Fabrication of U-10 wt.%Zr Metallic Fuel Rodlets for Irradiation Test in BOR-60 Fast Reactor

Kim, Kihwan; Kim, Jong-Hwan; Oh, Seok Jin; Lee, Jung Won; Lee, Ho-Jin; Lee, Chan-Bock

doi:10.1155/2016/4385925

Cited by 3 publications

(1 citation statement)

References 18 publications

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“…Hal ini terkait dengan siklus bahan bakar tertutup untuk menangani sejumlah kecil unsur aktinida dan mengurangi jumlah bahan bakar nuklir bekas. Bahan bakar logam U-Zr memiliki beberapa keunggulan antara lain proses fabrikasi yang sederhana, ekonomi neutron baik, konduktivitas termal yang baik, kompatibilitas antara pendingin sodium dengan bahan bakar baik dan keselamatan pasif yang melekat [2]. Dari pengalaman beberapa peneliti tentang pengoperasian SFR di seluruh dunia dapat mengindikasikan bahwa rancangan bahan bakar logam yang ada dimasa lalu tidak dapat beroperasi dengan handal pada temperatur tinggi.…”

Section: Pendahuluanunclassified

Identifikasi Fasa Pelet Bahan Bakar U-ZrHx Hasil Proses Sinter Dengan Atmosfer Nitrogen

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Setiawan

Biyantoro

2017

urania

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ABSTRAK IDENTIFIKASI FASA PADA PELET BAHAN BAKAR U-ZrH x HASIL PROSES SINTER DENGAN ATMOSFER NITROGEN.Identifikasi fasa bahan bakar pelet U-ZrH x hasil proses sintering dengan atmosfer nitrogen telah dilakukan. Proses sintering dbertujuan untuk mendapatkan pelet yang mempunyai densitas lebih tinggi sehingga memenuhi persyaratan untuk digunakan sebagai bahan bakar Pressurized Water Reactor (PWR). Hasil penelitian ini dapat digunakan untuk mengetahui perubahan fasa dan densitas pelet U-ZrH x pada berbagai konsentrasi Zr setelah dikenakan proses sintering pada berbagai temperatur. Bahan bakar U-ZrH x untuk PWR dibuat berbentuk pelet dan perlu disinter untuk menaikkan densitasnya. Mula-mula dibuat pelet dari serbuk U-ZrH x dengan komposisi Zr berturut-turut sebesar 35, 45 dan 55 %berat melalui proses pengepresan pada tekanan 509-637 MPa. Pelet U-ZrH x mentah disinter dalam suasana gas nitrogen pada temperatur 1200 °C dan 1300 °C dengan waktu sinter dibuat tetap selama satu jam. Pelet U-ZrH x sinter dianalisis fasanya menggunakan teknik difraksi sinar-X (XRD) dan data yang diperoleh dievaluasi menggunakan software HighScore Plus. Hasil pengolahan data menunjukkan terbentuknya fasa seperti fasa U(ZrH 2 ), UO 3 , UO 2 , dan Zr. Fasa UO 2 , dan Zr kemudian dianalisis karakteristiknya seperti densitas, parameter kisi dan persentase beratnya. Hasil penelitian ini diharapkan diperoleh U-ZrH x yang mempunyai densitas tinggi tanpa terbentuknya banyak fasa. Hasil pengujian densitas menunjukkan bahwa logam zirkonium dan oksida UO 2 mengalami penurunan densitas apabila temperatur sintering dinaikkan dari 1200 °C menjadi 1300 °C. Densitas total tertinggi diperoleh pada pelet U-55ZrH x yang disinter pada temperatur 1200 °C yakni sebesar 8,9187 g/cm 3 . Dari hasil analisis komposisi menunjukkan bahwa persentase logam zirkonium maupun uranium dioksida mendekati persentase yang direncanakan apabila pelet disinter pada temperatur 1300 sedangkan parameter kisinya mengalami kenaikan. Sementara itu dari perhitungan persen berat diperoleh logam zirkonium maupun uranium dioksida mempunyai persen berat yang sesuai dengan perhitungan teoritis bila disinter pada temperatur 1300 °C.

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Section: Pendahuluanunclassified

Identifikasi Fasa Pelet Bahan Bakar U-ZrHx Hasil Proses Sinter Dengan Atmosfer Nitrogen

Masrukan

Setiawan

Biyantoro

2017

urania

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Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction

et al. 2021

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Summary This study compares three fuel types using neutronic analysis for use in a sodium‐cooled fast reactor (SFR) design with a modified CANDLE (Constant Axial shape of Neutron flux, nuclide densities, and power shape During Life of Energy production) radial shuffling strategy. SFR is one type of generation IV reactor that is currently under investigation for commercial implementation. In this study, the SFR design utilizes natural uranium as the fuel input. The designed reactor core has a two‐dimensional cylindrical geometry for each fuel mixed oxide (MOX), uranium‐plutonium nitride ([U‐Pu]N), and uranium‐plutonium zirconium ([U‐Pu]Zr). A radial shuffling strategy, using natural uranium as the fuel input, is applied to the SFR to manage the nuclear fuel burn‐up process of the long‐life reactor. This strategy is called the modified CANDLE burn‐up scheme. The reactor core is divided into 10 regions with equal volume to represent the 10 years that the reactor operates without refueling. Initially, the first (innermost) region of the reactor core is filled with natural uranium fuel. The result of the burn‐up from the first region is then shuffled into the second region. The third region is the result of the burn‐up that is shuffled from the second region, and so on. This mechanism only requires natural uranium as the input for each 10‐year fuel cycle. In this study, the fuel movement scheme is examined for three fuels. Global neutronic parameters, such as the multiplication factors and burn‐up analyses, are observed and optimized. Overall, for an output power of 500 MWth and an active core radius of 110 cm and height of 210 cm, the study indicates that (U‐Pu)N is the optimal fuel to be applied in the SFR with a modified CANDLE burn‐up scheme. (U‐Pu)Zr reaches a critical condition at an output power of 500 MWth with an active core radius of 130 cm and a height of 210 cm; whereas criticality for MOX is achieved at an output power of 1500 MWth with an active core radius of 210 cm and a height of 210 cm.

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REVIEW OF METAL FUEL U-10 wt. % Zr STUDIES

Kurina

Frolova

Chesnokov

2021

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants

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The article provides a review of well-known foreign scientific publications devoted to the study of the properties of metallic nuclear fuel based on U-Zr, in composition close to U 10 wt. % Zr, which is widely used in reactors. Differences in the microstructure of fuel made by different methods: extrusion and casting - are considered. The effect of thermal annealing on the change in the microstructure of the alloy is shown. The photographs obtained using optical and electron microscopes are presented, as well as crystallographic data for two phases: α-U and δ-UZr2. The known literature data indicate that the density of uranium-rich U-Zr alloys corresponds to the rule of mixtures. The theoretical density of the alloy U-10 wt. % Zr (U-22.5 at. % Zr) should be taken as 16.2 g/cm3. The results of thermophysical studies of 10 wt. % Zr fuel using the method of differential scanning calorimetry (DSC) are presented. Data on measurements of thermal expansion of U-Zr alloys, as well as thermal conductivity are presented. Most of the thermal conductivity data are either calculated from the measured density, specific heat and thermal diffusivity, or obtained from simulations.

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Fabrication of U-10 wt.%Zr Metallic Fuel Rodlets for Irradiation Test in BOR-60 Fast Reactor

Cited by 3 publications

References 18 publications

Identifikasi Fasa Pelet Bahan Bakar U-ZrHx Hasil Proses Sinter Dengan Atmosfer Nitrogen

Identifikasi Fasa Pelet Bahan Bakar U-ZrHx Hasil Proses Sinter Dengan Atmosfer Nitrogen

Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction

REVIEW OF METAL FUEL U-10 wt. % Zr STUDIES

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