Irradiation behaviour of uranium silicide compounds

Finlay, M. Ross; Hofman, G.L.; Snelgrove, J.L.

doi:10.1016/j.jnucmat.2003.11.009

Cited by 100 publications

(68 citation statements)

References 12 publications

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“…(11) and (46)) and density (Eq. (45)) at the knee compared with data for mini-plate A224 [15]. The calculated quantities are in agreement with the measured values.…”

Section: Bubble Growth At the Kneesupporting

confidence: 78%

“…Fig. 6 shows the calculated fraction of generated gas in SEM-observable bubbles at the knee (i.e., (11) compared with data taken at various fission densities [15]. The general agreement between the calculated and measured quantities supports the position that the gas in bubbles at times subsequent to the formation of the knee is relatively constant.…”

Section: Bubble Growth At the Kneementioning

confidence: 53%

“…4 shows the fission density at which the knee occurs obtained from a numerical solution of Eqs. (8)- (11) using Mathematica (http://www.wolfram.com) and the value of R ds ¼ 0:42 (derived in Section 2.3.2) as a function of fission rate compared with the experimentally estimated quantities [15]. The uncertainty in the experimental values is estimated to be ±20%.…”

Section: Bubble Growth At the Kneementioning

confidence: 99%

See 2 more Smart Citations

A model for fission-gas-bubble behavior in amorphous uranium silicide compounds

Rest

2004

Journal of Nuclear Materials

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“…(11) and (46)) and density (Eq. (45)) at the knee compared with data for mini-plate A224 [15]. The calculated quantities are in agreement with the measured values.…”

Section: Bubble Growth At the Kneesupporting

confidence: 78%

Section: Bubble Growth At the Kneementioning

confidence: 53%

Section: Bubble Growth At the Kneementioning

confidence: 99%

See 1 more Smart Citation

A model for fission-gas-bubble behavior in amorphous uranium silicide compounds

Rest

2004

Journal of Nuclear Materials

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“…In order to partition Mo into the more stable binary aluminide phases, the solubility limit must be increased. Experimental evidence has shown [3,27,52,[56][57][58][59][60][61][62] that the introduction of Si into the Al reduces the thickness and changes the phase constituents of the interdiffusion layer. There is strong evidence of the absence of the U 6 Mo 4 Al 43 phase [52] in the interdiffusion layer due to the fact that UAl 3 phase can accommodate Mo as (U,Mo)(Al,Si) 3 with extended solubility or the mechanism that results in the development of the U 6 Mo 4 Al 43 phase may be disrupted.…”

Section: Discussionmentioning

confidence: 99%

Phase Constituents and Microstructure of Interaction Layer Formed in U-Mo Alloys vs Al Diffusion Couples Annealed at 873 K (600 °C)

Perez

Keiser

Sohn

2011

Metall Mater Trans A

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U-Mo dispersion and monolithic fuels are being developed to fulfill the requirements for research reactors, under the Reduced Enrichment for Research and Test Reactors program. In dispersion fuels, particles of U-Mo alloys are embedded in the Al-alloy matrix, while in monolithic fuels, U-Mo monoliths are roll bonded to the Al-alloy matrix. In this study, interdiffusion and microstructural development in the solid-to-solid diffusion couples, namely, U-15.7 at. pct Mo (7 wt pct Mo) vs pure Al, U-21.6 at. pct Mo (10 wt pct Mo) vs pure Al, and U-25.3 at. pct Mo (12 wt pct Mo) vs pure Al, annealed at 873 K (600°C) for 24 hours, were examined in detail. Scanning electron microscopy (SEM), transmission electron microscopy (TEM), and electron probe microanalysis (EPMA) were employed to examine the development of a very fine multiphase interaction layer with an approximately constant average composition of 80 at. pct Al. Extensive TEM was carried out to identify the constituent phases across the interaction layer based on selected area electron diffraction and convergent beam electron diffraction (CBED). The cubic-UAl 3 , orthorhombic-UAl 4 , hexagonal-U 6 Mo 4 Al 43 , and cubicUMo 2 Al 20 phases were identified within the interaction layer that included two-and three-phase layers. Residual stress from large differences in molar volume, evidenced by vertical cracks within the interaction layer, high Al mobility, Mo supersaturation, and partitioning toward equilibrium in the interdiffusion zone were employed to describe the complex microstructure and phase constituents observed. A mechanism by compositional modification of the Al alloy is explored to mitigate the development of the U 6 Mo 4 Al 43 phase, which exhibits poor irradiation behavior that includes void formation and swelling.

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“…Com base nesses fatos, selecionou-se LEU para a concentração de urânio no combustível considerado neste trabalho. Além disso, adotou-se que a densidade de urânio no combustível é de 3,2 g/cm 3 , por ser a mais comum em reatores nucleares de pesquisa [33][34][35].…”

Section: Objetivo Originalidade E Contribuiçãounclassified

Desenvolvimento de um modelo para dimensionamento da capacidade produtiva de fábricas de combustível nuclear para reatores de pesquisa

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Irradiation behaviour of uranium silicide compounds

Cited by 100 publications

References 12 publications

A model for fission-gas-bubble behavior in amorphous uranium silicide compounds

A model for fission-gas-bubble behavior in amorphous uranium silicide compounds

Phase Constituents and Microstructure of Interaction Layer Formed in U-Mo Alloys vs Al Diffusion Couples Annealed at 873 K (600 °C)

Desenvolvimento de um modelo para dimensionamento da capacidade produtiva de fábricas de combustível nuclear para reatores de pesquisa

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