Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir is a scientific publication platform that presents experimental research and development studies on the nuclear fuel cycle, covering radiation physics and chemistry, reactor engineering, nuclear safety and security, nuclear forensics, and radioactive waste management
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<![CDATA[PERCOBAAN PEMBUATAN PELAT ELEMEN BAKAR U-7Mo-xSi/Al DALAM UKURAN MINI ]]>
<![CDATA[Supardjo]]>;
<![CDATA[Agoeng Kadarjono]]>;
<![CDATA[Isfandi]]>;
<![CDATA[Yatno Dwi Agus Susanto]]>;
<![CDATA[Setia Permana]]>;
<![CDATA[Guswardani]]>
<![CDATA[ Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 3 (2019): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir ]]>
Publisher : <![CDATA[Badan Riset dan Inovasi Nasional ]]>
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DOI: 10.17146/urania.2019.25.3.5697
<![CDATA[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.]]>
<![CDATA[PENGARUH TOOL ROTATION SPEED TERHADAP SIFAT MEKANIK SAMBUNGAN ALUMINIUM PADUAN 6061-T6 PADA PROSES FRICTION STIR WELDING ]]>
<![CDATA[Tarmizi]]>;
<![CDATA[Riki Indrawan]]>;
<![CDATA[Irfan]]>
<![CDATA[ Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 3 (2019): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir ]]>
Publisher : <![CDATA[Badan Riset dan Inovasi Nasional ]]>
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DOI: 10.17146/urania.2019.25.3.5703
<![CDATA[Friction stir welding is a newly developed welding process in 1991, and various studies have been continuously conducted to determine parameters that can produce optimum welded joints as an alternative to fusion welding process which still shows some imperfections. The purpose of this research is to determine the effect of tool rotation speed, which is one of the important parameters in friction stir welding of 6061-T6 aluminum alloy plate with 6 mm thickness, on mechanical properties of the welded joints, where variation of rotation speed applied was 910 rpm, 1175 rpm, 1555 rpm, 1700 rpm and 2000 rpm. The results show that the welded joint resulted from a speed of 910 rpm, 1175 rpm and 1555 rpm indicate no defects and satisfy the acceptance criteria of AWS D17.3 standard. The most optimum mechanical characteristic was found for welded joint with rotation tool speed of 910 rpm because grain coarsening and dissolution of precipitate were not too significant when compared to other rotational speeds.]]>
<![CDATA[KARAKTERISASI MIKROSTRUKTUR, KEKERASAN, KOMPOSISI KIMIA DAN STRUKTUR KRISTAL LAPISAN PADA PERMUKAAN BAJA ]]>
<![CDATA[Sungkono]]>;
<![CDATA[Maman Kartaman Ajiriyanto]]>;
<![CDATA[Sri Ismarwanti]]>;
<![CDATA[Rohmad Sigit]]>
<![CDATA[ Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 3 (2019): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir ]]>
Publisher : <![CDATA[Badan Riset dan Inovasi Nasional ]]>
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DOI: 10.17146/urania.2019.25.3.5708
<![CDATA[Steel and alloys are used as structural material for nuclear reactor components and supporting equipments of hot cells. During the operation of nuclear reactors or hot cell facilities, structural materials suffer from tensile, compressive, and frictional stresses in high radiation environments and thus reduce the life time of the components. One solution for this issue is surface coating of steel with materials having high hardness, corrosion and wear resistance. The aim of this research is to obtain the characteristics of microstructure, thickness, hardness, chemical composition and crystal structure of layers on steel surface. The method used was observation with optical microscope for microstructure, vickers microhardness tester for hardness, spark spectrometry for chemical composition and X-ray diffractometry for crystal structure. The results shows that the base metal microstructure consists of fine equiaxial grains with ferrite and pearlite phases, where the metal-layer interface is clearly visible, and the compact and homogeneous layer has an average thickness of 624.071 µm. The hardness of the layer is 943 VHN. From the chemical composition it is identified that the base metal is S45C carbon steel, and the surface layer is a stable compound of chromium oxide (Cr2O3) with hexagonal crystal structure.]]>
<![CDATA[PENGARUH DIAMETER NOZZLE TERHADAP DIAMETER GEL PADA PROSES GELASI EKSTERNAL KERNEL CERIA STABILIZED ZIRCONIA (CSZ) ]]>
<![CDATA[Kristanti Nurwidyaningrum]]>;
<![CDATA[Wahyudi Budi Sediawan]]>;
<![CDATA[Indra Perdana]]>
<![CDATA[ Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 3 (2019): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir ]]>
Publisher : <![CDATA[Badan Riset dan Inovasi Nasional ]]>
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DOI: 10.17146/urania.2019.25.3.5592
<![CDATA[In the production of coated particles that meet the requirements for high temperature gas reactor fuels, one of quality control requirements for the kernel is diameter control. The study was conducted by varying the diameter of the nozzle for predicting the size of gel diameter obtained from external gelation process by correlating variables of feed density, feed viscosity, feed solution tension and nozzle diameter quantitatively with dimensional analysis method in the form of dimensionless numbers. Fabrication of CSZ kernel was done by preparing the feed solution, which consists of a mixture of ZrO(NO3)2.2H2O and Ce(NO3)3.6H2O, urea, tetrahydrofurfuryl alcohol (THFA) and poly vinyl alcohol (PVA). External gelation is performed by dripping sol feed solution through a nozzle into gelation column containing ammonium hydroxide solution to form CSZ gel. Droplet formation occurs when the feed solution passes by the nozzle. The diameter of the gel formed can be calculated by correlating nozzle diameter and physical properties of the feed solution using dimensional analysis. Gel diameter of the experimental results was measured using an optical microscope. The diameter of the gel obtained from the dimensionless number equation shows results that are not too different from the diameter of the experimental gel with some deviations in the data. Data of diameter measurement of experimental gel and data of calculation by dimensionless equation show that diameter of the nozzle is directly proportional to diameter of the obtained gel.]]>
<![CDATA[NEUTRONIC AND THERMAL HYDRAULICS ANALYSIS OF CONTROL ROD EFFECT ON THE OPERATION SAFETY OF TRIGA 2000 REACTOR ]]>
<![CDATA[Surian Pinem]]>;
<![CDATA[Tukiran Surbakti]]>;
<![CDATA[Iman Kuntoro]]>
<![CDATA[ Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 3 (2019): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir ]]>
Publisher : <![CDATA[Badan Riset dan Inovasi Nasional ]]>
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DOI: 10.17146/urania.2019.25.3.5576
<![CDATA[Analysis of neutronic and thermal-hydraulics parameters of whole operation cycle is very important for the safety of reactor operation. During the reactor operation cycle, the position of the control rods will change due to reactivity changes. The purpose of this study is to determine the effect of control rods position on neutronic and thermal-hydraulics parameters in relation to the safety of reactor operation of the TRIGA 2000 reactor using silicide fuel of MTR plate type. Those parameters are power peaking factor, reactivity coefficients, and steady-state thermohydraulic parameters. Neutronic calculations are performed using a combination of WIMSD/5 and Batan-3DIFF codes and for thermal-hydraulics the calculations are done using WIMSD/5 and MTRDYN codes. The calculation results show that the reactivity coefficient values are negative for all control rod positions both at CZP and HFP conditions. The MTC value decreases when the control rod is inserted into the active core while the FTC value increases. The total ppf results and temperature in steady-state rise when the control rods are inserted of into the active core whereby the maximum value occurs at the position of the control rods of 20 cm from the bottom of the active core. The calculation results of ppf, reactivity coefficient, and thermal-hydraulics parameters lay below safety limits, indicating that the TRIGA 2000 reactor can safely use U3Si2-Al silicide fuel as a substitute fuel for cylindrical type fuel.]]>
<![CDATA[PEMODELAN DAN SIMULASI KINERJA PIN UJI BAHAN BAKAR PWR DENGAN UO2 DIPERKAYA ]]>
<![CDATA[Etty Mutiara]]>;
<![CDATA[Tri Yulianto]]>;
<![CDATA[Winter Dewayatna]]>
<![CDATA[ Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 3 (2019): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir ]]>
Publisher : <![CDATA[Badan Riset dan Inovasi Nasional ]]>
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DOI: 10.17146/urania.2019.25.3.5692
<![CDATA[Modeling and simulation of irradiation of PWR type test fuel of mini pin in RSG GAS reactor has been done using thermomechanics computer code of FEMAXI-6. The simulation was conducted by varying fuel enrichment under irradiation to predict fuel performance. The expected result from the simulation is the availability of simulation data on fuel behavior under simulated irradiation with different enrichment, neutron fluxes along the fuel, length of time and burn-up level at the beginning of contact between fuel pellets and cladding (Pellet-Cladding Mechanical Interaction,PCMI). The simulation data will provide valuable information for real irradiation experiment planning in RSG GAS reactor. The input for the simulation includes geometry and materials and operation condition such as neutron fluxes and linear heat rate. The calculations include heat generated by the fuel, heat transferred out of the fuel, axial and radial distribution of temperatures along the fuel, fission gas release and also pressure generated in fuel pin for whole length of the fuel pin. Temperature distribution calculation from thermal analysis module is applied to detailed mechanical analysis module to calculate gap width between the pellet and the cladding. The simulation shows a trend for reduction of contact time between fuel and cladding with increasing enrichment level at a same reactor power level because higher enrichment will cause higher linear heat rate. While PCMI does not occur on natural uranium fuel even for 100% burnup at full power level, fuel pin containing 5% enriched uranium causes the occurance PCMI at 900 hours of irradiation despite a reduce of power level by half with only 4% burnup.]]>
<![CDATA[PELAPISAN PERMUKAAN BAJA TAHAN KARAT AISI 304 DENGAN KHROM OKSIDA MENGGUNAKAN METODA SPUTTERING ]]>
<![CDATA[Sungkono]]>;
<![CDATA[Jan Setiawan]]>;
<![CDATA[Isfandi]]>;
<![CDATA[Ikhwanul Aziz]]>
<![CDATA[ Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 2 (2019): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir ]]>
Publisher : <![CDATA[Badan Riset dan Inovasi Nasional ]]>
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DOI: 10.17146/urania.2019.25.2.5433
<![CDATA[Stainless steel has been used as structure material of power reactors of LWR, AGR and LMFBR types. The problem of structural materials that arises is low corrosion resistance and swelling in high irradiation environments. One method to overcome this problem is surface coating of the stainless steel cladding with chromium oxide. The aim of this study is to obtain the characteristics of microstructure, microhardness, and compounds formed in the surface layer of AISI 304 stainless steel. DC-sputtering method was used for the coating of AISI 304 surface. The coating process used coater material of chromium target and argon as sputtering gas which was mixed with oxygen gas with concentrations varying from 0 - 50% volume. The process was carried out at 10 - 20 mA current for 1 - 3 hours. Characterization of the layer includes microstructure observation using optical microscope, hardness with microhardness Vickers tester, and compounds analysis in layers with X-ray diffractometer. The results shows that the base metal microstructure is composed of austenite and carbide deposits. The metal-layer interface is clearly visible. The thickness of the resulted compact and homogeneous layer tends to increase for O2 gas composition in the range of 0 – 30 %volume but decrease for the range of 30 - 40 %volume and rise at 40 - 50 %volume. The hardness of the layer increases until oxygen gas is at 30 %volume and then decreases at 50 %volume of O2 gas. At a fixed value of O2 composition at a current of 10 - 20 mA and a process time of 1 - 3 hours, it is observed that the hardness of the SS 304 surface layer increases with increasing current and sputtering time. At a composition of 30 %volume of O2, 10 mA current and 2 hours process, the resulted layer contains CrO2.]]>
<![CDATA[OKSIDASI SIKLIK PADA TEMPERATUR 1200 oC PADUAN TERNER Ni-Al-Ti YANG DIDOPING DENGAN WOLFRAM ]]>
<![CDATA[Adam Aprilianda]]>;
<![CDATA[Pradoto Ambardi]]>;
<![CDATA[Djoko Hadi Prajitno]]>
<![CDATA[ Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 2 (2019): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir ]]>
Publisher : <![CDATA[Badan Riset dan Inovasi Nasional ]]>
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DOI: 10.17146/urania.2019.25.2.5442
<![CDATA[This research is aimed to study the effect of Wolfram (W) on high temperature oxidation resistance of Ni-Al-Ti ternary alloy by cyclic oxidation method at 1200 °C. The amount of Wolfram added was 1.5% W. Number of samples used in this study is 2 samples, namely Ni-Al-Ti alloy and Ni-Al-Ti-1.5W alloy. Cyclic oxidation process was carried out with cycle variation of 4, 9, 16 and 25 cycles (a cycle refers 60 minutes of heating in the furnace and 30 minutes cooling outside the furnace). The tests include Rockwell-C hardness testing, metallographic testing, oxide thickness testing, surface morphology observation, Scanning Electron Microscopy (SEM) examination and X-Ray Diffraction (XRD) analysis. Wolfram content shows an influence in the hardness values with the highest hardness value obtained for the Ni-Al-Ti-1,5W sample with a hardness of 48.5 HRC for as cast sample and 50.5 HRC after treatment solution. The addition of wolfram appears to improve the resistance to high temperature, which can be seen from the cyclic weight loss curve where the Ni-Al-Ti-1,5W sample has lower weight loss when compared to the other sample.]]>
<![CDATA[OPTIMASI PARAMETER PEMISAHAN Zr DALAM PEB U3Si2/Al PRA IRADIASI MENGGUNAKAN METODE KROMATOGRAFI PENUKAR ANION ]]>
<![CDATA[Yanlinastuti Yanlinastuti]]>;
<![CDATA[Noviarty Noviarty]]>;
<![CDATA[Iis Haryati]]>;
<![CDATA[Syamsul Fatimah]]>;
<![CDATA[Boybul Boybul]]>;
<![CDATA[Aslina Br. Ginting]]>
<![CDATA[ Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 2 (2019): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir ]]>
Publisher : <![CDATA[Badan Riset dan Inovasi Nasional ]]>
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DOI: 10.17146/urania.2019.25.2.5508
<![CDATA[Determination of optimum parameters in the process of zirconium separation from U3Si2/Al fresh fuel solution by anion exchanger chromatography and analysis with UV-Vis spectrophotometer has been carried out. Zirconium is one of isotopes that can be used in the determination of fuel burn-up. The purpose of this study is to obtain optimal parameters of zirconium separation in standard materials as well as U3Si2/Al fresh fuel solution by anion exchanger chromatography. Optimization of Zr separation parameters was carried out using Dowex 1x-8 resin with a variation in weight of 0.5; 1.0; 1.5; 2.0 and 2.5 g, acidity of H2SO4 at 1; 2; 3; 4; 5 and 6 M, standard feed concentrations of Zr at 50; 100; 150 and 200 ppm and flow rate of 3M H2SO4 elution at 0.1; 0.3; 0.5; 0.7 and 0.9 mL/minute. To the Zr effluent as the result of separation was added Arsenazo III 0.1% as complexing agent, and subsequent analysis with UV-Vis spectrophotometry was done at a wavelength of 665.3 nm. The measurement results show that the optimal parameters of Zr separation are the use of 1.5 g resin with resulting recovery of 70.79%, acidity of 3M H2SO4 with recovery of 83.94%, feed concentration of 150 ppm with recovery of 87.64% at a flow rate of 0.5 mL/minute. When those optimal parameters were used in Zr separation from U3Si2/Al fresh fuel solution, the recovery obtained was 96.23%. These optimized parameters can also be used to separate Zr from U3Si2/Al irradiated fuel solution.]]>
<![CDATA[PEMISAHAN DAN ANALISIS CESIUM DALAM PEB U3Si2/Al TMU 2,96 gU/cm3 PASCA IRADIASI DENGAN METODE PENGENDAPAN CHLOROPLATINATE ]]>
<![CDATA[Arif Nugroho]]>;
<![CDATA[Boybul Boybul]]>;
<![CDATA[Sutri Indaryati]]>;
<![CDATA[Iis Haryati]]>;
<![CDATA[Rosika Kriswarini]]>;
<![CDATA[Aslina Br. Ginting]]>
<![CDATA[ Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 2 (2019): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir ]]>
Publisher : <![CDATA[Badan Riset dan Inovasi Nasional ]]>
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DOI: 10.17146/urania.2019.25.2.5466
<![CDATA[Fuel burnup is an important parameter for determining the quality and integrity of irradiated nuclear fuel. The most important parameters in the calculation of burnup is the separation process and 137Cs content analysis sampled from the irradiated plate fuel. This research has conducted separation and analysis of the 137Cs contained in irradiated U3Si2/Al plate by chloroplatinate precipitation method. This method requires that the sample has to be made free from elements that may interfere with the precipitation process. The separation is done by precipitation of 137Cs isotope in the form of Cs2PtCl6. The precipitation process uses CsNO3 as non-active carrier with varied weight of 0.0263; 0.0501; 0.0754; 0.1036 ; 0.2064; 0.3020, and 0.4017 g. The CsNO3 carrier is added in order to obtain more ammount of precipitate of Cs in the form of Cs2PtCl6 because CsNO3 has similar chemical properties with 137Cs in uranyl nitrate solution. The 137Cs isotope is coprecipitated in Cs2PtCl6, and γ-spectrometry is used in the determination of the content of 137Cs in Cs2PtCl6 precipitate. The separation results show that addition of 0,1036 g CsNO3 has recovered 0.000328 g/g-sample of 137Cs from 0.000465 g/g-sample in irradiated U3Si2/Al solution, or a recovery of 70.4753%. Recovery value by this method is still lower when compared to other 137Cs separation methods due to longer steps of separation process, which may cause many errors in the sample preparation process.]]>
