Jurnal Sains dan Teknologi Nuklir Indonesia
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INVESTIGATION OF AG AND PD FISSION PRODUCTS PENETRATION DEPTH IN ZRC LAYER OF HTGR TRISO FUEL PARTICLE USING SRIM/TRIM MONTE CARLO SIMULATION
Full text linkHigh-temperature gas-cooled Reactors (HTGRs) is one type of Generation IV reactor that uses TRISO (tri-structural isotropic) coated-fuel particles (CFP) for containment of radioactive fission products, which is produced from the fission reaction of UO2 fuel. ZrC has been proposed to be the main barrier for containing fission products either as a replacement of the SiC layer or as an additional layer of the TRISO fuel particle to overcome the corrosion issue of SiC because of interaction with the fission product of silver (Ag) and palladium (Pd). ZrC is an excellent material because it has good physical and nuclear properties, i.e., high corrosion-resistant, excellent thermal shock resistance and a small cross-section for neutron capture. ZrC is expected to provide a better barrier against Ag and Pd diffusion attacks than SiC. However, ZrC is very challenging to manufacture, so it depends on factors such as microstructure, chemical composition and interactions, morphology and impurities. Many attempts have been made to study the interaction phenomena of Ag and Pd with ZrC that cause corrosion. Here, the penetration depth of those two fission products was studied using SRIM (Stopping and Range of Ions in Matter) /TRIM (TRansport of Ions in Matter) for simulation with 0.1-10 MeV of kinetic energies. The results provide detailed information about the Ag/ZrC and Pd/ZrC Ion Ranges and Doses. In addition, Ag and Pd’s products of the depth and concentration within ZrC were observed as important first steps in understanding the corrosion phenomena of her ZrC layers in TRISO particles
COMPARATIVE ANALYSIS OF COOLANT MASS FLOW RATE FOR PELUIT-40 REACTOR IN ENERGY CONVERSION SYSTEM: A STUDY OF CONCEPTUAL DESIGN WITH AND WITHOUT A SPLITTER
Full text linkPeLUIt-40 is a nuclear reactor being designed in Indonesia for heat utilizing and generating electricity, with a thermal power of 40 MW. To improve energy efficiency, a system of electricity power and heat generation for hydrogen production called a cogeneration system was developed. The purpose of this study is to determine the best design for the cogeneration system. In this study, two conceptual designs of the cogeneration system were simulated, i.e., with and without a splitter system, respectively. The effect of coolant mass flow rate from (5, 6, 7, 8, 9, 10, 11, 12, 13, and 14 kg/s) to the energy utilization factor were analyzed. Calculations were performed using the ChemCAD 6.4.1 program and Python programming. The result shows that an increase of the coolant mass flow rate will increase the exit temperature of the coolant secondary side as a result of the heat transfer in the Intermediate Heat Exchanger (IHX). This temperature impacts an increase in the thermal power used for power generation and heat production. An increase in the mass flow rate in both designs also causes the value of the energy utilization factor (Energy Utilization Factor-EUF) and the value of the thermal efficiency to increase. Using the splitter has an EUF value of 34.51%, while the without splitter design is 33.92%. Likewise, the efficiency value of both with a splitter and without a splitter are 71.02% and 69.92%
ANALISIS PENGGUNAAN EMI FILTER 220 VAC/40A SEBAGAI PENYARING DERAU TEGANGAN PADA PERANGKAT DAC-SIK REAKTOR TRIGA 2000 BANDUNG
Full text linkPerangkat Data Acquisition Computer – Sistem Instrumentasi dan Kendali (DAC-SIK) Reaktor TRIGA 2000 memerlukan suplai tegangan murni tanpa adanya gangguan noise / derau. Berdasarkan pengamatan tegangan masuk dipre-Amplifier PA15 menggunakan Digital Oscilloscope Tektronik terhadap tegangan yang masuk perangkat DAC, ditemukan adanya lonjakan tegangan hingga 2000-2400 mV yang menyebabkan SCRAM, sedangkan standarnya dibatasi 20 mV. Lonjakan tegangan yang masuk perangkat DAC dalam orde milivolt (mV) diolah pada blok pengolah sinyal pre-Amplifier PA15 yang sangat sensitif terhadap kenaikan arus dan tegangan meskipun dalam orde mV. Agar reaktor dapat dioperasikan dengan aman dan selamat serta tidak ada gangguan derau ,maka derau tegangan tersebut harus dihilangkan dengan memasang perangkat EMI (Electromagnetic Interface) filter pasif 220VAC/40A yang mampu menangani lonjakan arus sebesar dua kali lebih besar daripada beban arus perangkat DAC-SIK reaktor (5KVA/20A). Dari hasil pengamatan dengan menggunakan Digital Oscilloscope Tektronik pada sistem setelah dipasang EMI filter diperoleh kesimpulan bahwa perangkat ini mampu menurunkan derau hingga 10 kali lipatnya dan reaktor dapat dioperasikan dengan aman dan selamat tanpa adanya gangguan derau tegangan
CALIBRATION TECHNIQUE OF TEMPERATURE MONITORING CHANNEL ISOTOPE PRODUCTION REACTOR
Full text linkThe measurement of reactor fuel temperature by using Instrumented Fuel Element (IFE) are necessary for monitoring the safety limit of the reactor fuel during operation. This device uses a temperature sensor type K thermocouple-based (Ni-Cr/Ni) and placed at the hottest position of the reactor core (hot channel). Placement in these positions potentially causing damage that can lead to errors reading of the measurement results. Because the reactor safety limits directly related to temperature, then the thermocouple as a sensor, it needs to be calibrated periodically so that the measurement results send the correct value of the measures. In general, every value that is obtained through measurement has some uncertainty, even though a careful execution of the experiment applied. Therefore, the main goal of this paper is to understand the characteristics of the measurement tools by doing a proper calibration method in order to get accurate results
TEMPERATURE MAPPING OF TRIGA 2000 REACTORS AT 500 kW POWER WITH 105 CONFIGURATIONS OF PRE-RESHUFFLING AND POST-RESUFFLING FUEL
Full text linkThe continuity of operation of the TRIGA 2000 reactor is thermohydraulically determined by the temperature of the fuel and the temperature of the primary cooling water in the reactor core. Currently, the operation of the TRIGA 2000 reactor at a power of 500 kW using a fuel 105 configuration in the core has caused boiling and the formation of bubbles in the reactor core, thereby reducing neutron moderation. The core of reactor is unable to achieve more power. One of the efforts that can be made to reduce the core temperature of the TRIGA 2000 reactor is by reshuffling the fuel inside the core, including using 105 fuels but shifting the position of the fuel to a different ring. In this research, thermohydraulic analysis has been carried out using the FLUENT program package for the configuration of 105 fuels in the pre-reshuffling and post-reshuffling core. Based on the results of the study, it is known that at 500 kW of power with a pre-reshuffling fuel configuration, there are positions for sub-cooled boiling in B3, B4, B5, B6, D4, D6, D8, D10, and D12. The hottest channel is at B5 with a maximum fuel cladding surface temperature of 126.41 °C, and a cooling water saturation temperature in the core of 112.4 °C. Meanwhile, for the post-reshuffling fuel configuration there is no position for sub-cold boiling in the core, where the maximum temperature is at B2 with the maximum fuel cladding surface temperature of 93.55 °C. Thus, it is concluded that the TRIGA 2000 reactor with a configurations of 105 post-reshuffling fuel can be operated at of 500 kW without boiling or at least not occurring sub-cold boiling
EFFECT OF GAMMA IRRADIATION ON PHYTOCHEMICAL CONTENT AND ANTICANCER ACTIVITIES OF ROSELLE (Hibiscus sabdariffa Linn)
Full text linkGamma irradiation is widely used in herbal medicine industries as an efficient preservative method in reducing microorganism contaminants. The aim of this study was to evaluate the effect of gamma irradiation at the doses of 5; 7.5; and 10 kGy on H. sabdariffa ethanolic extract (HS-EE). The Co-60 was used for irradiation the samples. The phytochemical content of HS-EE was carried out by total microorganism analysis using dilution method, TPC by Follin-Cicalteu method, TFC by aluminium chloride colorimetric method, antioxidant activity using DPPH method, TLC profiling on silica gel F254, in vitro anticancer activity using A-549, HUT-78, and MCF-7 cancer cell lines. The irradiation at 10 kGy caused the total bacteria decreased, while dose of 5 kGy could eliminate the total mold. Irradiation at 5 kGy caused TPC, TFC, and antioxidant activity decreased by 5-11%. TLC chromatograms analysis confirmed that one of the compounds contained in HS-EE was quercetin. The HS-EE has the strongest anticancer property against HUT-78 (IC50 10.51 µg/mL) followed by against MCF-7 (IC50 13.39 µg/mL), and A-549 (IC50 14.19 µg/mL). It can be concluded that irradiation at a dose of 10 kGy could remove total bacteria and molds, decreasing the phytochemical content and anticancer activities of HS-EE. It is recommended to increase the active ingredient level in the formulation
ANALYSIS OF EYE LENS EFFECTIVE DOSE OF WORKERS DURING CARDIAC CATHERIZATION EXAMINATION IN A CATHLAB ROOM
Full text linkIn the current era, many radiological imaging technologies are used, one of which is the C-Arm equipment technology, which is capable of imaging three-dimensional patient objects in real time using fluoroscopy techniques. This study aims to obtain and evaluate the effective radiation dose received around the eye organs of radiation workers during cardiac catheterization. The main tool uses the C-Arm modality, and the TLD detector chip. The object of observation is the area around the eye organs of radiation workers consisting of one doctor and one nurse. Catheterization was carried out on 10 patients with different examination times. Research results: in the area around the eyes without protective glasses; the effective dose received by doctors' eyes ranges from 0.0011 to 0.0054 mSv, while for nurses it ranges from 0.0010 mSv to 0.0025 mSv. It was found that the effective dose received around the eye organs was lower than the dose value set by Perka Bapeten No. 8 of 2011 which is 20 mSv and ICRP 203 which is 500 mSv per year
RADIOLOGICAL HAZARDS ESTIMATION BY NATURAL RADIOACTIVITY IN WATER SAMPLES ALONG BATANG HARI RIVER, JAMBI
Full text linkIllegal mining activity is still operated along the watershed of Batang Hari, which could potentially be contaminated by natural radionuclides, which are Uranium-238 (238U), Thorium-232 (232Th), Radium-226 (226Ra), Polonium-210 (210Po), Kalium (40K), and Lead-210 (210Pb). This study aimed to measure activity concentrations of 238U, 232Th, and 40K in river water, groundwater, and drinking water samples along Batang Hari River, then calculate radiological hazard parameters in the sample. The sample collects from 3 different locations from 3 sample types Muaro Jambi District, Jambi City, District Batanghari, Tebo District, and Bungo District. The samples were measured using gamma spectrometry High Purity Germanium (HPGe) for 17 hours. The results showed that the average value of the radiology hazard parameters sample consists of Raeq 0,307653, AEDE that is 1,771 x10-6, and each external and internal hazard index are 0,00083 and 0,00155, respectively. The radiological hazard parameters in water samples along Batang Hari River, Jambi, are below the limit recommended that Raeq is 370 Bq.L-1, AEDE is 1 mSv.y-1, and hazard index Hex and Hin are 1. This study showed that the water is safe and fulfills the radiological aspect of water quality requirements
ANALYSIS ON HEAT LOSS IN WATER HEATING TANK BASED ON TEMPERATURE SETTING VARIATION DURING NATURAL CIRCULATION FLOW USING FASSIP-02 TEST LOOP
Full text linkBased on the nuclear reactor accident in Fukushima due to an earthquake that caused a tsunami that turned off the electrical system for the cooling water pump. So that the reactor core melts due to the failure of the active cooling system, based on this incident, a passive cooling system that does not require external energy for emergency cooling is needed to prevent such an accident. Experimental research on the passive cooling system based on natural circulation flow to improve reactor thermal management performance during an accident has been done using the FASSIP-02 Test. One of the important components of the simulation of heat sources in nuclear power plants is the water heating tank (WHT). This study aimed to obtain the analysis results of heat absorption in water in WHT and the value of heat loss. The research method was carried out by calculating changes in the internal energy of water in WHT and heat loss for variations in water temperature settings from temperatures of 40 oC, 50 oC, and 60 oC in WHT at steady-state conditions for 5 hours experiment. The results showed that the entire surface of the tank resulted in heat losses of 10.85 kW, 9.2 kW, and 8.37 kW, which occurred at temperature settings of 40 oC, 50 oC, and 60 oC as a whole
RANCANG-BANGUN SISTEM PENCUPLIK UDARA MODEL PORTABLE-ADJUSTABLE
Full text linkDalam upaya melindungi pekerja, masyarakat, serta lingkungan, perlu dilakukan monitoring dan pengawasan secara berkala mencakup seluruh aspek keselamatan di lingkungan fasilitas nuklir yang mengacu kepada peraturan perundang-undangan. Monitoring perlu dilakukan untuk mengetahui nilai radioaktivitas komponen lingkungan yang berpotensi berdampak bagi kualitas lingkungan sehingga dijadikan dasar evaluasi pengelolaan lingkungan. Udara merupakan salah satu komponen lingkungan yang dipantau dengan pengukuran secara tidak langsung di laboratorium. Monitoring terhadap komponen udara memerlukan sistem sarana dan peralatan pendukung lainnya. Selain itu, sarana yang ada dinilai kurang praktis mengingat kondisi dan kendala di lapangan. Oleh karena itu, pada tulisan ini dijelaskan mengenai pemenuhan sarana yang diperlukan dengan cara merancang sistem pencuplik udara yang cukup ekonomis, desain model portable-adjustable sehingga selain mendapatkan sarana yang relatif murah, juga memberikan kemudahan untuk dapat meminimalisasi beberapa kendala yang dihadapi di lapangan. Perancangan dilakukan dengan cara mengidentifikasi kendala yang dihadapi di lapangan, menentukan bagian-bagian sistem yang diperlukan, lalu membangun sistem dengan memanfaatkan komponen yang telah tersedia dan mudah didapat di pasaran. Telah dirancang dan dibuat sistem alat pencuplik udara model portable-adjustable. Sistem alat telah dioperasikan dan digunakan untuk kegiatan monitoring komponen udara