A5088834049- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Fusion materials and technologies
- Hydrogen embrittlement and corrosion behaviors in metals
- Luminescence Properties of Advanced Materials
- Gas Sensing Nanomaterials and Sensors
- Nuclear and radioactivity studies
- Corrosion Behavior and Inhibition
- Metallurgy and Material Forming
- Glass properties and applications
- Graphite, nuclear technology, radiation studies
- Pigment Synthesis and Properties
- High-Velocity Impact and Material Behavior
- Radioactive element chemistry and processing
- Nuclear Physics and Applications
- Thermodynamic and Structural Properties of Metals and Alloys
National Nuclear Energy Agency of Indonesia
2020-2024
National Research and Innovation Agency
2023-2024
Badan Pengkajian dan Penerapan Teknologi
2022
STUDY OF FISSION GAS BUBBLES AND INTERACTION LAYER ON IRRADIATED U3Si2-Al DENSITY 4.8 gU/cm3. Uranium-silicide compound fuel dispersed in aluminium matrix (U3Si2-Al) have been used a large number of research reactors around the world because its excellent behavior under irradiation. This also provides high uranium density with typical loading up to gU/cm3 compensate for reduced fissile amount LEU. To improve current (2.96 gU/cm3) Indonesian GA Siwabessy Multipurpose Research Reactor,...
Dysprosium doped CaSO4 thermoluminescent crystal was successfully synthesized by the sol-gel method assisted chitosan and citric acid as chelating agent. This study conducted preliminary work to compare obtained CaSO4−based from commonly used co-precipitation method. The powders this were then analyzed using XRD, major phase of base material found in anhydrite form, with average crystallite size between 90-97 nm. powder a high concentration suitable pH solution wet chemical process....
A characterization and analysis with SEM EDS have been carried out on Zr-4 material after sputtering titanium target, applications for nuclear power reactor cladding, Pressurized Water Reactor (PWR) Heavy (PHWR) types. Samples which has a length width of about 1 cm thickness 10 mm, the surface is sputtered Ti target voltage variation 4 kV 5 time also varied 2, 3 hours. It was found that longer process material, thicker layer. The minimum must be kV. in does not change much to coating sample...
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...
Abstract Austenitic stainless steel 316 has very high mechanical properties and corrosion resistance. This type of is widely used both in the nuclear non-nuclear industries. In industry, SS316 as a cladding material for uranium fuel due to its good properties, also low neutron absorption cross-section. Center Nuclear Fuel Technology (PTBBN BATAN), it container waste that be stored on Temporary Storage Installation Spent (KHIPSB3 BATAN). can contain high-activity solid from testing activity...
The fuel element plates in a research reactor can be exposed to an acidic, neutral, or alkaline environment based on its surroundings. This study aimed investigate the effect of Nb addition corrosion properties U-6Zr alloys various environments. U-6Zr-xNb (U-6Zr-2Nb, U-6Zr-5Nb, and U-6Zr-8Nb) with different compositions 2, 5, 8 wt%, respectively, were prepared cut into smaller pieces. pieces then mounted chemical resin equipped copper wire cables metallography by grinding using sandpaper...
Stainless steel is an important component in the industrialized world with rising growth consumption. It has strong, durable, and economically valuable materials. One of stainless-steel applications for nuclear power plant facilities. In Indonesian industry, stainless not only used purpose reactor but also radiometallurgical facility. The should be improved its lifetime to minimize failure. methods that can surface hardening through nitrocarburizing. Where this method would form compound...
OXIDE LAYER CHARACTERIZATION OF AlMg2 CLADDING IRRADIATED U3Si2/Al FUEL WITH 4,8 gU/cm3 DENSITY. To investigate the performance of cladding in dispersion fuel, oxide layer characterization irradiated fuel with 4.8 density was conducted. The on surface is one changes that occur after plate has been RSG-GAS reactor to a burn-up ∼40%. and observation conducted using SEM (Scanning Electron Microscope) Energy-dispersive X-ray spectroscopy (EDS). Samples size 3x3 mm were taken from middle (middle...