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Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Published by BRIN Publishing
ISSN : 08524777     EISSN : 25280473     DOI : https://doi.org/10.55981/urania
Core Subject :
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
Arjuna Subject : -
Articles 183 Documents
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KARAKTERISASI LAPISAN PENYERAP DAPAT BAKAR PADA PERMUKAAN PELET UO2 + DOPAN TiO2 Sungkono; Tri Mardji Atmono
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 3 (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.2016.22.3.3182

Abstract

Burnable absorber layer on the surface of UO2 + doped TiO2 pellets have successfully created using RF sputtering methods. The objective of this research is to obtain of microstructure characters of UO2 + doped TiO2 pellets, thickness, micro hardness, chemical composition and crystal structure of burnable absorber layer on the surface of UO2 pellets. The methods used are the microstructure and layer thickness using optical microscopy, layer hardness with micro Vickers hardness method, chemical composition by XRF spectrometry, and crystal structure by X-ray diffraction. The results showed that the larger of TiO2 content in the pellets then the greater of the grain size in the microstructure of the pellets and the thicker of the layer formed on the surface of UO2 pellets. The hardness of surface layer of UO2 + doped TiO2 sintered pellets are equal and does not depend on the dopant concentration of TiO2. The surface layer of UO2 + 0.3 % TiO2, UO2 + 0.5 % TiO2 and UO2 + 0.7 % TiO2 sintered pellets are containing zirconium respectively 1.97 mg, 2.47 mg and 4.81 mg. Burnable absorber layer on the surface of UO2 + doped TiO2 sintered pellets have ZrB2 phase with a hexagonal crystal structure.
PEMISAHAN DAN ANALISIS 137Cs DARI LARUTAN PELAT ELEMEN BAKAR U-7%Mo/Al Dian Anggraini; Noviarty Noviarty; Yanlinastuti Yanlinastuti; Aslina Br. Ginting; Rosika Kriswarini; Arif Nugroho; Boybul Boybul
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 3 (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.2016.22.3.3183

Abstract

The aim of this research is to get a valid method of separating cesium from U-7Mo/Al fuel plate solution through determination of parameter of method (accuracy, precision, and recovery). Precipitation method and cation exchange method that are used refer to standard ASTM 690-000 and research result of U3Si2/Al. Parameter method determination has been done by using 150 μL sample (U-7%Mo/Al fuel plate solution, 50 μL of standard solution in 2 mL of HCl 0,1 N. The sample solution was undergone precipitation process by using HClO4 concentrated and 225 mg of CsNO3 as carrier in temperature 0oC for an hour, while exchange cation process was done by using 400 mg of resin zeolite Lampung. The analysis of 137Cs in CsClO4 and 137Cs - zeolite was done by gamma spectrometer. Determination of recovery method was done by comparing count value of 137Cs before and after separation process. Recovery of precipitation method was obtained 95.56 % with accuracy and precision measurement of 0.375 % and 1.875 % respectively, while recovery of cation exchange method obtained 26.73 %. To sum up, the results show that precipitation method better than exchange cation method for separation 137Cs from U-7Mo/Al fuel plate solution.
INTERAKSI BAHAN BAKAR U3Si2-Al DENGAN KELONGSONG AlMg2 PADA ELEMEN BAKAR SILISIDA TMU 2,96 gU/cm3 PASCA IRADIASI Aslina Br. Ginting; Maman Kartaman Ajiriyanto; Supardjo Supardjo
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 21 No. 1 (2015): 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.2015.21.1.2255

Abstract

INTERACTION OF U3Si2-Al FUEL ELEMENT WITH AlMg2 CLADDING ON POST IRRADIATION WITH LOADING OF URANIUM 2.96 gU/cm3. Interaction of U3Si2-Al fuel element with AlMg2 cladding on post irradiation of 2.96 gU/cm3 loading of uranium (TMU) of U3Si2-Al fuel elements plate (PEB) has been analyzed. The purpose of this research is to study the changes of microstructure of nuclear fuel elements during iradiation in reactor core. Understanding on interaction of U3Si2-Al fuel meat with AlMg2 cladding onpre and post irradiation needed to study the influence of radiation on fuel elements plate. PEB U3Si2-Al with 2.96 gU/cm3 by size 10 × 10 mm were heated in DTA (Differential Thermal Analysis) furnace with temperature variation at 450, 550, 650, 900 and 1350oC to perform pre irradiation test.Post irradiation samples were cut by size 2 × 10 mm as many as three samples taken from bottom, middle, and top of PEB in hotcell. The metallography preparation for each pieces of pre and post irradiation samples of U3Si2-Al fuel elements platewith 2.96 gU/cm3 weredone through steps mounting, grinding, polishing, and etching.Scanning Electron Microscope (SEM-EDS) were used to observe the pre irradiation microstructure of fuel elements U3Si2-Al with AlMg2 cladding interaction, while the post irradiationmicrostructure were observed by optical microscope in hot cell. The result show the interaction of U3Si2 with Al matrix or AlMg2 cladding in pre irradiation PEB U3Si2-Aloccurred agglomeration formed new compouds of U(Al,Si)x and UAlx formation. Agglomeration formation on heated pre irradiation samples were bigger while heating temperature increased. The post irradiation sampels shoed the oxide layer were formed outside the AlMg2 cladding and the inner side of caldding that contact to the fuel meat formedlight-grey U(Al,Si)xlayer at 1-3 micron of thickness.
PEMISAHAN Zr – Hf SECARA SINAMBUNG MENGGUNAKAN MIXER SETTLER Dwi Biyantoro; Isyuniarto; Masrukan
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 3 (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.2016.22.3.3184

Abstract

Separation of Zr - Hf continuously using mixer settler 16 stage has been done. The feed solution is zircon nitrate concentration of Zr = 30786 ppm and Hf = 499 ppm. As the solvent used extractant 60 % TBP in 40 % kerosene. Nitric acid solution used srubbing 1 M. The feed entered into stage to 5 is contacted with solvents direction on the stage to 16 and the scrubbing solution enter the stage to 1. The purpose of this study is to separate Zr and Hf of the results from the process of zircon sand using solvent TBP using 16 stage mixer settlers. Analysis of the feed and the results of the separation process for zirconium (Zr) using X-ray fluorescence instrument which hafnium (Hf) using Neutron Activation Analysis (AAN). Parameter study done of acidity variation of nitric acid in the feed and time variation in various stirring speed. From the research the separation of Zr-Hf, the optimum conditions in acidity feed 4 N HNO3, equilibrium was received after 3 hours, and stirring speed of 3300 rpm obtained extract of zircon (Zr) concentration = 28577 ppm (efficiency of Zr = 92,76 %) with impurities of hafnium (Hf) = 95 ppm.
ANALISIS TEKSTUR ZIRCALOY-4 MENGGUNAKAN METODE WILLIAM–IMHOF–MATTHIES-VINEL (WIMV) Tri Hardi Priyanto; Mei Juan Li
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 21 No. 1 (2015): 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.2015.21.1.2256

Abstract

TEXTURE ANALYSIS OF ZIRCALOY-4 USING WILLIAM-IMHOF-MATTHIES-VINEL (WIMV) METHOD. Zircaloy-4 as a nuclear fuel cladding has been widely examined macroscopically and microscopically, but research using neutron diffraction technique, especially the characterization of crystallite orientation (texture) in Indonesia is still rare. The purpose of this study is to apply the methods of William-Imhof-Matties-Vinel (WIMV) on the characterization of zircaloy-4 material texture. WIMV is one of data analysis method for textures materials obtained by neutron or x-ray diffractions technique. The analysis is obtained that 002 pole figure has the largest texture index (F2) compared to the others pole figures, that are 100, 101, 102 and 110. Index texture (F2) of pole figure 002 for incomplete pole figures, F2 = 4.69 m.r.d with a reliability factor RP0 = 3.28%, and recalculated pole figures, F2 = 4.42 m.r.d with RP1 = 2.97%. For all pole figures, it is obtained that a reliability factor of the average RP0= 6.60%, RP1 = 5.02%, entropy = - 0.5871, and texture index (F2) = 2.34 m.r.d. Data analysis showed that the WIMV method can be used to determine the direction of the crystallite orientation of the pole figure where the most powerful texture leads to the <001> (c-axis direction) in a hexagonal structure.
USE OF MEMBRANE EMULSION SPAN 80 AND TOPO IN URANIUM EXTRACTION AND STRIPPING Kris Tri Basuki; Nurimaniwathy; Dian Puspita; Bambang E.H.B
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 3 (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.2016.22.3.3185

Abstract

Membrane emulsion span 80 and TOPO used in uranium extraction and stripping has been done. The extraction was carried outby emulsion membrane H3PO4 in TOPO-Kerosene. The feed or external aqueous phase was uranium in HNO3. The emulgator span-80 was used to obtain a stable emulsion membrane system. The influence factors were percentage of TOPO-Kerosene, time extraction, molarity of external aqueous phase and molarity of internal aqueous. After the emulsion membrane was formed, the extraction and stripping process was performed. The ratio volume feed: volume membrane phase equal to 1 : 1 and volume of 5 % TOPO-Kerosene: Volume 3 M H3PO4 equal 1 : 1 were used. The relatively good yield were obtained at concentration of TOPO in Kerosene and 3 M H3PO4 was 5 %, molarity of internal aqueous phase equal to 1 M, molarity of external aqueous phase 3 M H3PO4 and time extraction equal to 10 minutes with the speed of emulsification was 8000 rpm. At this condition the extraction efficiency of uranium obtained was 97.8 %, the stripping efficiency 52.56 %, and the total efficiency was 53.80 %.
KARAKTERISTIK PERMUKAAN SERAT SILIKON KARBIDA HASIL PEMINTALAN LISTRIK DARI POLYCARBOSILANE DALAM N,N-DIMETILFORMAMIDA (DMF)/ TOLUENA Deni Mustika; Riwandi Sihombing; Slamet Pribadi; Ratih Langenati; Agus Sujatno; Arbi Dimyati; Jan Setiawan; Eddy Indarto
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 21 No. 1 (2015): 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.2015.21.1.2257

Abstract

SiC SURFACE CHARACTERISTIC RESULT OF ELECTRIC SPINNING FROM POLICARBOSILANE IN THE DIMETILFORMAMIDA (DMF)/ TOLUENA. Non oxide ceramic silicon carbide (SiC) has unique properties such as mechanical strength, chemical and thermal stability that is used in many applications. Results of modelling studies on SiC show good stability on neutron irradiation and had low permeability againts fission product increased the interest in the use of SiC in nuclear applications. Composites form was used to increased mechanical properties. Composites that used fiber as filler show better mechanical properties than filler in form particle and whisker. In SiC composites, mechanical properties influenced by interphase properties and/or SiC surface characteristic. Electrospinning was a promising method to form fibers. This research aims to study the characteristics of silicon carbide fiber surface produced from polycarbosilane that solute by toluene and N,N-dimethylformamide (DMF). The addition of DMF and polycarbosilane in toluen affect the electrospinnability and characteristic the surface of fibers. The SiC fibers produced from polycarbosilane that solute by toluen and N,N-dimethylformamide (DMF) form continue fibers with ribbon liked. Black spot on the surface of pyrolysis fibers possible from free carbon or graphite contamination from furnace material. Value of surface area of pyrolysis fibers at 3.321 – 46.14 m2/g and porous in micro size, with distribution its radius in range at 1-3 nm, highgest distribution in size less than 2 nm. Pyrolysis and sintering in higher temperature expected to form fiber with less porous and its density able to approach the theoretical density.
PENGARUH REGENERASI KOLOM ALUMINA ASAM TERHADAP RECOVERY DAN KUALITAS 99mTc HASIL EKSTRAKSI PELARUT MEK DARI 99Mo HASIL AKTIVASI NEUTRON Adang Hardi Gunawan; Yono Sugiharto; Widyastuti
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 3 (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.2016.22.3.3186

Abstract

Purification of 99mTc from 99Mo activation using acidic alumina column chromatography system from MEK (Methyl Ethyl Keton) extraction has been carried out through cooperation between PTRR - BATAN, Chiyoda and JAEA Japan. This method has a limitation that acidic alumina column for purification of 99mTc can be used only once, for the next purification acidic alumina column should be replaced with new column, so it is less practical and also requires high cost. This study aims to obtain a 99mTc solution can be used for labelling of a radiopharmaceutical kit. In this study, the used of acidic alumina column for 99mTc purification was tried more than once by regeneration using 0.1N HNO3 solution after purification process is completed. Parameters observed in this study are the percent recovery, elution profile, pH, radiochemical purity and radionuclide purity. The results of observational studies conducted over 5 days has been obtained pH ~ 5, % recovery > 60%, radiochemical purity of > 95% and 99Mo leakage not detected. The treatment of acidic alumina column with 0,1 N HNO3 solution concluded that acidic alumina column does not need to be replaced every day.
REDUKSI AKTIVITAS URANIUM DALAM LIMBAH RADIOAKTIF CAIR MENGGUNAKAN PROSES ELEKTROKOAGULASI Prayitno; Vemi Ridantami; Imam Prayogo
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 3 (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.2016.22.3.3187

Abstract

Waste generated from the process of the industrial material development one of which waste containing uranium radioactive, can have negative impact on humans and the environment. In the present time, chemicals are still mostly use in radioactive waste treatment. To reduce pollutants with the use of chemicals is less efficient, because less environmentally friendly, take long time and costly. Therefore, a system of electrocoagulation process will be applied to decrease the activity of uranium from waste solution. The purpose of this study is to determine the efficiency of uranium activity decrease in waste water which is produced in the electrolysis process is conducted with voltage variations, the dwelling time, electrode spacing, and the waste inlet pH. The waste that will be treated has uranium contaminant levels of 500 mg/L. The experiment was conducted by a batch system with aluminum electrodes. Parameters affecting electrocoagulation process, such as voltage, time, distance electrode, and the pH have been studied and the best voltage optimization condition has been obtained of 12.50 V, a distance of 1 cm, pH 7, and in the processing time of 60 minutes efficiency of 97.20 % was obtained.
MODEL SIMULATION OF GEOMETRY AND STRESS-STRAIN VARIATION OF BATAN FUEL PIN PROTOTYPE DURING IRRADIATION TEST IN RSG-GAS REACTOR Suwardi Suwardi; Winter Dewayatna; Sungkono Sungkono; Ridwan Ridwan; M Rifai
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 21 No. 1 (2015): 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.2015.21.1.2259

Abstract

MODEL SIMULATION OF GEOMETRY AND STRESS-STRAIN VARIATION OF BATAN FUEL PIN PROTOTYPE DURING IRRADIATION TEST IN RSG-GAS REACTOR*). The first short fuel pin containing natural UO2 pellet in Zry4 cladding has been prepared at the CNFT (Center for Nuclear Fuel Technology) then a ramp test will be performed. The present work is part of designing first irradiation experiments in the PRTF (Power Ramp Test Facility) of RSG-GAS 30 MW reactor. The thermal mechanic of the pin during irradiation has simulated. The geometry variation of pellet and cladding is modeled by taking into account different phenomena such as thermal expansion, densification, swelling by fission product, thermal creep and radiation growth. The cladding variation is modeled by thermal expansion, thermal and irradiation creeps. The material properties are modeled by MATPRO and standard numerical parameter of TRANSURANUS code. Results of irradiation simulation with 9 kW/m LHR indicates that pellet-clad contacts onset from 0.090 mm initial gaps after 806 d, when pellet radius expansion attain 0.015 mm while inner cladding creep-down 0.075 mm. A newer computation data show that the maximum measured LHR of n-UO2 pin in the PRTF 12.4 kW/m. The next simulation will be done with a higher LHR, up to ~ 25 kW/m.

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