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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 JENIS PACKING PADA MENARA PACKED-BED ABSORBER DALAM PENYERAPAN GAS NOx Agoeng Kadarjono; Erilia Yusnitha; Agus Sartono Dwi Santosa; Pertiwi Diah Winastri
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 26 No. 1 (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.2020.26.1.5738

Abstract

THE EFFECT OF PACKING TYPE ON THE PACKED-BED ABSORBER IN ABSORPTION OF NOx. Design of NOx effluent gas processing needs to be done for broth preparation and gel casting activities in the UO2 kernel fabrication process series. The availability of this effluent processing tool will increase the economic value and process efficiency, reduce the amount of the chemicals needed, and minimize the hazards associated with toxicity and contamination. The design of the effluent processing tool chose the packed-bed absorber using NOx gas as a feed stream and water as an absorbent medium. The packed-bed absorber has been designed and calculated to determine the effect of various types of packing (pall, ralu, and nor-pac ring) for the absorbtion of the NOx gas. To determine the effect of the packing type, it is carried out by simulating fluid flow rate on diameter, effective surface area of packing, pressure drop, mass transfer coefficient, packing column height, and tower height by inserting into the appropriate equations using the EXCEL program. The inclusion of the effect of feed flow rate and type of packing in the calculation resulted in smaller diameter for the tower containing pall ring packing than the diameter of tower containing other fillings but gave higher pressure drop values, effective surface area of packing, total mass transfer coefficient, and tower height. Increase in NOx gas absorption causes an increase in the amount of packing space and tower height. Increase in operating pressure and temperature causes a decrease in packing and tower height, whereas increase in flooding factor, beside causing a decrease in packing and tower height, decreases the tower diameter. This type of pall ring packing is a design choice because it produces small/economic dimensions.
PENENTUAN RECOVERY NEODYMIUM DAN CERIUM PADA PROSES PEMISAHAN ISOTOP DARI SIMULASI PEB U3Si2/Al PRA IRADIASI Noviarty Noviarty; Erlina Noerpitasari; Rosika Kriswarini; Agus Jamaludin; Sutri Indaryati; Sayyidatun Nisa; Samsul Fatimah
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 26 No. 1 (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.2020.26.1.5791

Abstract

DETERMINATION OF NEODYMIUM AND CERIUM RECOVERY IN ISOTOPE SEPARATION PROCESS OF SIMULATED PRE-IRADIATED U3Si2/Al FUEL. Neodymium (Nd) is one of the fission product isotopes used as an indicator of nuclear fuel burn-up because Nd isotope is a stable fission product, has a sufficiently great yield, is not volatile and has low neutron-capture cross- section. Burn-up determination using Nd can support and verify the results of the burn-up determined by using Cs, U and Pu isotopes. Destructive burn-up determination (Destructive Test, DT) is based on the determination of specific isotopes that is performed physicochemically using mass spectrometer equipment. Based on ASTM E 321-69 method for Nd isotope analysis, Nd separation from Ce is required because 142Ce isotope interferes with 142Nd measurement due to their being isobars, and this phenomenon will affect the results of the burn-up calculations. In addition, Nd isotope in U3Si2/Al fuel is present along with other fission isotopes such as 235U, 239Pu, 148Nd, 137Cs, 152Eu, 90Sr, 143Ce, 103Ru, 95Zr, and 95Nb. Therefore, to obtain an accurate value to be used as burn-up indicator, the isotopes must be separated. Before the Nd and Ce separation, several separation phases of Cs isotopes (137Cs, 134Cs), U isotopes (234U, 235U, 236U, 238U), Pu isotopes (239Pu, 238Pu) and other isotopes (152Eu, 90Sr, 103Ru, 95Zr and 95Nb) were done. The determination of separation recovery aimed to determine the amount of Nd and Ce at each stage of the separation process of other isotopes prior to the separation stage of Nd and Ce. The determination of recovery was conducted by a simulation of fresh U3Si2/Al solution plus standard solutions of Cs, U, Nd and Ce. The recovery for Nd and Ce from Cs separation phase using zeolites were 69.91% and 64.42% respectively while the recovery of Nd and Ce at Pu and U separation phase were close to 100%. The recovery values of Nd and Ce were then used as a correction in the calculation of Nd and Ce separation from the fuel solution, and the corrected values can then be used as a reference in determining the burn-up of U3Si2/Al fuel using Nd as an indicator.
UJI TAK MERUSAK PELAT ELEMEN BAKAR U3SI2/Al DENSITAS URANIUM 4,8 gU/cm3 MENGGUNAKAN RADIOGRAFI SINAR-X DIGITAL Refa Artika; Rohmad Sigit; Helmi Fauzi Rahmatullah; Supardjo Supardjo; Aslina Br. Ginting
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 26 No. 1 (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.2020.26.1.5822

Abstract

NON DESTRUCTIVE TEST FOR U3Si2/Al FUEL PLATE WITH 4,8 gU/cm3 URANIUM DENSITY USING DIGITAL X-RAY RADIOGRAPHY. Non-destructive test for irradiated U3Si2/Al fuel plate with 4,8 gU/cm3 uranium density and 20, 40, and 60% burn-up has been done. The test includes visual inspection, radiographic image analysis, and dimension measurement using digital x-ray radiography. The non-destructive test aimed to determine the performance, integrity, and reliability of U3Si2/Al fuel plate with 4,8 gU/cm3 uranium density during irradiation at RSG-GAS. Reliability and safety of the fuel during irradiation are indicated by the absence of anomalies in the post-irradiation examination result. Three samples of irradiated U3Si2/Al fuel element (FE) with 20, 40, and 60 % burn-up were transferred from RSG-GAS to RMI hot cell 101 through transfer channel of Interim Storage Spent Fuel (ISSF). The U3Si2/Al fuel plate were then transferred to hot cell 103 for non-destructive test using digital x-ray radiography with seven shots for good resolution radiographic images. The radiographic images were evaluated to obtain data of defects and dimensions such as meat width, fuel plate width, meat-cladding distance, right-left meat- cladding boundary distance at the far side (SJ) and the near side (SD). The X-ray radiography analysis shows the presence of white spot in the middle of U3Si2/Al fuel cladding with 20% burn- up. Meanwhile, indication of surface defects and other defects were not found for the 40 and 60% burn-up samples. The dimensional measurement data show no dimensional changes, which indicates solid integrity after irradiation in the RSG-GAS. The measurement data analisis can further be used for mapping the sampling spots for the next test.
PROLIFERATION RESISTANCE ASSESSMENT OF INDONESIAN 10-MWT RDE EXPERIMENTAL POWER REACTOR USING INPRO METHODOLOGY Bening Farawan; Muhammad Sukron Fajrin Husein; Agus Sunarto; Arief Sasongko Adhi
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 26 No. 1 (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.2020.26.1.5620

Abstract

PROLIFERATION RESISTANCE ASSESSMENT OF INDONESIAN 10-MWT RDE EXPERIMENTAL POWER REACTOR USING INPRO METHODOLOGY. Assessment of proliferation resistance (PR) for 10-MWt RDE has been conducted to verify the RDE safeguards desain. Proliferation resistance (PR) is a parameter that can be used to measure the ability of a facility to implement safeguards (safeguardability). Safeguards is every technical measure used to ensure that every nuclear material in a facility is used as declared and only for welfare. Proliferation resistance of 10-MWt RDE has been assessed with INPRO methodology. The areas assessed were specific to intrinsic features of RDE, which consist of the attractiveness of nuclear material and technology and also detectability and chances of diversion of the nuclear material. This assessment concludes that the 10-MWt RDE has strong proliferation resistance, which indicates that the facility has small ability to diverse nuclear material and will less likely be used to proliferate nuclear weapon.
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

Abstract

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.
SIMULASI DIAMETER GEL BASAH PADA FABRIKASI KERNEL YTTRIA-STABILIZED ZIRCONIA MENGGUNAKAN ALAT GEL-CASTING Erilia Yusnitha; Sarjono; Sri Rinanti Susilowati; Winter Dewayatna; Wahyudi Budi Sediawan
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.2018.24.3.4984

Abstract

In kernel fabrication, microsphere of gelled kernels (yttria-stabilized zirconia) were made by droplet formation of the broth through the gel-casting equipment. Broth is feed of gel-casting equipment that were made of mixed of zirconium (IV) nitrate, yttrium (III) nitrate hexahydrate, urea, tetrahydrofurfuryl alcohol (THFA), and poly vinyl alcohol (PVA). The process parameter of the gel-casting equipment such as vibration frequency and broth flowrate need to be set up to control shape and diameter of the targeted microsphere of gelled kernels. The gel-casting equipment at PTBBN – BATAN is equipped with single nozzle with 1 mm diameter. The simulation work is important to be carried out to reduce the number of experiments in the laboratory hence it reduces the waste from trial and error in the experiment. Moreover, the objective of this simulation work is to predict the diameter of microsphere of gelled kernels. Therefore, the simulation of microsphere of gelled kernel diameter is necessary to be build and verified with the experiment data. According to hypothesis, the simulation of microsphere of gelled kernel diameter can be conducted by considering gel-casting equipment parameter such as the broth flowrate and vibration frequency. In addition, the broth characteristic as broth density affects the diameter of microsphere of gelled kernels diameter. The diameter of microsphere of gelled kernels produced from gel-casting equipment were determined with digital microscope. The result from simulation calculation shows that diameter of microsphere of gelled kernels produced from laboratory experiment can be approached by modified equation involving vibration frequency, broth flowrate, metal concentration in the broth and broth density. It appears that the deviation of simulation calculation is smaller than simple equation, where only vibration frequency and broth flowrate are included in the calculation.
PREDIKSI SIFAT MATERIAL PRESSURE TRANSMITING MEDIUM PADA QUASI-ISOSTATIC PRESSING MENGGUNAKAN FINITE ELEMENT ANALYSIS Dede Sutarya; Iqbal Ramadhian Pamungkas; Hendri Sukma; Agus Sartono; Dedi Haryadi
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.2018.24.3.5028

Abstract

Quasi-isostatic pressing technique is developed from isostatic pressing, which is made more simple and efficient. Quasi-isostatic pressing can provide the effect of volumetric triaxial compaction, so that it can produce compaction with uniform density. With these advantages, the quasi-isostatic pressing technique is used in pebble fuel fabrication process for high-temperature gas-cooled reactors (HTGR). The main problem in the quasi-isostatic pressing technique lies in need of hyperelastic material as a pressure transmitting medium (PTM) to transmit uniform static pressure in all directions in the compacting process. Therefore, the properties and characteristics of the PTM material needed for quasi-isostatic pressing with the boundary conditions of process must be determined. In this paper Finite Element Analysis (FEA) was used to predict the properties and characteristics (constants) of PTM materials for the quasi-isostatic pressing process using Mooney-Rivlin 2 and 3 parameters and single-acting press methods. From the results of FEA experiments, C10 values of 120 MPa, C01 of 49 MPa and C11 of 10 MPa were obtained. However, the quasi-isostatic pressing process for graphite powder compacting has not completed perfectly, so further research will be carried out with numerical improvement and the use of the Mooney-Rivlin 5 to 9 parameter model using double-acting press method.
ANALISIS POTENSI PROSES CREEP (PEMULURAN) TEHADAP BAHAN BAKAR UJI AKIBAT DISTRIBUSI STRAIN (KETEGANGAN) DENGAN MENGGUNAKAN PROGRAM FEMAXI Tri Yulianto; Etty Marti Wigayanti
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.2018.24.3.5031

Abstract

Analysis of creep process potential of test fuel due to strain distribution has been carried out using FEMAXI program. The purpose of this study is to predict the possibility of creep of test fuel due to circumocular distribution of axial and radial strain at certain operating temperatures and times and to provide information on quality standards during production and operation of pin tests in the reactor core. This analysis is important because cladding is a barrier to the pressure release of fission gas products produced when the fuel is irradiated. The phenomenon of the total creep process on pin cladding is assumed to be caused by the effect of burn-up on the release of fission gas products, which results in pressure induced by strain of cladding at relatively high temperatures. The creep rate will increase with increasing strain. The total mechanical analysis of the top and inner part of fuel pins at steady operating conditions shows that there is an increase in creep depending on the LHR (linear heat rate) and operating pattern on the reactor core. For transient operating conditions, it shows an increase in stable creep. In ramp operating conditions or sudden LHR change operations, it indicates an increase in creep processes due to difference in strain pressures between steady operation patterns, transients and ramps during the process of creep on pellets and cladding. This is due to fission gas products, but the final results of the total pin condition calculation indicate that the pin products are still considered as safe in terms of both thermal and mechanical processes with various patterns of LHR changes.
EVALUATION OF RADIATION DOSE RATE OF RSG-GAS REACTOR Amir Hamzah; Hery Adrial; Subiharto
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.2018.24.3.4909

Abstract

The RSG-GAS reactor has been operated for 30 years. Since the nuclear reactor has been operated for a long time, aging process on its components may occur. One important parameter for maintaining the safety level of the RSG-GAS reactor is to maintain radiation exposure as low as possible, especially in the working area. The evaluation results should be able to demonstrate that the radiation exposure of the RSG-GAS is still safe for workers, communities and the surrounding environments. The purpose of this study is to evaluate radiation exposure in the working area to ensure that the operation of RSG-GAS is still safe for the next 10 years. The scope of this work is confirming the calculation results with the measured radiation dose in the RSG-GAS reactor working area. Measurement of radiation exposure is done by using the installed equipments at some points in the RSG-GAS working area and a portable radiation exposure measurement equipment. The calculations include performance of a modeling and analysis of dose rate distribution based on the composition and geometry data of RSG-GAS by using MCNP. The analysis results show that the maximum dose rate at Level 0 m working area of RSG-GAS reactor is 3.0 mSv/h with a deviation of 6%, which is relatively close to the measurement value. The evaluation results show that the dose rate in RSG-GAS working area is below the limit value established by the Nuclear Energy Regulatory Agency of Indonesia (BAPETEN) of 10 mSv/h (for the average effective dose of 20 mSv/year). Therefore, it is concluded that the dose rate in RSG-GAS working area is safe for personnel.
PENGARUH PH PADA PENURUNAN KADAR THORIUM DALAM LIMBAH MENGGUNAKAN PROSES ELEKTROKOAGULASI DENGAN ELEKTRODA ALUMUNIUM DAN TEMBAGA Prayitno; Vemi Ridantami; Indah Muji Mulyani Mulyani
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.2018.24.3.4396

Abstract

Reduction of thorium level by electrocoagulation process has been done. Electrocoagulation process is a method used in waste management, which is based on the use of electrodes with potential difference to produce coagulant. One of the process parameters in electrocoagulation is pH. This study aims to determine the effect of pH on the electrocoagulation process in order to lower the thorium level. The method used was batch electrocoagulation process in electrocoagulator tub of 22.5 × 14.5 × 20 cm dimension. The electrodes used were aluminum and copper of 20 × 20 cm2 size with active surface area of 250 cm2. Electrodes were installed in parallel with 1 cm distance between the electrodes. The electrocoagulation process was carried out with a working voltage of 2 V for 60 minutes. Sampling was done every 5-minute interval to prepare samples for subsequent thorium level analysis and pH measurement. The results show changes in pH value during the electrocoagulation process. Such changes result in the concentration change, which was indicated by coagulant separation efficiency. The separation efficiency of aluminum electrode was 98.06%, which was indicated by an increase in thorium level from the initial value of 439.274 ppm to 8.503 ppm within 5 minutes at a pH of 7.38. The copper electrode shows 96.35% efficiency in reducing thorium level from the initial value of 439.274 ppm to 16.015 ppm within 5 minutes at a pH of 7.29. Both electrodes used in the electrocoagulation processes show high separation efficiency and significant increase in pH values within 5 minutes, suggesting that the formation rate of coagulants is rapid during 5 minutes.

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