A5080479222- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Graphite, nuclear technology, radiation studies
- Nuclear and radioactivity studies
- Material Selection and Properties
- Nuclear Engineering Thermal-Hydraulics
- Nuclear Physics and Applications
- Corrosion Behavior and Inhibition
- Copper Interconnects and Reliability
- Heat Transfer and Boiling Studies
- Heat Transfer and Optimization
- Fusion materials and technologies
- Electrodeposition and Electroless Coatings
- Metal Forming Simulation Techniques
- Solar Thermal and Photovoltaic Systems
- High-Velocity Impact and Material Behavior
- Aluminum Alloys Composites Properties
- Electron and X-Ray Spectroscopy Techniques
- Geotechnical and construction materials studies
- Mechanical Failure Analysis and Simulation
- Bauxite Residue and Utilization
- Combustion and Detonation Processes
- Decision Support System Applications
- Engineering and Information Technology
- Engineering and Technology Innovations
National Nuclear Energy Agency of Indonesia
2015-2024
National Research and Innovation Agency
2024
Badan Pengkajian dan Penerapan Teknologi
2018-2023
University of Indonesia
2016-2018
The lesson learned from the severe accident of Fukushima Daiichi nuclear power plant shows that residual heat generated spent fuel should be cooled properly. In order to absorb when station blackout occurs, wickless-heat pipe is proposed used as an alternative passive cooling system in pool. objective this research simulation effect initial pressure and evaporator filling ratio factors influence thermal performance pipe. results will validated with experiment results. model was built...
The development of high density silicide fuels for research reactor RSG-GA Siwabessy has been carried out by increasing the fuel density. U3Si2/Al was increased from 2.96 gU/cm3 to 4.8 with potential effect on cladding integrity and its geometric stability, so a post-irradiation examination is required. Non-destructive test using digital X-ray radiography visual inspection are important in performance evaluation irradiated fuels. This uses plate 20% burnup as known CBJJ249. Visual surface...
Water in spent fuel storage pool that serves as a water cooling of decay heat and radiation shielding must be kept steady from evaporation. Knowledge the evaporation rate is needed so amount make up can well known for nuclear safety purposes. This study aims to calculate RSG-GAS pool. The Shah Carrier correlations were used based on operational data obtained pool, i.e, pond temperature, room relative humidity, airflow velocity SFSP building. calculation was performed two conditions: during...
To enhance the thermal safety in case of station blackout, a wickless-heat pipe is proposed as an alternative passive cooling system technology to remove decay heat generation nuclear spent fuel storage pool. The objectives this research are investigate transfer phenomena vertical straight using Graphene nanofluid working fluid and study effect on performance. investigation was conducted 6 meters height 0.1016 m inside diameter pipe. In research, with 1 % weight concentration used fluid....
Barreling methods are suitable for small pieces. Electroplating aluminum (Al) using copper (Cu) is less costly than a bar of Cu as part. barreling electroplating was conducted on an Al alloy. Various rotating speeds were applied during the plating process. onto alloy substrates performed in 0.5 M CuSO4 with 40 mA cm−2 current density 2 h. Scanning electron microscopy-energy dispersive spectroscopy, MATLAB software, X-ray diffraction, and potentiostat used to investigate properties layer. In...
Indonesia has two TRIGA research reactors operating in Bandung and Yogyakarta. reactor uses UZrH1.6 fuel with SS304 cladding. During operation, the cladding potentially performance decreasing, especially on mechanical integrity. The aim of this study was to determine effect cyclic oxidation tensile strength hardness value as reactor. specimen oxidized a furnace for 35 hours each cycle at temperatures 300, 400, 500 600°C, respectively. Tensile test results show remaining all temperature 446 -...
Zr-4 alloy in the nuclear industry is used as a cladding material for PWR. In order to prepare fabrication and prototype of PWR fuel, PRTBBNLR has carried out irradiation tests on at G.A. Siwabessy power ramp test facility. The form short pin. Irradiation 15 MW, average thermal neutron flux 1.15 x 1013 with highest distribution 4.65 lowest 3.14 1010, secondary coolant outlet temperature 42 °C, pressure range 16.5-17.5 MPa 350 hours. To determine mechanical performance material, it necessary...
Zircaloy-4 is a material used in the nuclear industry as cladding for PWR (pressurized water reactor) type reactor. The corrosion behavior of anodized layer on Zr-4 substrate 2000 ppm LiOH was analyzed. anodization process with various voltages has been carried out at 20 and 25 V. Electrolytes anodizing consisted (NH4)2SO4 NH4F. effects voltage microstructure, phase composition, elemental distribution, resistance coatings were investigated by scanning electron microscopy (SEM-EDS), X-ray...
Nickel (Ni) is an interesting candidate for corrosion protection of copper (Cu) due to its present passive area. Ni films with larger areas have better than those smaller ones. In the research, were produced over Cu. A barreling apparatus was employed support in sulphate solution. Various spinning speeds (0, 50, and 100 rpm) used on barrel while it being processed. Several investigations conducted, such as deposition rate, current efficiency, surface morphology, phase, film thickness,...
In order to anticipate station blackout, the use of safety system based on passive features is highly considered in advanced nuclear power plant designs, especially after Fukushima Dai-ichi accident. An example application natural circulation emergency cooling system. To study reliability such an application, a research project was carried out. This paper describes investigation results phenomena obtained using large rectangular experimental loop named FASSIP-01. The experiments were...
In order to cope with the absence of external electricity source condition, such as accident occurred in Fukushima Dai-ichi nuclear power plant, several designs reactor incorporate a natural circulation based emergency cooling system (ECS). To understand phenomena and assess reliability ECS, one experimental facility named FASSIP-02 is being constructed. The consists water heater tank (WHT), (WCT), which contains C-shaped heat exchanger (CHX) straight wickless pipe (SHP), piping system....
As the operating body that has authority to construct and operate a non-commercial nuclear reactor in Indonesia, BATAN decided develop RDE, an HTGR based with pebble bed fuels type. post-irradiation examination facility, IRM prepared developed PIE for fuel hot cell. Mechanisms supporting apparatus be considered during transfer processes from RDE sites This paper aims analyze technical design of compatibility existing system cell 101 such as wall-plug cask dimension, storage rack remote...
When station blackout occurs on high temperature gas-cooled reactor, the decay heat will be absorbed by a residual dissipation system (known as cooling tank) which connected to reactor cavity system. The U-shaped pipe passive is proposed new feature of technology absorb in tank, and keep water remains its operating level. This research objective know thermal resistance scale model based variation load coolant velocity. influence circulating thermostatic bath evaporator section air velocity...
In a typical small modular reactor, an emergency cooling tank acts as additional safety feature that is intended to cope with situation. Water inside the absorbs residual heat from reactor core when accident occurs through system designed for purpose. tank, exchanger used transfer water coolant under natural convection. For studying this system, experimental facility was designed, namely FASSIP-02. The objective of study investigate temperature distribution numerical code Fluent 6.3 and...
KARAKTERISASI MIKROSTRUKTUR, KEKERASAN, KOMPOSISI KIMIA DAN STRUKTUR KRISTAL LAPISAN PADA PERMUKAAN BAJA. Baja dan paduannya digunakan sebagai bahan struktur komponen reaktor nuklir peralatan dukung fasilitas hot cell. Selama pengoperasian atau cell, mengalami tegangan tarik, tekan, gesek dalam lingkungan radiasi tinggi sehingga dapat menurunkan umur komponen. Salah satu solusi yang adalah pelapisan permukaan baja dengan pelapis mempunyai kekerasan, ketahanan korosi aus tinggi. Penelitian...
Abstract Research and studies on pebble bed fuel to support the realization of RDNK based HTGR have been carried out by BATAN. Indicators reliability nuclear are able fulfill criteria for irradiation testing qualify in post tests. At present, Radiometallurgy Installation as a examination location has completed installation X-ray radiography equipment non-destructive testing. Performance analysis includes function tools completeness test facilities. Digital maximum voltage capability 320 kV....
PENGARUH ARAH PENGEROLAN DAN SHEAR CUTTING TERHADAP KARAKTER PADUAN AlMg2 SEBAGAI MATERIAL CLADDING BAHAN BAKAR REAKTOR RISET. Proses pengerolan paduan dilakukan secara bertahap hingga diperoleh ketebalan tertentu dengan syarat perilaku mekanik akhir sesuai spesifikasi cladding bahan bakar reaktor riset. Pada pengujian tarik elemen pasca iradiasi digunakan spesimen mini untuk meminimalkan limbah radioaktif. Tujuan penelitian adalah mendapatkan pengaruh arah dan shear cutting terhadap...
UJI PASCA IRADIASI PELAT ELEMEN BAKAR U3Si2/Al DENSITAS 4,8 gU/cm3 PADA BURNUP 60%: PENGAMATAN VISUAL, RADIOGRAFI SINAR-X DAN ANALISIS CITRA. Pengembangan bahan bakar densitas tinggi telah dilakukan melalui peningkatan nuklir dari 2,96 menjadi gU/cm3. Peningkatan uranium memiliki dampak terhadap integritas mekanik kelongsong dan stabilitas geometri, sehingga diperlukan pengujian pascairadiasi. Pengujian pascairadiasi yang meliputi pengamatan visual, uji radiografi sinar-X analisis citra pada...
Abstract Post irradiation examination is one of the requirements to obtain licensing nuclear fuel, and purpose this activity represent performance fuel itself. Currently, Indonesia developing 10 MWth high-temperature reactor type with its in form pebble bed. has a hot cell installation that function do post-irradiated examinations. This mainly used for plate rod fuel. paper wants show capability perform post-irradiation examinations based on documents current status. We also future...
ANALISIS KETIDAKPASTIAN PENGUKURAN KEKUATAN TARIK DAN ELONGASI SPESIMEN SS304 BERBENTUK RING. Ketidakpastian adalah tolok ukur dari kehandalan suatu pengukuran. Salah satu pendekatan analisa ketidakpastian yang banyak digunakan dengan menggunakan Guide to the expression of uncertainty in measurement (GUM). Langkah-langkah untuk menganalisa pengukuran telah dijelaskan secara rinci oleh GUM. Analisa dilakukan pada pengujian tarik mengetahui ketertelusuran data diperoleh. Pengujian menghasilkan...
ABSTRAK PEMANFAATAN GAMMA SPEKTROMETRI UNTUK PENGAMATAN DISTRIBUSI PEMBELAHAN DALAM ELEMEN BAKAR NUKLIR PASCA IRADIASI TELAH DILAKUKAN. Unjuk kerja pelat elemen bakar nuklir selama digunakan di reaktor dapat diketahui melalui pengujian pascairadiasi. Salah satu pasca iradiasi adalah mengamati distribusi hasil belah, yang untuk menentukan pembelahan dari bahan belah dalam bakar. Pengamatan ini umumnya dilakukan secara gamma scanning dengan paparan radiasi-g pada energi tertentu. Pada penetuan...
Untuk meningkatkan keselamatan termal ketika terjadi kecelakaan yang diakibatkan oleh kejadian station blackout, maka dipertimbangkan untuk menggunakan teknologi heat pipe sebagai sistem pendinginan pasif pembuangan panas sisa hasil peluruhan di kolam bahan bakar nuklir bekas. Tujuan penelitian ini adalah mempelajari unjuk kerja dari akan didisain pendingin Investigasi secara eksperimental dilakukan dengan mempertimbangkan pengaruh tekanan awal dalam dan beban kalor evaporator. Tekanan...
Pengembangan bahan bakar nuklir baik untuk reaktor riset dan daya telah menjadi fokus penelitian Pusat Riset Teknologi Daur Bahan Bakar Nuklir Limbah Radioaktif (PRTDBBNLR), mulai dari tahap fabrikasi, uji pra-iradiasi, iradiasi pasca-iradiasi. Sebagai satu-satunya fasilitas pasca-iradiasi di Asia Tenggara, Instalasi Radiometalurgi (IRM) dituntut siap melakukan evaluasi unjuk kerja nuklir, salah satunya adalah short pin PWR-fuel berisi UO2 yang saat ini sedang dalam proses iradiasi. Salah...