderator Materialsmentioning

confidence: 57%

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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“…Because of its high thermal stability, high hydrogen density [4], low neutron capture cross-section, and good thermal conductivity [5][6][7], zirconium hydride became an ideal neutron moderator and was put into application in space nuclear reactor. However, hydrogen will escape from zirconium hydride in the working environment, leading to the loss of hydrogen and hence deteriorating the moderating effect of the moderator [8].…”

Section: Introductionmentioning

confidence: 99%

Hydrogen Permeation Behavior of Zirconium Nitride Film on Zirconium Hydride

et al. 2022

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Hydrogen permeation barrier plays an important role in reducing hydrogen loss from zirconium hydride matrix when used as neutron moderator. Here, a composite nitride film was prepared on zirconium hydride by in situ reaction method in nitrogen atmosphere. The phase structure, morphology, element distribution, and valence states of the composite film were investigated by XRD, SEM, AES, and XPS analysis. It was found that the composite nitride film was continuous and dense with about 1.6 μm thickness; the major phase of the film was ZrN, with coexistence of ZrO2, ZrO, and ZrN0.36H0.8; and Zr-C, Zr-O, Zr-N, O-H, and N-H bonds were detected in the film. The existence of ZrN0.36H0.8 phase and the bonds of O-H and N-H revealed that the nitrogen and oxygen in the film could capture hydrogen from the zirconium hydride matrix. The hydrogen permeation performance of nitride film was compared with oxide film by permeation reduction factor (PRF), vacuum thermal dehydrogenation (VTD), and hydrogen permeation rate (HPR) methods, and the results showed that the hydrogen permeation barrier effects of nitride film were better than that of oxide film. The zirconium nitride film would be a potential candidate for hydrogen permeation barrier on the surface of zirconium hydride.

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Influence of hydrogen content on the strength and the presence of defects in ε-zirconium hydride

Cited by 9 publications

References 1 publication

First-Principles Study of Different Polymorphs of Crystalline Zirconium Hydride

First-Principles Study of Different Polymorphs of Crystalline Zirconium Hydride

Advance in and prospect of moderator materials for space nuclear reactors

Hydrogen Permeation Behavior of Zirconium Nitride Film on Zirconium Hydride

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