Determination of mechanical behavior of U3Si2 nuclear fuel by microindentation method

Metzger, Kathryn E.; Knight, Travis W.; Roberts, Elwyn; Huang, Xinyu

doi:10.1016/j.pnucene.2017.05.007

Cited by 38 publications

(15 citation statements)

References 9 publications

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“…U 3 Si 2 , USi 2 ) as alternatives to conventional UO 2 fuel due to an increase in uranium density and a larger thermal conductivity in the former materials, potentially allowing prolonged generation of energy from nuclear fuels. [31][32][33] Given historical experimental and computational limitations, early reports of f-element silicon chemistry lack in-depth analysis of the bonding and properties of the M-Si linkage compared to what can be done now; a higher level of analysis has only started to be practicable recently and these fundamental studies are the necessary rst step for this eld to develop further. The increasing rate of development in felement silicon chemistry in the last two decades has provided the motivation for this perspective; the heavier tetrels are discussed herein to inspire the future development of the felement chemistry of these elements also, but silicon remains the focus.…”

Section: Introductionmentioning

confidence: 99%

f-Element silicon and heavy tetrel chemistry

2020

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Section: Introductionmentioning

confidence: 99%

f-Element silicon and heavy tetrel chemistry

2020

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“…These observations are very probably a direct consequence of the grain size of the arc-melted samples. Moreover, as proved by Metzger et al [52] by microindentation, cracks propagate through grains, meaning that fragmentation is mainly intragranular. That is why, in the "slow" cooled ingots, particles can be found that include two grains separated by a grain boundary, as the one pointed by white arrow in Fig.…”

Section: Impact Of Fabrication Process On the Powder And Plate Characteristicsmentioning

confidence: 88%

From arc-melted ingot to MTR fuel plate: A SEM/EBSD microstructural study of U3Si2

Havette

Iltis

Palancher

et al. 2020

Journal of Nuclear Materials

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U 3 Si 2 /Al fuel plates are widely used in Material Testing Reactors (MTRs) as Low Enriched Uranium driver fuel. In this paper, a reinvestigation of the microstructure of U 3 Si 2 particles is proposed to take full advantage of the new capabilities offered by Electron BackScattered Diffraction (EBSD) techniques.Using EBSD we demonstrate that most particles are single crystalline in as-fabricated plates. To understand this characteristic, linked to the microstructure of the starting material, an in-depth study of U 3 Si 2 ingots produced by arc-melting was performed at a laboratory scale; they were extensively characterized by EBSD, scanning electron microscope, energy dispersive spectroscopy and X-ray diffraction. It is shown that U 3 Si 2 grain may be large (up to several thousands of micrometers) and that they exhibit a strong preferential orientation, linked to the axial thermal gradient created in the arcmelting chamber. A significant impact of the cooling rate after arc-melting on the ingot microstructure is noticed: grains are smaller and more columnar when the cooling rate is high. A deviation from 3U/2Si stoichiometry caused for example by impurities induces the formation of a secondary phase, which exhibits a square spiral morphology.We then demonstrate that the cooling rate of U 3 Si 2 ingots has a direct influence on the characteristics of the powders obtained by crushing these ingots. Indeed the powder obtained from "slow" cooled ingots is found very close to the powder used for industrial MTR plates. On the contrary particles obtained from "fast" cooled ingots, are polycrystalline and more resistant to crushing. Thus, this work provides significant advances both in the characterisation of technological products like U 3 Si 2 /Al MTR plates and in more basic knowledge about the U 3 Si 2 phase formation.

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“…Peningkatan densitas bahan bakar nuklir dari 2,96 gU/cm 3 menjadi 4,8 gU/cm 3 salah satunya bertujuan untuk peningkatan efisiensi manajemen bahan bakar melalui penyesuaian periode refuelling menjadi lebih lama. Peningkatan densitas uranium juga akan berdampak terhadap integritas mekanik kelongsong dan stabilitas geometri, sehingga diperlukan pengujian pasca iradiasi untuk mengevaluasi unjuk kerja selama iradiasi di dalam teras RSG-GAS [1]- [3].…”

Section: Pendahuluanunclassified

“…Uji Pasca Iradiasi Pelat Elemen Bakar U3Si2/Al Densitas 4,8 gU/cm 3 Pada Burnup 60%: Pengamatan Visual, Radiografi Sinar-X dan Analisis Citra ((Rohmad Sigit, Refa Artika, Helmi Fauzi Rahmatullah, Sri Ismarwanti, Aslina Br. Ginting…”

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UJI PASCA IRADIASI PELAT ELEMEN BAKAR U3Si2/Al DENSITAS 4,8 gU/cm3 PADA BURNUP 60%: PENGAMATAN VISUAL, RADIOGRAFI SINAR-X DAN ANALISIS CITRA

Sigit

Artika

Rahmatullah

et al. 2022

urania

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UJI PASCA IRADIASI PELAT ELEMEN BAKAR U3Si2/Al DENSITAS 4,8 gU/cm3 PADA BURNUP 60%: PENGAMATAN VISUAL, RADIOGRAFI SINAR-X DAN ANALISIS CITRA. Pengembangan bahan bakar U3Si2/Al densitas tinggi telah dilakukan melalui peningkatan densitas bahan bakar nuklir dari 2,96 gU/cm3 menjadi 4,8 gU/cm3. Peningkatan densitas uranium memiliki dampak terhadap integritas mekanik kelongsong dan stabilitas geometri, sehingga diperlukan pengujian pascairadiasi. Pengujian pascairadiasi yang dilakukan meliputi pengamatan visual, uji radiografi sinar-X dan analisis citra pada Pelat Elemen Bakar (PEB). Pengamatan visual sepanjang permukaan PEB dilakukan menggunakan periskop yang terdedikasi di operating area hot cell 102 dan didokumentasikan dengan bantuan kamera melalui jendela hot cell. Pengujian radiografi sinar-X dilakukan pada tegangan 150 kV dan kuat arus 1500 µA. Citra yang dihasilkan dianalisis lebih lanjut menggunakan software ImageJ. Pengamatan visual tidak menemukan indikasi cacat permukaan, lapisan oksida yang berlebih, swelling, blister, maupun cacat permukaan lainnya. Interpretasi citra radiografi sinar-X menunjukkan profil bahan bakar yang homogen, tidak menemukan indikasi cacat sub-permukaan, serta menghasilkan profil burn up yang sesuai dengan hasil pengujian gamma scanning. Berdasarkan hasil pengujian tak merusak, secara keseluruhan PEB U3Si2/Al densitas 4,8 gU/cm3 selama iradiasi di teras RSG-GAS menunjukkan kinerja yang cukup baik.Kata kunci: Uji pascairadiasi, PEB U3Si2/Al, pengamatan visual, radiografi sinar-X, analisis citra

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Determination of mechanical behavior of U3Si2 nuclear fuel by microindentation method

Cited by 38 publications

References 9 publications

f-Element silicon and heavy tetrel chemistry

f-Element silicon and heavy tetrel chemistry

From arc-melted ingot to MTR fuel plate: A SEM/EBSD microstructural study of U3Si2

UJI PASCA IRADIASI PELAT ELEMEN BAKAR U3Si2/Al DENSITAS 4,8 gU/cm3 PADA BURNUP 60%: PENGAMATAN VISUAL, RADIOGRAFI SINAR-X DAN ANALISIS CITRA

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