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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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PENGARUH TEMPERATUR DAN WAKTU HOMOGENISASI TERHADAP KARAKTERISTIK PELAT PADUAN AG3NE Hadijaya; Siti Aidah; Masrukan
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 2 (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.2018.24.2.4391

Abstract

Investigation on the effects of homogenization temperature and time on AG3NE alloy plate has been done. AG3NE alloy is used as cladding material of research reactor fuel. Ingot of AlMgFeSi melt was sampled for several tests and examination such as chemical composition, hardness, microstructure, phase, density and corrosion. Composition analysis shows that the alloy is composed of Al= 96.110%, Fe= 0.188%, Mg= 2.333% and Si= 0.355%.The hardness value for AG3NE is 153.33 HV for samples treated with rapid cooling and 72.70 HV for samples treated with slow cooling. Microstructure examination with optical microscope shows that AG3NE alloy without homogenization consists of flat grains with a fraction of dendrite of 0.02 mm mean diameter, while samples homogenized at 500°C at varied temperatures of 1, 2, 3, and 4 hours consist of grains with 0.01 mm, 0.02 mm, 0.03 mm and 0.04 mm respectively. Phase analysis with X-Ray Diffractometer indicates the existence of Al (ά) and FeSiAl5 phases at 2θ of 38.24° - hkl (119) and 44.446° - hkl (209) with 100% and 76.6% intensity respectively. The measured density of AG3NE, however, is similar to that of AlMgSi as material for comparison, the values of which are 2.6893 ± 0.0013 g/cm3 for AG3NE and 2.6910 ± 0.0283 g/cm3 for AlMgSi. Corrosion rate analysis shows that the corrosion rate for AG3NE is lower than that for AlMgSi. Based on the characterization for chemical composition, microhardness, microstructure, density and corrosion rate, it is concluded that AG3NE alloy can be used as a candidate for cladding material for research reactor fuel.
KARAKTERISTIK MEKANIK KELONGSONG BAHAN BAKAR NUKLIR TEMPERATUR TINGGI DALAM ATMOSFER GAS NITROGEN Rohmad Sigit; Sri Ismarwanti; Guswardani; Yatno Dwi Agus Susanto; Jan Setiawan
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 2 (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.2018.24.2.4422

Abstract

At Loss of Cooling Accident (LOCA) scenario, Zr-2 and Zr-4 as nuclear fuel cladding potentially exposed to air which experimentally leads to mechanical properties degradation faster than in steam environment. This study aims to determine the impact of nitrogen on the mechanical strength of cladding by minimizing other environmental influences. The Zr-2 and Zr-4 cladding was annealed under vacuum at a temperature of 500°C for one hour. It was followed by nitriding with the pressure of 1500 mbar for two hours. It was followed by natural cooling to room temperature. The results of tensile strength and microhardness testing showed that tensile strength, ductility and microhardness values increase of 12.1%, 19.2% and 28.2% for Zr-2 and 5.1%, 25% and 22.6% for Zr-4, respectively. Nitride layer was formed on the cladding surface due to interaction with nitrogen and there is no mechanical properties degradation due to nitriding process. It was caused by nitriding processes that were not followed or accompanied by oxidation processes.
CORE DESIGN OF TRIGA2000 BANDUNG USING U3Si2/Al FUEL ELEMENT MTR TYPE Surian Pinem; Tukiran Surbakti; Tagor Malem Sembiring
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 2 (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.2018.24.2.4302

Abstract

The TRIGA2000 Bandung reactor currently uses cylinders fuel type, but the fuel production has been discontinued. In order to operate continuously, it is planned that the TRIGA2000 reactor should change the fuel from cylinder type to U3Si2/Al MTR type since Indonesia has been able to produce such fuel element. In this research calculation of TRIGA2000 coreusing U3Si2/Al fuel MTR type of three different fuel densities has been done. This activity begins with performing neutron macroscopic cross section generation for all core materials as a function of temperature, burn up and xenon. The cross-section generation was performed with the WIMSD5 code. The calculation of the core parameters were done with the Batan-FUEL code. Based on the calculation of neutronic parameters, there are three core configurations, i.e.core with 16 fuel elements and 4 control elements (Core 16/4), core with 14 fuel elements and 4 control elements (Core 14/4) and core with 12 fuel elements and 4 control elements (Core 12/4). The three cores meet the safety constraint but only the Core 16/4 that uses U3Si2/Al fuel with a density of 2.96 gU/cm3. The maximum thermal neutron flux in the core center is 5.874×1013 n/cm2s with core cycle length is 245 days at 2 MW. The results show that the TRIGA2000 core can be converted from cylinder type fuel to silicide MTR type.
ANALISIS KOROSI PIPA PENDINGIN SEKUNDER RSG-GAS DENGAN TEKNIK ELECTROCHEMICAL IMPEDANCE SPECTROSCOPY (EIS) Maman Kartaman Ajiriyanto; Rosika Kriswarini; Yanlinastuti Yanlinastuti; Diyah Erlina Lestari
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 2 (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.2018.24.2.4421

Abstract

Multi-purpose reactor G.A. Siwabessy has a secondary cooling system facility to extract heat generated from uranium fission reactions in the reactor. The cooling pipe material is a type of carbon steel. Secondary cooling media is water supplied from Puspiptek. To extend the lifetime of the pipe, chemical compound ZnPO4 was put on the water-cooling media as a corrosion inhibitor. The corrosion analysis of secondary pipe was performed by corrosion testing using EIS and tafel method. The electrochemically corrosion test was performed with three electrode cells in water media, 0.05 M HCl solution and 3% NaCl solution. The aim is to obtain the optimum inhibitor concentration added in the secondary coolant and to determine the inhibition mechanical as well as the inhibitor efficiency. EIS testing was performed in the frequency range 100 kHz to 0.02 Hz in HCl 0,05M. Test results show changes in electrical parameters such as Rct, Cdl and Rs. The inhibitor concentration increases then Rct value increase. At inhibitor concentration of 90 ppm obtained the highest Rct value is 81,29 ohm. Efficiency of the inhibitor addition produces maximum value is 66,75% at concentration of 90 ppm. The corrosion rate in samples on medium of 3% NaCl without inhibitor, moss inhibitor and corrosion inhibitor were 3.975, 3.576 and 3.215 mpy respectively. The addition of a mixture of corrosion inhibitors and moss inhibitors can decrease the corrosion rate up to 1.586 mpy quantitatively. The addition of inhibitors using ordinary water may inhibit interface reactions on the surface of the sample as indicated by the higher the inhibitor concentration the higher the Rct value. In NaCl 3% medium also shows the same phenomenon relatively that the corrosion mechanism can be inhibited by increasing of Rct value as well as in this condition, Rs value is constant relatively. The dominant fact that the addition of a corrosion inhibitor could decrease the corrosion rate. The moss inhibitors have a primary function not to decrease the corrosion rate.
OPTIMASI PH ALUMINA DAN 99Mo DALAM PEMBUATAN GENERATOR 99Mo/99mTc BERBASIS MoO3 ALAM Sulaiman; Yono Sugiharto; Chairuman; Gatot Setiawan; Adang Hardi Gunawan
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 2 (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.2018.24.2.4159

Abstract

Alumina material has long been used for 99Mo radioisotope adsorbent in the 99Mo/99mTc generator. The 99Mo/99mTc generator produces 99mTc radioisotope which is used for the diagnostic purposein nuclear medicine. To date, alumina is used to adsorp 99Mo obtained from fission reaction of 235U. The restriction of the use of fission 235U leads to the find of an alternative 99Mo. The alternative of 99Mo production is obtained from natural MoO3 which is irradiated by thermal neutron in the nuclear reactor. The 99Mo radioisotope produced from this reaction has no carrier-free properties. This is due to the abundanceof natural MoO3 is 24.13%.In the99Mo/99mTc generator based on natural MoO3 by using alumina column, it is necessary to know the alumina type for optimum 99Mo adsorption, as well as pH of 99Mo. In this study, there were used three variations of alumina-based generator column namely acid, neutral, and basic alumina. The 99Mo solution used in this study was also performed three pH: pH 4, pH 7, and pH 8 of the 99Mo solution. The generator eluted and observed daily for 3 days and continued after the next two days for 2 days. The optimum adsorption of 99Mo from natural MoO3 by alumina material was given in the use of acidic alumina with the pH 4 of the99Mo solution. Among the three pH variation of the 99Mo solution, the 99Mo solution of pH 4 gives the highest of 99mTc yield. The column with the smallest 99Mo breakthrough is given by acidic alumina column using the 99Mo solution of pH 4. Thus, acidic alumina column can be used as an adsorbent to adsorp natural 99Mo.
PEMISAHAN CESIUM DALAM PEB U3Si2/Al PASCA IRADIASI DENGAN METODE KOLOM PENUKAR KATION MENGGUNAKAN RESIN DOWEX Arif Nugroho; Dian Anggraini; Boybul Boybul; Sutri Indaryati; Rosika Kriswarini; Aslina Br. Ginting
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 2 (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.2018.24.2.4306

Abstract

The burn up calculations of nuclear fuel by destruction method can be determined from the analysis of 137Cs isotope, as fission product. For this reason, the separation of 137Cs isotopes from uranium in irradiated fuel element plates of U3Si2/Al (PEB) needs to be done. The separation of 137Cs was done by using cation exchange column method with Dowex resin with weight variation of 1; 2; 3; 4; 5 and 6 g. This study aims to determine the content of 137Cs in irradiated fuel element plates of U3Si2/Al (PEB) using the cation exchange column method with Dowex resin to be compared with the result of 137Cs separation by cation exchange column method using Lampung zeolite and CsClO4 precipitation method. The irradiated fuel element plates of U3Si2/Al (PEB) PEB U3Si2/Al with a density of 2.96 gU/cm3 from the middle part of RI-SIE2 code and side plate 20 IDA 0045 was taken with weight 0.1103 g and dissolved with HCl 6N and HNO3 6N to obtain uranil nitrate solution. The U3Si2/Al post irradiated solution was 150 μL was added with 2 mL aquadest and added with Cs carrier 20 μL and 1 mL HCl 12 M. The solution mixture was used as feed into the anion exchange column (first column) containing the R-Cl resin –with the wight variation about 1; 2; 3; 4; 5 and 6 g. The effluent from the anion exchange column was introduced into the cation exchange column (second column) which contained R-NH4+ resin with weight variation of 1; 2; 3; 4; 5 and 6 g. The bounded 137Cs isotope in R-NH4+ resin in the column was being eluted using 1 M HCl of 15 mL and being vaporized until the volume reach ± 2 mL. The quantity of the 137Cs isotope in the effluent was measured by using a gamma spectrometer with a counting time of 500 s. The 137Cs isotope content in irradiated fuel element plates of U3Si2/Al with the density 2.96 gU/cm3is 0.000445 g/gPEB and the parameter of separation 137Cs with cation exchange column method using Dowex resin weighing 2 g with recovery is 98.67%. The result of separation of 137Cs by cation exchange column method is not much different from the result of separation 137Cs by cation exchange method and CsClO4 precipitation method. The 137Cs obtained can then be used for burn up calculations.
PENGARUH ROL DINGIN DAN ANIL TERHADAP KARAKTERISTIK STRUKTUR MIKRO DAN KEKERASAN MIKRO PADUAN Zr-0,5%Nb-Si Heri Hardiyanti; Arief Sasongko Adhi; Jan Setiawan
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 26 No. 2 (2020): 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.2020.26.2.6069

Abstract

EFFECTS OF COLD-ROLLING AND ANNEALING ON THE MICROSTRUCTURE AND MICROHARDNESS CHARACTERISTICS OF Zr-0.5%Nb-Si. The performance improvement of zirconium alloys can be done by adding a certain percentage of common alloying elements such as Nb and Si. The addition of Nb provides resistance to irradiation and stabilizes the β phase (which normally forms at high temperatures) at room temperature. The addition of Si increases the strength of the alloys. The synthesis of a Zr-0.5% Nb-Si alloy have been carried out using an electric arc furnace. The microstructure and the microhardness of this alloy were observed after cold-rolling and annealing. It can be seen from the annealed alloy without cold-rolling that the grain size is larger with reduced microhardnes. The alloy treated with cold-rolling shows changes in the microstructure while the deformation density increases, which results in an increase in microhardness. Heat treatment to the cold-rolled alloy changes the microstructure of the alloy where recrystallization occurs, and the deformation density decreases, which results in the decreasing of microhardness. The lowest grain size and microhardness for the alloy that was cold-rolled at ε = 0.8 and annealed are 0.302 mm and 187 HVN, respectively.
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): 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.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 theliquid 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.
UJI TAK MERUSAK SHORT PIN PWR – FUEL DUMMY PASCA IRADIASI Rohmad Sigit; Refa Artika; Maman Kartaman Ajiriyanto; Tri Yulianto
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 26 No. 2 (2020): 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.2020.26.2.6058

Abstract

NON-DESTRUCTIVE TEST OF IRRADIATED SHORT PIN OF PWR TYPE – FUEL DUMMY. Post- irradiation examination (PIE) for nuclear fuel is used as an indicator of fuel performance reliability during the irradiation process. The Center for Nuclear Fuel Technology (PTBBN) conducts research and development of nuclear fuel for Pressurized Water Reactor (PWR). Short pin of PWR fuel dummy with zircaloy-4 cladding has been irradiated at the Multipurpose Reactor – G.A. Siwabessy (RSG-GAS) and has been sent to the Radiometallurgy Installation (IRM) – PTBBN. Non-destructive tests conducted at the IRM includes visual observation and X-ray radiographic test. Visual observations using a digital camera were done in hot cell 102, while X-ray radiographic test was carried out in hot cell 103 IRM. X-ray radiographic test using the voltage and current parameters at a range of 120-125 kV and 1000-1100 uA. The test material was placed at a height of 60 cm from the detector to obtain a 100% magnification. Visual observation shows the formation of several spots indicating oxidation on the short pin PWR fuel dummy surface. Radiographic images from X- ray radiographic testing do not show any anomalies, which is indicated by relatively homogeneous gray value in the axial and radial directions. Generally, based on the non-destructive test results, performance of the short pin PWR - fuel dummy is relatively satisfactory with no significant defects. To confirm the existence of oxides formation on the surface of the short pin PWR fuel dummy, Eddy Current test is needed, followed by microstructure observations.
STRATEGY TO SUPPORT HTGR FUEL FOR THE 10 MW INDONESIA’S EXPERIMENTAL POWER REACTOR (RDE) Taswanda Taryo; Ridwan; Geni Rina Sunaryo; Meniek Rachmawati
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 1 (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.2018.24.1.3729

Abstract

The Indonesia’s 10 MW experimental power reactor (RDE) is developed based on high temperature gas-cooled reactor (HTGR) and the program of the RDE was firstly introduced to the Agency for National Development Planning (BAPPENAS) at the beginning of 2014. The RDE program is expected to have positive impacts on community prosperity, self-reliance and sovereignty of Indonesia. The availability of RDE will be able to accelerate advanced nuclear power technology development and hence elevate Indonesia to be the nuclear champion in the ASEAN region. The RDE is expected to be operable in 2022/2023. In terms of fuel supply for the reactor, the first batch of RDE fuel will be inclusive in the RDE engineering, procurement and construction (RDE-EPC) contract for the assurance of the RDE reactor operation from 2023 to 2027. Consideration of RDE fuel plant construction is important as RDE can be the basis for the development of reactors of similar type with small-medium power (25 MWe–200/300 MWe), which are preferable for eastern part of Indonesia. To study the feasibility of the construction of RDE fuel plant, current state of the art of the R&D on HTGR fuel in some advanced countries such as European countries, the United States, South Africa and Japan will be discussed and overviewed to draw a conclusion about the prospective countries for supporting the fuel for long-term RDE operation. The strategy and roadmap for the preparation of the RDE fuel plant construction with the involvement of national stakeholders have been developed. The best possible vendor country to support HTGR fuel for long-term operation is finally accomplished. In the end, this paper can be assigned as a reference for the planning and construction of HTGR RDE fuel fabrication plant in Indonesia.

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