Garuda - Garba Rujukan Digital

PENGARUH ROL DINGIN TERHADAP SIFAT MEKANIK MATERIAL AL 6061-T6 Saga Octadamailah; Dwi Marta Nurjaya; Supardjo Suparjdo; Ganisa Kurniati Suryaman
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 27, No 1 (2021): Februari, 2021
Publisher : website

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2021.27.1.6339

PENGARUH PROSES PENGEROLAN DINGIN TERHADAP SIFAT MEKANIK MATERIAL AL 6061-T6. Proses pembuatan pelat tutup dan pelat bingkai untuk pelat elemen bakar reaktor G.A. Siwabessy dilakukan dengan cara dirol dingin, sehingga dicapai ketebalan yang diinginkan. Pada penelitian sebelumnya, proses pengerolan dingin pada material AlMg2 menyebabkan perubahan sifat mekanik, dimana material menjadi lebih ulet dan kekuatan tariknya menurun. Pada bahan bakar densitas tinggi, material kelongsong Al 6061-T6 akan digunakan untuk menggantikan material kelongsong sebelumnya, yaitu AlMg2. Tujuan dari penelitian ini adalah untuk mengetahui perubahan sifat mekanik dari material Al 6061-T6 hasil pengerolan. Untuk melihat perubahan sifat mekanik yang terjadi, dilakukan uji tarik, pengamatan mikrostruktur dan struktur kristal. Hasil uji tarik menunjukkan bahwa kekuatan tarik, modulus elastis dan kekuatan luluh cenderung naik seiring dengan besarnya derajat reduksi ketebalan. Meskipun demikian, kekuatan luluh dari hasil pengujian cukup rendah. Rasio antara kekuatan luluh dan kekuatan tariknya hanya 0,7. Dari hasil pemindaian menggunakan difraksi sinar-X diketahui bahwa proses pengerolan dapat menyebabkan penghalusan ukuran kristalit. Kesimpulan dari penelitian ini secara umum adalah proses pengerolan dapat meningkatkan sifat mekanik material Al 6061-T6.Kata kunci: Pengerolan dingin, sifat mekanik, Al 6061-T6, kekuatan tarik, modulus elastis.

PENGARUH ROL DINGIN TERHADAP SIFAT MEKANIK MATERIAL AL 6061-T6 Saga Octadamailah; Dwi Marta Nurjaya; Supardjo; Ganisa Kurniati Suryaman
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 27 No. 1 (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.2021.27.1.6339

PENGARUH PROSES PENGEROLAN DINGIN TERHADAP SIFAT MEKANIK MATERIAL AL 6061-T6. Proses pembuatan pelat tutup dan pelat bingkai untuk pelat elemen bakar reaktor G.A. Siwabessy dilakukan dengan cara dirol dingin, sehingga dicapai ketebalan yang diinginkan. Pada penelitian sebelumnya, proses pengerolan dingin pada material AlMg2 menyebabkan perubahan sifat mekanik, dimana material menjadi lebih ulet dan kekuatan tariknya menurun. Pada bahan bakar densitas tinggi, material kelongsong Al 6061-T6 akan digunakan untuk menggantikan material kelongsong sebelumnya, yaitu AlMg2. Tujuan dari penelitian ini adalah untuk mengetahui perubahan sifat mekanik dari material Al 6061-T6 hasil pengerolan. Untuk melihat perubahan sifat mekanik yang terjadi, dilakukan uji tarik, pengamatan mikrostruktur dan struktur kristal. Hasil uji tarik menunjukkan bahwa kekuatan tarik, modulus elastis dan kekuatan luluh cenderung naik seiring dengan besarnya derajat reduksi ketebalan. Meskipun demikian, kekuatan luluh dari hasil pengujian cukup rendah. Rasio antara kekuatan luluh dan kekuatan tariknya hanya 0,7. Dari hasil pemindaian menggunakan difraksi sinar-X diketahui bahwa proses pengerolan dapat menyebabkan penghalusan ukuran kristalit. Kesimpulan dari penelitian ini secara umum adalah proses pengerolan dapat meningkatkan sifat mekanik material Al 6061-T6.

PRODUCTION OF URANIUM-MOLYBDENUM ALLOY AS A CANDIDATE FOR NUCLEAR RESEARCH REACTOR FUEL Ganisa Kurniati Suryaman; Muhammad Waziz Wildan; Supardjo; Yatno Dwi Agus Susanto
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 3 (2018): 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.2018.24.3.4685

Research and development on high density uranium for nuclear research reactor fuel is still in progress. Uranium-molybdenum alloy is one of the strongest candidates of nuclear research reactor fuel material. The properties and characteristics of U-Mo alloy is of important consideration for the selction of the fabrication techniques for the production of the fuel. In this work, uranium-molybdenum (U-Mo) alloys with varied molybdenum content have been produced succesfully by arc melting technique. The molybdenum content variations were 7 %wt, 8 %wt, 9 %wt and 10 %wt Mo. The melting process was done 5 times to achieve homogenization. Metallographic micrograph shows the presence of dendritic structure. XRD examination result affirms the presence of 2 phases of γ-U phase and d-U2Mo phase. Microhardness Vickers test shows higher hardness value for Uranium-molybdenum alloy with higher molybdenum content.

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

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.

PHASE CHANGES ON 4H AND 6H SIC AT HIGH TEMPERATURE OXIDATION Jan Setiawan; Ganisa Kurniati Suryaman; Masrukan
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 2 (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.2016.22.2.3091

The oxidation on two silicon carbide contains 6H phase and contains 6H and 4H phases has been done. Silicon carbide is ceramic non-oxide with excellent properties that potentially used in industry. Silicon carbide is used in nuclear industry as structure material that developed as light water reactor (LWR) fuel cladding and as a coating layer in the high temperature gas-cooled reactor (HTGR) fuel. In this study silicon carbide oxidation simulation take place in case the accident in primary cooling pipe is ruptured. Sample silicon carbide made of powder that pressed into pellet with diameter 12.7 mm and thickness 1.0 mm, then oxidized at temperature 1000 oC, 1200 oC dan 1400 oC for 1 hour. The samples were weighted before and after oxidized. X-ray diffraction con-ducted to the samples using Panalytical Empyrean diffractometer with Cu as X-ray source. Diffraction pattern analysis has been done using General Structure Analysis System (GSAS) software. This software was resulting the lattice parameter changes and content of SiC phases. The result showed all of the oxidation samples undergoes weight gain. The 6S samples showed the highest weight change at oxidation temperature 1200 oC, for the 46S samples showed increasing tendency with the oxidation temperature. X-ray diffraction pattern analysis showed the 6S samples contain dominant phase 6H-SiC that matched to ICSD 98-001-5325 card. Diffraction pattern on 6S showed lattice parameter, composition and crystallite size changes. Lattice parameters changes had smaller tendency from the model and before oxidation. However, the lowest silicon carbide composition or the highest converted into other phases up to 66.85 %, occurred at oxidation temperature 1200 oC. The 46S samples contains two polytypes silicon car-bide. The 6H-SiC phases matched by ICSD 98-016-4972 card and 4H-SiC phase matched by ICSD 98-016-4971 card. Diffraction pattern on 46S also showed lattice parameter, composition and crystallite size changes. The lattice parameter changes not significant. For 6S and 46S samples at 1400 oC, the 6H-SiC phase changes into other phases more than 50 % from its original weight percentage.

OPTIMASI PEMISAHAN SESIUM DI DALAM PELAT ELEMEN BAKAR TIPE U3Si2/Al PASCA IRADIASI MENGGUNAKAN METODE PENGENDAPAN KLOROPLATINAT Arif Nugroho; Komar Sutriah; Sri Mulijani; Triyono Basuki; Ahmad Ade Rofiqi; Noviarty; Helmi Fauzi Rahmatullah; Ganisa Kurniati Suryaman; Guswardani
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 30 No. 1 (2024): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/urania.2024.8679

Several methods for separating fission product ¹³⁷Cs from uranium isotopes (²³⁸U, ²³⁵U, ²³⁶U, and ²³⁴U) in U₃Si₂/Al fuel have been widely developed. Optimization and separation were performed using the chloroplatinate precipitation to establish a new cesium (Cs) separation method. The method developed in this research offers the potential to achieve higher-purity cesium precipitates. This study aims to develop a method of separating the ¹³⁷Cs isotope from U₃Si₂/Al fuel element plates (PEB) using chloroplatinate reagents. The procedure involves dissolving the pre-irradiation U₃Si₂/Al PEB and adding several elements such as Sm, Sr, Cs, and Nd to represent the composition of pre-irradiation PEB, simulating its original condition. The cesium precipitation process in the supernatant solution was carried out by adding HCl and NaOH to separate impurities from cesium. The precipitation was conducted by adding H₂PtCl₆ to precipitate and isolate cesium from other elements. The precipitation process was optimized by varying the temperature and precipitation time. The optimum precipitation conditions were achieved at a temperature of -3°C and a time of 10 minutes, resulting in a Cs2PtCl6 precipitate weighing 0.3361 g. XRD and SEM analyses were used to complement and verify the cesium separation results using the chloroplatinate precipitation method, showing a uniform distribution of all elements. The purity of the Cs2PtCl6 precipitate obtained was 100%, with a diffractogram pattern identical to the reference.

Title

Found 6 Documents
Search

Abstract

Abstract

Abstract

Abstract

Abstract

Abstract

Title Search

Found 6 Documents Search

Abstract

Abstract

Abstract

Abstract

Abstract

Abstract

Title

Found 6 Documents
Search