GANENDRA Majalah IPTEK Nuklir
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STUDY OF POISSON NOISE REDUCTION ON GAMMA CAMERA IMAGE USING SPATIAL DOMAIN FILTER
A gamma camera image is produced by a gamma camera that detects the gamma radiation emitted by the radioactive substance or radiopharmaceutical injected into the body. The gamma camera image sometimes has noise that can interfere with the diagnosis. This image is commonly affected by a Poisson-type random noise. This research proposes using a spatial domain filter to study Poisson noise reduction in gamma camera images. The image sample used is the image of a mouse injected with Lu-177-DOTA Trastuzumab with 100 µCi activity detected using a dual-head gamma camera with NaI(Tl) detectors. The grayscale image is treated with Poisson noise, then improved using a spatial domain filter. The spatial domain filters used include Mean, Median, Wiener, and Spatial Lowpass Filters. The mean filter is the best one that can reduce Poisson noise among the four applied filters. The best filter size for noise reduction is 3 with MSE 5.07, PSNR 41.08 dB, and SSIM 0.99
MPS SIMULATION ON THE CORIUM MELT FLOW IN CASE OF REACTOR ACCIDENT
A simulation model has been made for molten corium in a nuclear reactor using the Moving Particle Semi-Implicit (MPS) method. By setting the value of dynamic viscosity and temperature of corium, simulations are carried out to display the pressure profile and flow velocity of the corium fluid that falls from the RPV to the plenum. In the first simulation to observe the pressure and velocity profile of the corium in the plenum, three conditions were made: the plenum was empty; the plenum was filled with corium fluid, and the plenum was filled with debris. The second simulation was carried out to determine the relationship between the time required for corium to reach the plenum for variations in corium viscosity and temperature values. The simulation results show that the increase in corium viscosity will be proportional to the length of time it takes to reach the plenum. In contrast to the effect of temperature where the increase in corium temperature will be the smaller the time required
CESIUM CHEMISORPTION ONTO STAINLESS STEEL UNDER SIMULATED LIGHT WATER REACTOR SEVERE ACCIDENT
During light water reactor severe accident, source terms may interact with structural materials, generating new compounds and affecting their volatility which make the existing codes could not accurately estimate the radioactive release. Cesium is one of the source terms that can interact with structural materials and contributes greatly to the late release phenomenon. Several studies have been conducted to predict the physicochemical interactions between cesium and structural materials. However, the types of chemisorbed cesium compounds onto structural materials are still under discussion. For this reason, this study was carried out using advanced techniques, involving TEM, SEM, EDS and FIB to estimate the chemisorbed cesium compounds onto stainless steel structural material under simulated light water severe accident. This study indicates that cesium is strongly adsorbed on the oxide layer of stainless steel in the form of cesium silica, cesium aluminum silica, and/or cesium ferro silica. CsFeSiO4 and CsAlSiO4 could dominate these compounds
THE EFFECT OF THE DC-SPUTTERING PROCESS ON CHANGES IN THE HARDNESS VALUE AND ELEMENTS COMPOSITION OF BIOCOMPATIBLE STAINLESS STEEL 316L MATERIAL
Titanium Dioxide (TiO2) thin films have intriguing optical, photocatalytic, and electrical properties and have been investigated for various applications, including solar cells, biomaterials, corrosion-resistant materials, and gas sensor. In this study, TiO2 thin films were deposited on the surface of 316L Stainless Steel to improve its mechanical properties as an implant material. The deposition method used was DC sputtering with variations in deposition times of 30, 60, 90, 120, and 150 minutes. Vickers hardness test and SEM-EDX characterization were carried out to determine the hardness value, elemental composition, and thickness of the TiO2 thin film formed. Based on these tests, it was discovered that the optimal hardness value of316L stainless Steel material was attained at a deposition period of 90 minutes with a hardness value of 170.10 VHN, and the average thickness of the layer formed was ± 119.02 μm
ARDUINO AND IOT-BASED OBSERVATION METHOD FOR MONITORING TEMPERATURE, HUMIDITY, AND AIR PRESSURE OF ELECTRON BEAM ACCELERATOR’S ROOM
The monitoring system for temperature, humidity and air pressure in the electron accelerator’s room has been designed. This research is based on operational environmental monitoring procedures in the accelerator room that must be carried out before the accelerator operates. We offer a simple and adaptable monitoring solution for the electron accelerator room. Parameter data can be monitored using a smart device. Operators do not need to go into the accelerator room to carry out environmental monitoring. The proposed system uses Arduino technology and the Internet of Things (IoT). Data acquisition programming was performed using Arduino IDE and ESP8266 NodeMCU as microcontrollers. The microcontroller then transmits temperature, humidity, and pressure data parameters to the cloud server, where they are then displayed on the smart device via the Blynk app. The results show that the system that has been designed is able to read and store parameter readings on the sensors used and the system has been able to make decisions in the form of notifications about whether the Electron Beam Machine is ready or not to be operated
AN IMPROVEMENT OF ARJUNA 1.0 CONVEYOR SYSTEM FOR 3D IRRADIATION
An improved design of the conveyor system of Arjuna 1.0 electron accelerator for 3D object irradiation has been done. The penetration of low energy electrons is less than 1 cm in the surface, causing a challenge for the irradiation process for sterilization of 3D objects. We design a conveyor that can be rotated 360o to irradiate objects evenly. The dimension of this conveyor is 1750 x 600 x 800 mm and the maximum diameter of the object is 7 cm. Based on the Frame Bending Stress analysis to calculate the strength of the conveyor frame, it is shown that the maximum displacement is only 0.029 mm, which is very small so it will cause no disturbance to power transfer from the motor to the conveyor. The normal stress (Smax) is 3.926 MPa and the bending stress for Smax (Mx) and Smax (My), are 2.391 MPa and 3.925 MPa respectively. We also calculate the stress analysis of the 3 mm-thickness of the motor mount and found that the Von-Misses Stress, first, and third Principal Stress are 4.425 MPa, 5.01 MPa, and 1.95 MPa respectively. These results confirm that the design and the material used for the conveyor are safe because the stress is very low than the material’s yield strength which is 207 MPa. The power needed for this conveyor is 0.01724 kW, with a maximum speed is 880 rpm. The new model of 3D conveyor has been constructed and can be implemented to ARJUNA 1.0 to irradiate objects on all its surface
PENENTUAN TINGKAT KLIERENS LIMBAH RADIOAKTIF HASIL SEMENTASI KONSENTRAT EVAPORASI DAN TINJAUAN KESELAMATAN PEMBUANGANNYA
Telah dilakukan penelitian untuk mengukur tingkat klierens 14 unit shell beton 950 L milik Instalasi Pengelolaan Limbah Radioaktif, Direktorat Pengelolaan Fasilitas Ketenaganukliran, Badan Riset dan Inovasi Nasional (IPLR-DPFK BRIN). Shell-shell beton tersebut merupakan paket hasil olahan konsentrat evaporasi limbah radioaktif cair yang dikondisioning dengan teknik sementasi. Jika telah memenuhi tingkat klierens, maka shell-shell beton tersebut dapat dibebaskan dari pengawasan Badan Pengawas Tenaga Nuklir (BAPETEN) melalui mekanisme klierens sehingga pada akhirnya dapat menambah ruang kosong di gedung penyimpanan sementara limbah radioaktif. Penelitian dilakukan dengan mengukur laju dosis radiasi, tingkat kontaminasi permukaan, dan konsentrasi aktivitas radionuklida pemancar α, β, dan ϒ untuk menentukan tingkat klierens. Dari penelitian yang telah dilakukan dapat diketahui bahwa laju dosis tertinggi 0,15 µSv/jam, tingkat kontaminasi permukaan tertinggi sebesar 0,0148 Bq/cm2 untuk radionuklida pemancar α dan 0,0935 Bq/cm2 untuk radionuklida pemancar β. Nilai tingkat klierens radioaktivitas unit shell beton 950 L yang diuji berkisar antara 0,47020 – 0,66730. Mengacu pada Peraturan Kepala BAPETEN Nomor 16/2012 tentang Tingkat Klierens, kandungan radionuklida dalam shell-shell beton 950 L yang diuji telah mencapai tingkat klierens. Pembuangan klierens terhadap 14 unit shell beton tersebut sangat mungkin untuk dilakukan karena shell-shell beton tersebut tidak mengandung bahan berbahaya dan beracun (B3). Perkiraan dosis radiasi yang akan diterima oleh kelompok kritis, tidak akan melebihi 10 µSv per tahun.
ANALISIS KESELAMATAN UNTUK MENCEGAH KECELAKAAN PADA PROSES EVAPORASI DI INSTALASI ELEMEN BAKAR EKSPERIMENTAL DENGAN METODE HAZOPS
Instalasi elemen bakar eksperimental (IEBE) DPFK – BRIN telah menerapkan standar keselamatan sebagai acuan keselamatannya yang dalam penerapannya menggunakan Hazard Identification Risk Assesment Determining Control (HIRADC). Metode HIRADC mempunyai beberapa kekurangan sehingga dalam penerapannya masih belum maksimal. Sebagai pelengkap dari metode HIRADC, maka dalam penelitian ini akan dilakukan analisis risiko menggunakan metode lain yaitu Hazard and Operability Study (HAZOPS). Pada proses evaporasi larutan uranil nitrat yang akan diidentifikasi potensi bahayanya adalah tangki evaporator E-601. Metode HAZOPS dilakukan berdasarkan diagram proses dan instrumentasi (P&ID) yang ada untuk menentukan potensi bahaya yang mungkin terjadi selama proses evaporasi dilakukan. Metode HAZOPS dilakukan dengan menentukan titik kajian (node) dan parameter, menganalisis penyimpangan atau potensi bahaya dari setiap node, melakukan analisis kemungkinan penyebab penyimpangan dan konsekuensinya, menentukan skala likelihood serta menentukan tingkat risiko dan membuat rekomendasi. Dari penilaian yang telah dilakukan, didapatkan 6 node dan kemudian menghasilkan 11 penyimpangan yang disebabkan oleh 13 kerusakan atau kegagalan peralatan. Penilaian risiko terhadap 13 kerusakan menghasilkan 1 potensi risiko bahaya rendah dan 12 potensi risiko bahaya sedang. Kategori risiko bahaya rendah dapat diatasi dengan penanganan rutin seperti melakukan pemeliharaan preventif dan kalibrasi alat secara berkala. Untuk kategori risiko bahaya sedang, selain memerlukan rekomendasi seperti bahaya rendah, juga diperlukan rekomendasi lain dalam mengatasi penyimpangan yang mungkin terjadi sesuai dengan jenis penyimpangannya. Dari hasil analisis keselamatan yang telah dilakukan, dapat disimpulkan juga bahwa HAZOPS dapat melengkapi HIRADC untuk memastikan keselamatan terjaga saat dilakukan proses
ESTIMASI DOSIS 99mTc-PERTEHNETAT DARI GENERATOR 99Mo / 99mTc NON-FISI PADA ANAK-ANAK USIA 1-15 TAHUN UNTUK PROSEDUR DIAGNOSTIK
99mTc-pertehnetat berguna untuk pengobatan yang disertai dengan adanya info pemberian dosis ke tubuh manusia. Penelitian ini bertujuan untuk mengetahui estimasi dosis radiofarmaka 99mTc Pertehnetat pada anak-anak usia 1-15 tahun. Metode penelitian ini dilakukan dengan berbasis uji biodistribusi mencit dengan interval waktu 0,5, 1, 3, 5, 24 jam pasca injeksi radiofarmaka. Dari data hasil uji biodistribusi diperoleh %ID/gram organ mencit, dikonversikan ke %ID/gram organ manusia. Setelah itu, hasil perhitungan diinput ke software OLINDA/EXM dengan mengamati perbedaan dosis efektif untuk anak-anak usia 1-15 tahun. Berdasarkan nilai %ID/gram organ manusia masing-masing aktivitas uptake pada interval waktu pasca injeksi dari organ tertinggi dihasilkan yaitu, otot, hati, paru-paru, dan lambung. Hasil perbandingan dosis efektif OLINDA/EXM menggunakan t hewan dan t manusia dapat diketahui hasil yang diperoleh menghasilkan nilai dosis efektif yang lebih kecil dibandingkan setelah dikonversi ke t manusia. Rata-rata dosis serap dari organ tertinggi pada OLINDA/EXM berada di tiroid, lambung, paru-paru dan. Hasil dosis efektif yang diperoleh untuk usia 1 tahun 1.11 x 10-2, 5 tahun 6.01 x 10-3 , 10 tahun 3.96 x 10-3 dan 15 tahun 2.50 x 10-3 . Oleh sebab itu, besar dosis efektif yang dihasilkan semakin besar terhadap umur pasien yang lebih muda
AN ANALYSIS OF CYLINDRICAL BORIS SOLVER FOR TYPICAL PARAMETERS OF TWO-DIMENSIONAL PENNING ION SOURCE SIMULATION
The cylindrical Boris solver is analyzed for typical two-dimensional Penning ion source simulation parameters. The analysis comprises the solver's accuracy and stability, especially for the latter simulation stages, typically after about 30 μs. The simulation is done for two cases; the first is a gyration simulation with a homogenous magnetic field, and the second uses the same setup as the Penning simulation. Several investigated quantities to determine the error are the radial position, axial position, and velocity magnitude (or kinetic energy). The error is calculated by comparing the result with the reference result from the exact solver with an incredibly small time step width, dt = 10-15 s. The result shows a discrepancy between cylindrical and cartesian Boris solvers. The velocity magnitude of the particle decays as time goes on for the cylindrical Boris solver, especially when the particle is close to the z-axis, an error not found on the cartesian solver. For typical Penning simulation parameters, the trajectory of individual particles is way off the reference trajectory. However, the mean position is relatively close to the reference compared to the dimension of the simulation domain. The kinetic energy is also relatively accurate, with a similar slow decay related to the deteriorating non-axial velocity components previously observed in the first case. Thus, for the simultaneous simulation of millions of particles, there should not be any significant observable difference in actual Penning simulation compared to Penning simulation with reference time step width