PENGUKURAN BERAT RADIONUKLIDA 137Cs DALAM LARUTAN PELAT ELEMEN BAKAR U3Si2/Al DENSITAS 4,8 gU/cm3 PASCA IRADIASI DENGAN METODE KOLOM KROMATOGRAFI

Burnup bahan bakar adalah salah satu parameter untuk mengetahui unjuk kerja bahan bakar U3Si2/Al setelah digunakan di reaktor. Salah satu isotop indikator burnup adalah 137Cs karena mempunyai waktu paruh panjang (T1/2) 30,17 tahun dengan fission yield 6,26%. Pemisahan 137Cs dilakukan untuk mengetahui jumlah 137Cs dalam larutan bahan bakar U3Si2/Al pasca iradiasi dengan metode kolom penukar kation menggunakan zeolit dari Lampung beserta besar recoverynya. Larutan bahan bakar U3Si2/Al pasca iradiasi dari masing-masing potongan Top (T), Middle (M) dan Bottom (B) dipipet sebanyak 50 µL secara duplo dan ditambahkan dengan 2 mL HNO3 0,1 M, kemudian diukur aktivitasnya menggunakan spektrometer gamma untuk mendapatkan jumlah awal radionuklida137Cs. Jumlah 137Cs dalam larutan dinyatakan dengan berat 137Cs per gram PEB (Pelat Elemen Bakar). Selanjutnya larutan tersebut dimasukkan ke dalam kolom kromatografi yang berisi zeolit Lampung 700 mg dan dibiarkan mengalir dalam keadaan vakum. Hasil pemisahan berupa 137Cs yang terikat dengan zeolit dalam bentuk fasa padat 137Cs-zeolit, sedangkan isotop lainnya berada dalam fasa cair (supernatan). Padatan 137Cs-zeolit dan supernatan diukur dengan spektrometer gamma untuk mengetahui berat 137Cs yang terikat dengan zeolit. Hasil pengukuran menunjukkah rerata berat awal 137Cs sebelum pemisahan sebesar 7,49 × 10-3 µg/gPEB dan 6,97 × 10-3 µg/gPEB untuk sampel T1 dan T2 dari potongan Top, 10,50 × 10-3 µg/gPEB untuk sampel M1 dari potongan Middle, serta 8,43 × 10-3 µg/gPEB dan 8,76 × 10-3 µg/gPEB untuk sampel B1 dan B2 dari potongan Bottom. Setelah pemisahan diperoleh berat rerata 137Cs sebesar masing-masing 7,43 × 10-3 µg/gPEB dan 6,82 × 10-3 µg/gPEB untuk sampel T1 dan T2, 10,10 × 10-3 µg/gPEB untuk sampel M1, serta 8,32 × 10-3 µg/gPEB dan 8,41 × 10-3 µg/gPEB untuk sampel B1 dan B2. Berdasarkan berat 137Cs sebelum dan sesudah pemisahan, didapatkan recovery rerata pemisahan dengan metode kolom kromatografi penukar kation menggunakan zeolit sebesar 97,748%. Hal ini menunjukkan bahwa zeolit Lampung sangat selektif untuk menyerap 137Cs di dalam larutan bahan bakar U3Si2/Al pasca iradiasi

Phytoremediation of Hexavalent Chromium Using Aquatic Plants in Nickel Mine Waste

The abundant wealth that Indonesia has is very profitable. Wealth is not only from natural resources, but wealth or biodiversity is also able to make Indonesia an independent country in managing its environment. One of the varieties that can be utilized is the existence of aquatic plants that can be used in the restoration of polluted environments. The ability of plants to recover from pollutants is called phytoremediation. Hexavalent chromium/ Cr(IV) is a hazardous waste originating from the washing of ore/open pit waste from rainwater washing. The quality standard allowed for Cr (IV), according to the Minister of Environment Regulation No. 9 of 2006, concerning the Quality Standard of Wastewater for Nickel Ore Mining Businesses and/or Activities is 0.1 mg/L. Besides being used to reduce pollutant loads, this aquatic plant can also provide aesthetic value because it has a very beautiful shape, type, color, and flowers. The purpose of this research is to find out which plants can be used to reduce hexavalent chromium levels. Variations of aquatic plants that can reduce levels of hexavalent chromium which are harmful to living things include water hyacinth/Eichornia crassipes; water hyacinth; Kayambang/ Salvinia Cucullata; Kiambang/ Apu Wood/ Pistia Stratiotes; Hydrilla verticillata; Water Bamboo/Equisetum hyemale; Water spinach / Ipomoea Aquatica; and Sagittaria lancifolia. This aquatic plant can reduce Cr (IV) up to 99.5%. The ability of these aquatic plants not only to reduce Cr (IV) but also to reduce TSS, BOD, and COD and to neutralize pH. The combination of several aquatic plants also provides a high effectiveness value

MODEL SIMULATION OF THE EFFECT OF ZINC PHOSPHATE INHIBITOR ON CORROSION RATE OF SECONDARY COOLING PIPE FOR PRESSURIZED WATER REACTOR USING PREDICTOR-CORRECTOR METHOD

Corrosion is one of the unavoidable problems in nuclear reactor cooling systems. Secondary Cooling Pipe Multi-Purpose Reactor G.A Siwabessy (MPR-GAS) based on low carbon steel is very easy to oxidize because it is an open circulation cooling system. Zinc-phosphate inhibitor (ZnPO4) is one of the inhibitors used to inhibit the corrosion reaction that occurs between the low carbon steel cooling pipe and the cooling water environment. The research has been carried out on numerical calculations to find a solution for the corrosion rate model of steel with and without an inhibitor by the Predictor-corrector method. The simulation results show that the effect of ZnPO4 inhibitor on the corrosion rate of steel is seen as a relationship between inhibitor concentration and stable time, if the inhibitor concentration increases, the stable time will also increase. The rate of corrosion that occurs (reducing the concentration of corroded product). Therefore, the recommended inhibitor concentration value is 0.9% for models in 0.1 M HCL medium. This concentration is the most appropriate concentration to slow down the corrosion rate. most minimal

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

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

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

Advancements in Accident Tolerance Fuel: A New Horizon in Nuclear Safety

Accident Tolerant Fuels (ATFs) represent a significant advancement in nuclear safety, offering the potential to mitigate the risks associated with nuclear reactor accidents. This paper provides a comprehensive overview of the development and current state of ATF technology, tracing its evolution and highlighting key technological milestones. Through an analysis of various case studies, we examine the practical application and performance of ATFs in real-world scenarios. Despite the promising capabilities of ATFs, their development and deployment are not without challenges. We delve into the technical, regulatory, and economic hurdles that must be overcome to realize the full potential of ATFs. Looking ahead, we explore the prospects of ATFs, discussing potential advancements and their implications for the nuclear industry. The findings of this paper underscore the transformative role of ATFs in enhancing nuclear reactor safety and charting a new horizon in nuclear technology

Characterization of Radioactive and Rare Earth Elements in Heavy Minerals from River Sediments in Marau Region, Ketapang, West Kalimantan

Alluvium deposits from the Kendawangan River located in Marau, Ketapang, West Kalimantan have been known for their radioactive and rare earth mineral potential. In this paper, heavy minerals taken from alluvium deposits will be characterized to determine the elemental distribution of uranium, thorium, and rare earth elements in each mineral and their mineralogical composition. The samples are taken by panning and prepared using the flotation method to obtain heavy mineral concentrates. Geochemical analysis was carried out using a Bruker M4 Tornado plus Micro-XRF and continued with mineralogical analysis using AMICS (Advanced Mineral Identification and Characterization System) software. It was found that the distribution of heavy minerals from the sand samples was dominated by manganoan ilmenite, ilmenite, rutile, zircon, magnetite, and monazite, as well as thorite, cassiterite, xenotime, allanite, and other minerals in small quantities. Uranium, thorium, and rare earth elements are found in monazite, thorite, xenotime, zircon, and allanite

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OPTIMASI PEMISAHAN SESIUM DI DALAM PELAT ELEMEN BAKAR TIPE U3Si2/Al PASCA IRADIASI MENGGUNAKAN METODE PENGENDAPAN KLOROPLATINAT

Beberapa metode pemisahan hasil fisi 137Cs dengan uranium (238U, 235U, 236U, dan 234U) dalam bahan bakar U3Si2/Al telah banyak dikembangkan. Sebagai langkah awal pengembangan metode pemisahan sesium (Cs) yang baru, maka dilakukan optimasi dan pemisahan menggunakan metode pengendapan kloroplatinat. Metode yang dikembangkan pada penelitian ini menawarkan potensi hasil endapan sesium dengan kemurnian yang lebih tinggi. Penelitian ini bertujuan untuk mendapatkan metode pemisahan isotop ¹³⁷Cs dari pelat PEB U₃Si₂/Al menggunakan reagen kloroplatinat. Langkah yang dilakukan adalah dengan melarutkan PEB  U₃Si₂/Al pra iradiasi dan menambah beberapa unsur seperti Sm, Sr, Cs, dan Nd untuk mewakili unsur kandungan PEB pra iradiasi, seperti kondisi aslinya. Proses pengendapan Cs di dalam larutan supernatan dilakukan dengan menambahkan larutan HCl dan NaOH untuk memisahkan unsur pengotor dengan unsur sesium. Proses pengendapan dilakukan dengan menambahkan H2PtCl6 untuk mengendapkan dan memisahkan unsur Cs dan unsur yang lainnya. Optimasi proses pengendapan dilakukan dengan memvariasikan temperatur dan waktu pengendapan. Kondisi optimum proses pengendapan diperoleh pada temperatur -3 οC dan waktu 10 menit hal ini ditunjukkan dengan perolehan hasil endapan Cs2PtCl6 sebesar 0,3361 g. Analisis menggunakan XRD dan SEM digunakan untuk melengkapi dan memperkuat hasil pemisahan sesium menggunakan metode pengendapan kloroplatinat, yang hasilnya semua unsur terdistribusi merata. Kemurnian endapan Cs2PtCl6 yang diperoleh sebesar 100% dengan pola difraktogram sama dengan referensi.