The use of U3Si2/Al dispersion fuel for high power research reactors

Keiser, Dennis D.; Wachs, Daniel M.; Robinson, Adam; Williams, W. J.; Lillo, M. A.; Woolstenhulme, Nicolas E.; Moore, George A.; Jue, Jan‐Fong; Hofman, G.L.

doi:10.1016/j.jnucmat.2019.151820

Cited by 7 publications

(3 citation statements)

References 21 publications

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“…Fig 3 shows some gray contrast along the cracks in the fuel particles, that probably a penetration of Al into the cracks resulted from fuel plate compacting and rolling during fabrication [19]. Keiser Jr et al reported that U-Al-Si phase is formed along the cracks in the relatively larger fuel particles and around the smaller ones, that appeared as medium contrast phase [28]. Mirandou et al did report based on XRD and SEM result that low amount of U(Al,Si)3 phase can be formed in U3Si2-Al fuel during fabrication process [29].…”

Section: Methodsmentioning

confidence: 99%

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STUDY OF FISSION GAS BUBBLES AND INTERACTION LAYER ON IRRADIATED U3Si2-Al DENSITY OF 4.8 gU/cm3

Sihotang

Ajiriyanto

Putri

et al. 2022

urania

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STUDY OF FISSION GAS BUBBLES AND INTERACTION LAYER ON IRRADIATED U3Si2-Al DENSITY OF 4.8 gU/cm3. Uranium-silicide compound fuel dispersed in aluminium matrix (U3Si2-Al) have been used in a large number of research reactors around the world because of its excellent behavior under irradiation. This fuel also provides high uranium density with typical fuel loading up to 4.8 gU/cm3 to compensate for the reduced fissile amount in LEU. To improve the density of current U3Si2-Al (2.96 gU/cm3) used in Indonesian GA Siwabessy Multipurpose Research Reactor, U3Si2-Al dispersion fuel plate with density of 4.8 gU/cm3 (U235 ∼19.75%) had been irradiated in RSG GAS for 175 days at 15 MW power to burnup level of approximately 40%. The characterization was performed using SEM-EDS and optical microscope to study microstructure of the irradiatted fuel, largely the fission gas bubbles and the interaction layer between U3Si2 fuel and Al matrix. The average diameter of the bubbles with diameter from 0.06 to 0.55 µm was 0.21 µm. The interaction layer was identified as U(Al,Si)2,3 with thickness of approximately 1.5 µm. The relatively small fission gas bubbles and the interaction layer didn’t cause swelling on the fuel and the overall performance of the fuel plate was very good.Keyword: LEU, uranium-silicide, post-irradiation examination, interaction layer, fission gas bubbles.

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Section: Methodsmentioning

confidence: 99%

“…In Fig 6, there are no interconnections between the bubbles observed in the fuel particles. D. D. Keiser Jr stated other factor that affect fission gas behaviour such as matrix stress, burnup, fuel properties, fission gas properties, grain size, etc [28].…”

Section: Methodsmentioning

confidence: 99%

STUDY OF FISSION GAS BUBBLES AND INTERACTION LAYER ON IRRADIATED U3Si2-Al DENSITY OF 4.8 gU/cm3

Sihotang

Ajiriyanto

Putri

et al. 2022

urania

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“…Quando comparado com reatores comerciais tipo LWR, normalmente os reatores de pesquisa operam com potências reduzidas (aproximadamente dezenas de MWt), as temperaturas envolvidas são inferiores e determinados fenômenos associados com a temperatura não são tão críticos e exacerbados [121].…”

Section: Combustível De Alta Densidadeunclassified

Análise neutrônica e do comportamento sob irradiação de combustíveis tolerantes à falha

Abe¹

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ABE, Alfredo Y. Neutronic analysis and fuel performance behavior of accident tolerant fuel. 2023, 214 p. Tese (Doutorado em Tecnologia Nuclear) -Instituto de Pesquisas Energéticas e Nucleares -IPEN-CNEN/SP. São Paulo.This work presents a neutronic and fuel performance assessment and analysis of potential candidates for accident tolerant fuels (ATF). In the initial phase of the work for the bibliographic survey, a methodology based on the Technology Readiness Level (TRL) was considered to evaluate the different existing options and technologies of accident tolerant fuel. This initial phase identified possible gaps and the necessary activities to develop accident tolerant fuels at the readiness level of commercial use in nuclear power reactors.The neutronic and fuel performance evaluations and analysis of the accident tolerant fuel candidates were performed by means of computer simulations using fuel performance (TRANSURANUS) and neutronics (SERPENT) codes.

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Plasma-Chemical Synthesis and Investigation of Nano-Size Oxide Compositions Simulating Uranium-Thorium Dispersion Nuclear Fuel

2021

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The use of U3Si2/Al dispersion fuel for high power research reactors

Cited by 7 publications

References 21 publications

STUDY OF FISSION GAS BUBBLES AND INTERACTION LAYER ON IRRADIATED U3Si2-Al DENSITY OF 4.8 gU/cm3

STUDY OF FISSION GAS BUBBLES AND INTERACTION LAYER ON IRRADIATED U3Si2-Al DENSITY OF 4.8 gU/cm3

Análise neutrônica e do comportamento sob irradiação de combustíveis tolerantes à falha

Plasma-Chemical Synthesis and Investigation of Nano-Size Oxide Compositions Simulating Uranium-Thorium Dispersion Nuclear Fuel

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