Agoeng Kadarjono
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PEMBUATAN PELAT ELEMEN BAKAR MINI UMo-Al DENGAN DENSITAS URANIUM 6 DAN 7 gU/cm3 Supardjo .; Agoeng Kadarjono; Aslina Br. Ginting
Jurnal Teknologi Bahan Nuklir Vol 7, No 2 (2011): Juni 2011
Publisher : PTBN - BATAN

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Abstract

ABSTRAK PEMBUATAN PELAT ELEMEN BAKAR MINI U-Mo/Al DENGAN DENSITAS URANIUM 6 DAN 7 gU/cm3. Pembuatan PEB mini UMo-Al bertujuan untuk pengembangan bahan bakar U3Si2/Al dengan uranium pengayaan rendah (<20% U235). Paduan U-7Mo, U-8Mo dan U-9Mo dibuat dengan teknik peleburan menggunakan tungku busur listrik pada kondisi: media gas Ar, arus 150 A, dan setiap paduan dilakukan peleburan dengan 5 kali pengulangan. Ingot paduan U-7Mo hasil peleburan dibuat serbuk hingga diameter partikel serbuk <125 µm. Selanjutnya ditimbang serbuk U-7Mo dan matriks Al dengan perbandingan sesuai untuk densitas uranium 6 dan 7gU/cm3, dicampur dan dibentuk menjadi inti elemen bakar (IEB) mini U-7Mo/Al dengan pengepresan pada tekanan 50 bar. IEB U-7Mo/Al dimasukkan kedalam lubang frame dan kedua sisinya ditutup dengan cover, kemudian pada keempat sisi sambungannya diikat dengan las TIG sehingga membentuk paket rol. Paket rol diubah menjadi pelat elemen bakar (PEB) mini U-7Mo/Al dengan pengerolan panas pada temperatur 425 oC dan dilanjutkan pengerolan dingin hingga ketebalan ± 1,40 mm. Hasil pengujian/analisis menunjukkan bahwa: ingot paduan U-Mo cukup homogen, ulet, tidak terdapat lapisan oksida dipermukaannya dan kekerasan meningkat seiring kenaikan kadar Mo. Serbuk U-7Mo berbentuk pipih dan tidak beraturan dengan berat jenis 16,336 g/cm3. Inti elemen bakar mini U-7Mo/Al densitas uranium 6 dan 7 gU/cm3 hasil pengepresan berdimensi 25 x15 x ±2,98 mm dan 25 x15 x ±3,00 mm, tidak terdapat cacat dalam bentuk retak/crack. Data radiografi PEB. U-7Mo/Al terlihat bahwa distribusi uranium di dalam meat cukup homogen, terjadi pemanjangan pelat ±5,76 kali dengan tebal kelongsong rerata pada SJ, TG dan SD berturut-turut 0,407 mm, 0,440 mm, dan 0,425 mm dengan tebal minimum 0,302 mm di SJ. Dari seluruh data uji menunjukkan bahwa pembuatan PEB mini U-Mo/Al diperoleh hasil yang cukup baik sehingga dapat gunakan sebagai acauan untuk penelitian lebih lanjut.   Kata Kunci: paduan U-Mo, bahan bakar dispersi, inti elemen bakar U-Mo/Al, pelat elemen bakar U-Mo/Al   ABSTRACT THE MANUFACTURE OF THE UMo-Al MINI FUEL PLATE WITH URANIUM DENSITY 6 AND 7 gU/cm3. The manufacture of U-Mo/Al mini fuel plate was performed in order to develop U3Si2/Al fuel with low enrichment uranium (<20% U235). The U-7Mo, U-8Mo and U-9Mo alloys were made by smelting techniques using an electric arc furnace at the conditions: Ar gas media, current 150 A, and each alloy smelting was done with 5 repetitions. The U-7Mo alloy remelting was made of powder to the powder particle diameter <125 μm. Furthermore the U-7Mo powders and Al matrix were weighed with a ratio corresponding to 6 and 7gU/cm3 uranium density, mixed and formed into a U-7Mo/Al mini fuel core by pressing at a pressure of 50 bar. The U-7Mo/Al mini fuel core was incorporated into the frame hole and both sides were covered with a cover, and then on the fourth side seams was fastened with TIG welding to form a roll package. Package roller was converted into U-7Mo/Al mini fuel plate by hot rolling at a temperature of 425oC and continued cold rolling up to a thickness of ± 1.40 mm. Test results of analysis indicated that: ingots U-Mo alloys quite homogeneous, ductile, there was no oxide layer on the surface and the hardness increased with Mo content. The U-7Mo powders and irregularly shaped flat had specific gravity of 16.336 g/cm3. The U-7Mo/Al mini fuel core of a uranium which had densityof 6 and 7gU/cm3 as a result of the pressing had dimensions of (25 x15 x ± 2.98) mm and (25 x15 x ± 3.00) mm, there was no defect in the form of crack. Radiographic data of U-7Mo/Al mini fuel plate was seen that the distribution of uranium in the meat fairly homogeneous, there was a lengthening plate ± 5.76 times the average cladding thickness on the SJ, TG and SD respectively 0.407 mm, 0.440 mm and 0.425 mm with a minimum thickness 0.302 mm at SJ. From all the test data showed that the manufacture of U-Mo/Al mini fuel plate had shown good results so it could be used as refference for further research.  Free Terms: U-Mo alloy, dispersion fuel, the U-Mo/Al fuel core, the U-Mo/Al fuel plate
THE CONCEPTUAL DESIGN FOR LIQUID EFFLUENT TREATMENT OF UO2 KERNEL FABRICATION Erilia Yusnitha; Agoeng Kadarjono; Agus Sartono; Pertiwi Diah Winastri
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 26, No 2 (2020): Juni 2020
Publisher : website

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2020.26.2.5881

Abstract

THE CONCEPTUAL DESIGN FOR LIQUID EFFLUENT TREATMENT OF UO2 KERNEL FABRICATION. The pebble fuel for HTGR is prepared through fabrication of UO2 kernel, coated particle and spherical element fuel. In the fabrication of UO2 kernel by external gelation method, a multicomponent of liquid effluent is generated. Therefore, the liquid effluent is required to be treated for safety reason before disposed to waste storage. In this paper, the conceptual design for the liquid effluent treatment of UO2 kernel fabrication is performed with the simulation process using CHEMCAD software. CHEMCAD is a software that can be utilized for chemical process design. The results showed that the proposed conceptual design is able to separate valuable components: isopropyl alcohol (IPA) and tetrahydrofurfuryl alcohol (THFA). The flowrate of IPA product is 5.28 kg/h with purity of 0.99 in mass fraction and the flowrate of THFA product is 1.01 kg/h with purity of 0.99 in mass fraction.Keywords: liquid effluent, UO2 kernel, CHEMCAD, HTGR.
PERCOBAAN PEMBUATAN PELAT ELEMEN BAKAR U-7Mo-xSi/Al DALAM UKURAN MINI Supardjo; Agoeng Kadarjono; Isfandi; Yatno Dwi Agus Susanto; Setia Permana; Guswardani
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 3 (2019): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2019.25.3.5697

Abstract

The purpose of this study is to obtain the optimized process parameters in the fabrication of a U-7Mo-xSi/Al mini plate complying with the specifications. The process flow started with synthesizing U-7Mo-xSi alloys (x = 1%, 2%, and 3%) using depleted uranium and continued to preparing U-7Mo-xSi powder, U-7Mo-xSi/Al fuel core, and U-7Mo-xSi/Al fuel element plates. The quality of the product was determined by analyses/tests including tests of raw materials and products from each end of the process by the appropriate type of test which is commonly applied to the manufacturing process of plate type fuel. The quality of U-7Mo-xSi alloy ingots, U-7Mo-xSi powder, and U-7Mo-xSi/Al fuel core was satisfactorily good and in compliance with the specifications, indicating that the applied process parameters were appropriate. The obtained fuel element plates, however, have not satisfied the requirements especially the thickness of the cladding, where there are still several measurement points whose thickness is <0.25 mm. To obtain cladding thickness according to the required specifications, it is necessary to experiment with other rolling parameters or replacing the cladding material with material of higher hardness.
KOMPOSISI, STRUKTUR DAN DENSITAS PADUAN U-7Mo-xSi Supardjo; Agoeng Kadarjono; Jan Setiawan; Ganisa Kurniati Suryaman
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 27 No. 2 (2021): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2021.27.2.6386

Abstract

The structure of U-7Mo-xSi (x = 1, 2, and 3%) alloy was studied to obtain a new uranium alloy suitable for use as a candidate for high-density uranium research reactor fuel. The U-7Mo-xSi alloy was made by melting technique using an arc furnace. The characterization of the alloy includes chemical composition, density, and structural phases to identify the phases contained in the alloy. The hardness test was also done. The density characterization results show that U content and density of the alloy decrease with increasing of Si content in the U-7Mo-xSi alloy. On the other hand, the hardness of the alloy increases with increasing of Si content. The X-ray diffraction pattern of U-7Mo-xSi alloy was observed from diffraction angle of 25° to 95°. The results indicate the presence of U-γ, U3Si2, and U3Si2Mo phases. The higher the Si content, the more U3Si2 phase is formed and the more the hardness increases due to the formation of bonds between Si and Si.
PENGARUH UNSUR Zr TERHADAP PERUBAHAN SIFAT TERMAL BAHAN BAKAR DISPERSI U-7Mo-xZr/Al Supardjo; Agoeng Kadarjono; Boybul Boybul; Aslina Br. Ginting
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 1 (2016): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2016.22.1.2741

Abstract

Thermal properties data of nuclear fuel is required as input data to predict material properties change phenomenon during the fabrication process and irradiated in a nuclear reactor. Study the influence of Zr element in the U-7Mo-xZr/Al (x = 1%, 2% and 3%) fuel dispersion to changes in the thermal properties at various temperatures have been stiffened. Thermal analysis includes determining the melting temperature, enthalpy, and phase changes made using Differential Thermal Analysis (DTA) in the temperature range between 30 °C up to 1400 °C, while the heat capacity of U-7Mo-xZr alloy and U-7Mo-xZr/Al dispersion fuel using Differential Scanning Calorimeter (DSC) at room temperature up to 450 °C. Thermal analyst data DTA shows that Zr levels of all three compositions showed a similar phenomenon. At temperatures between 565.60 °C – 584.98 °C change becomes α + δ to α + γ phase and at 649.22 °C – 650.13 °C happen smelting Al matrix Occur followed by a reaction between Al matrix with U-7Mo-xZr on 670.38 °C – 673.38 °C form U (Al, Mo)x Zr. Furthermore a phase change α + β becomes β + γ Occurs at temperatures 762.08 °C – 776.33 °C and diffusion between the matrix by U-7Mo-xZr/Al on 853.55 °C – 875.20 °C. Every phenomenon that Occurs, entalphy posed a relative stable. Consolidation of uranium Occur in 1052.42 °C – 1104.99 °C and decomposition reaction of U (Al, Mo)x and U (Al, Zr)x becomes (UAl4, UAl3, UAl2), U-Mo, and UZr on 1328,34 °C - 1332,06 °C , The existence of Zr in U-Mo alloy increases the heat capacity of the U-7Mo-xZr/Al, dispersion fuel and the higher heat capacity of Zr levels increased due to interactions between the atoms of Zr with Al matrix so that the heat absorbed by the fuel increase.