Badan Tenaga Nuklir Nasional: Jurnal BATAN
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ARDUINO AND IOT-BASED OBSERVATION METHOD FOR MONITORING TEMPERATURE, HUMIDITY, AND AIR PRESSURE OF ELECTRON BEAM ACCELERATOR’S ROOM
Full text linkThe 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
ANALISIS KESELAMATAN UNTUK MENCEGAH KECELAKAAN PADA PROSES EVAPORASI DI INSTALASI ELEMEN BAKAR EKSPERIMENTAL DENGAN METODE HAZOPS
Full text linkInstalasi 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
HAZOP-Based Radiological Risk Assessment of Pebble Bed Fuel Handling Systems
No full textThe High-Temperature Gas-Cooled Reactor (HTGR), a promising candidate for Generation IV nuclear reactors, boasts superior inherent passive safety features and a continuous fuel handling system. This system employs multi-pass cycles, utilizing pneumatic and gravitational mechanisms to feed, circulate, and unload the pebble bed fuel element. This paper presents a descriptive analysis assessing the safety risk of the fuel handling system design in HTR-10. The Hazard and Operability Study (HAZOP) methodology is employed to identify hazard parameters, deviation limitations, causes, impacts, and potential risks to the system’s main components. The establishment of probability scales, consequence criteria, risk level ratings, and control activities adheres to the ISO 31000 standard. Primary data were gathered through expert interviews, while secondary data were sourced from design layout documentation, literature reviews, and safety analysis reports. Six main components - the elevator, core, singulator, failed fuel separator, burnup measurement, and distributor - were selected as assessment nodes from the piping and instrumentation diagram. The assessment revealed that each node initially presented a moderate to extreme risk potential (risk level rating C to E). However, after applying the effectiveness index of the designed control, the residual risk for all nodes was reduced to an acceptable limit (risk rating A - very low). Therefore, the fuel handling system design already incorporates adequate control activities to mitigate potential safety risks due to system component failure. As safety risk assessment is dynamic, it should be reviewed periodically or whenever there are design changes at any project stage. This ensures the safety risk magnitude is consistently known and managed effectively
MONTE CARLO SIMULATION FOR THE EFFICIENCY OF THE RGU-1 STANDARD IN URANIUM MEASUREMENT IN SAMPLE DIFFERENT ENVIRONMENTAL MATRIX
Full text linkPreliminary Study of Plutonium Utilization in AP1000 Reactor Use SRAC 2006 and JENDL 3.3 has been conducted. Nuclear energy, especially for nuclear reactor, become important this day because the need of energy will increase along with the increasing of human population, the advanced technology and economic. The more nuclear reactor operated the more existence of plutonium stockpile. This study evaluated the standard of Westinghouse AP1000 reactor and ZrB2 as Integral Fuel Burnable Absorber (IFBA). Different fuel compositions of assembly type were analyzed in by using SRAC 2006 code system with JENDL 3.3 nuclear data library. This study aiming to compare the neutronics characteristics of an UO2 and an (U,Pu)O2 assembly designs. Some results of the study show that optimal criticality of the fuel assembly can be accomplished by using 5% enrichment of U-235 for UO2 fuel and 9% plutonium fraction for (U,Pu)O2 fuel assembly
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
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
DESIGN OF HELICAL TYPE STEAM GENERATOR FOR EXPERIMENTAL POWER REACTOR
Full text linkReaktor Daya Eksperimental (RDE) is a high-temperature gas-cooled reactor (HTGR) for electricity generation, heat generation, and hydrogen production by Batan. Empirical and numerical calculations are needed to strengthen the existing design. The numerical method by computational fluid dynamic (CFD) analyzes temperature distribution and pressure drop along the pipe. The Batan RDE steam generator design has a seven-layer helical pipe model, while this research uses a one-layer helix pipe. In empirical calculations, the heat transfer region has three sections; single-phase liquid, two-phase, and single-phase vapor heat transfer. In numerical calculations, apply the assumption of constant heat flux and constant working fluid properties. The results of empiric calculations data showed that the helical pipe height was 3.98 m, shorter than the Batan design, which is 4.97 m. This considerable difference due to empirical calculations did not cover the safety factor. The results of numerical calculations show that in the single-phase, empiric calculation data were acceptable since the different values of numerical calculations for empiric calculations data were below 10%. Meanwhile, the case of the two-phase numerical calculations is not satisfactory and needs further research to obtain optimal results
Pengaruh Cekaman Kekeringan Berulang Fase Vegetatif dan Terminal pada Padi Gogo Mutan Towuti
Full text linkPerubahan pola iklim dan curah hujan menyebabkan meningkatnya risiko kekeringan terutama di lahan kering. Cekaman kekeringan pada budidaya padi dapat terjadi secara tunggal maupun berulang atau sering disebut cekaman ganda. Penelitian ini bertujuan untuk menjelaskan respon pertumbuhan beberapa galur padi M3 dan varietas pembanding pada kondisi cekaman kekeringan pendek ganda yaitu kekeringan pada awal tanam saat vegetatif dan terminal saat pembungaan. Percobaan ini menggunakan 24 galur padi gogo M3, Varietas Towuti (cek Indukan), IR20 (cek peka), dan Salumpikit (cek toleran). Hasil penelitian menunjukkan dari 24 galur padi M3, galur Tw16, Tw18 dan Tw22 merupakan galur yang toleran berdasarkan nilai derajat kekeringan (DTD), Skor recovey dan Skor daun mengering fase terminal. Nilai derajat kekeringan (DTD) beberapa galur mutan yang toleran (>0,85), memiliki skor daya tumbuh kembali yaitu <3 dan skor daun mengering fase terminal kurang dari 4. Cekaman kekeringan pada awal tanam dan terminal secara signifikan menurunkan rata-rata tinggi tanaman dan jumlah anakan total. Galur Tw16, Tw18 dan Tw22 merupakan galur harapan yang akan diuji pada tahapan penanaman generasi M4
PERBANDINGAN DOSIS PERMUKAAN PADA PEMERIKSAAN THORAX ANAK MENGGUNAKAN METODE AUTOMATIC EXPOSURE CONTROL DAN METODE MANUAL
Full text linkPERBANDINGAN DOSIS RADIASI PADA PEMERIKSAAN THORAX ANAK MENGGUNAKAN METODE AUTOMATIC EXPOSURE CONTROL DAN METODE MANUAL. Automatic Exposure Control (AEC) pada pesawat sinar-X Digital Radiography (DR) secara otomatis dapat mengendalikan paparan radiasi, sehingga dapat menurunkan Dose Area Product (DAP) mencapai 61% tanpa mengurangi kualitas citra medis. Metode AEC dirancang untuk pasien dewasa, namun tidak menutup kemungkinan digunakan untuk pasien anak. Agar tingkat risiko kanker akibat radiasi pada anak dapat diminimalisasi, maka metode AEC ini menjadi penting untuk diaplikasikan. Dalam penelitian, dilakukan perbandingan metode AEC dan metode manual terhadap 60 pasien anak pemeriksaan thorax untuk memperoleh metode yang memberikan dosis permukaan lebih rendah. Pasien anak dikelompokkan dalam tiga kategori menurut usia, yaitu; 1-5 tahun, 6-10 tahun dan 11-15 tahun. Setiap kategori terdiri atas 10 pasien untuk metode AEC dan 10 pasien untuk metode manual. Pengukuran dosis permukaan menggunakan TLD LiF:Mg,Cu,P. Dari penelitian diperoleh dosis permukaan untuk Kategori-1 masing-masing 0,15±0,09 mSv untuk metode AEC dan 0,15±0,02 mSv untuk metode manual. Untuk Kategori-2 dan Kategori-3 masing-masing diperoleh 0,16±0,07 mSv (AEC), 0,21±0,06 mSv (manual) dan 0,15±0,04 mSv (AEC), 0,31±0,13 mSv (manual) secara berurutan. Metode AEC untuk pasien anak dapat meningkatkan keselamatan radiasi dan menekan kemungkinan risiko kanker