Deformation of UO2 at High Temperatures
Article Properties
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LanguageEnglish
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DOI (url)
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Publication Date1971/02/01
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Indian UGC (journal)
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Refrences27
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Citations96
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R. F. CANON
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J. T. A. ROBERTS
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R. J. BEALS
Journal Categories
Technology
Chemical technology
Technology
Chemical technology
Clay industries
Ceramics
Glass
Technology
Electrical engineering
Electronics
Nuclear engineering
Materials of engineering and construction
Mechanics of materials
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Refrences
| Title | Journal | Journal Categories | Citations | Publication Date |
|---|---|---|---|---|
| Average Grain Size in Polycrystalline Ceramics | Journal of the American Ceramic Society |
| 1,506 | 1969 |
| Dependence of Flow Stress on Nonstoichiometry in Oxygen-Rich Uranium Dioxide at High Temperatures | Journal of the American Ceramic Society |
| 37 | 1969 |
| Diffusion of 233U in UO2 | Journal of the American Ceramic Society |
| 44 | 1969 |
| On the ionization of thin films by giant laser pulses | Physics Letters A |
| 2 | 1968 |
| The brittle-ductile transition in polycrystalline aluminium oxide | Philosophical Magazine | 12 | 1966 |
Citations
| Title | Journal | Journal Categories | Citations | Publication Date |
|---|---|---|---|---|
| Non-uniform fuel distribution and thermo-mechanical analysis of a 1 MW thermal power micronuclear heat pipe reactor | Heliyon | 2024 | ||
| Equibiaxial flexural strength determination of UO2 using a ball-on-ring test | Journal of Nuclear Materials |
| 2024 | |
| Micromechanical modeling of single crystal and polycrystalline UO2 at elevated temperatures | Journal of Nuclear Materials |
| 1 | 2023 |
Analysis of SMART reactor core with uranium mononitride for prolonged fuel cycle using OpenMC | Kerntechnik |
| 2022 | |
Spatial Series and Fractal Analysis Associated with Fracture Behaviour of UO2 Ceramic Material | Fractal and Fractional |
| 2 | 2022 |
Citations Analysis
The category
Technology: Electrical engineering. Electronics. Nuclear engineering: Materials of engineering and construction. Mechanics of materials 56
is the most commonly referenced area in studies that cite this article. The first research to cite this article was titled Nature of brittle-to-ductile transition in UO2-20 wt% PuO2 nuclear fuel and was published in 1971. The most recent citation comes from a 2024 study titled Non-uniform fuel distribution and thermo-mechanical analysis of a 1 MW thermal power micronuclear heat pipe reactor. This article reached its peak citation in 2021, with 7 citations. It has been cited in 32 different journals, 9% of which are open access. Among related journals, the Journal of Nuclear Materials cited this research the most, with 28 citations. The chart below illustrates the annual citation trends for this article.