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SERVICE DESCRIPTION | Supervising final project students with specialization in chemistry/ physics/ physics engineering/ chemical engineering/ metallurgy/ materials/ nuclear engineering/ instrumentation. Scope of mentoring activities with research topics: 1. R&D of Nuclear…
- Puspiptek - Serpong
Supervising final project students with specialization in chemistry/ physics/ physics engineering/ chemical engineering/ metallurgy/ materials/ nuclear engineering/ instrumentation. Scope of mentoring activities with research topics:
1. R&D of Nuclear grade Uranium Conversion and Refining Technology from various U . concentrates
2. Research and Development on Nuclear Grade Uranium and Thorium Conversion and Purification Technology from the U-Th concentrate produced by kelris Nuclear Raw Materials Processing Technology table scale.
3. R & D Recovery uranium from process effluent by solvent extraction, electrochemical and ion exchange methods.
4. R & D refining graphite by hydrometallurgical and pyrometallurgical methods from natural graphite
5. R&D of nuclear fuel analysis methods in various matrices
6. R&D of PWR Pin Fabrication Technology with Enriched Sintered Pellet
7. High Burn Up Nuclear Fuel Technology R&D
8. R&D of HTGR Nuclear Fuel Fabrication Technology
9. Research and Development on Reactor Fuel Fabrication Technology Research based on UMo
10. R&D of UZr-based Research Reactor Fuel Fabrication Technology
11. Nuclear Fuel Performance Modeling
12. Performance Analysis of USi .-based Fuel Element Plates
13. PWR . Pin Test Fuel Performance Analysis
14. Separation of Cs-137 Radionuclide Sources from Post-Irradiated Nuclear Fuels for Radiation Monitoring Portals at Airports and Industries
15. Separation of Sr-90 Radionuclide Sources for Nuclear Battery Candidates
16. Surface Modification of Al, Zr and SS Based Structural Materials to Improve Hardness, Corrosion Resistance and Wear Resistance of Materials
17. Development of Post-irradiation Test Facility Structural Materials: metal alloys, polymers, composites
18. Development of Test Support Systems for Nuclear Fuels and Post-Irradiated Structural Materials: Test Equipment, Manipulators, Incell Cranes, and others
19. Strength Analysis of Post-Irradiation Test Facility Structure
20. Synthesis of Oxide Layer on Zircaloy-4 Alloy to Improve High Temperature Oxidation Resistance of PWR Type Fuel Cladding by Anodizing Method.
Application Requirements:
1. R&D of Nuclear grade Uranium Conversion and Refining Technology from various U . concentrates
2. Research and Development on Nuclear Grade Uranium and Thorium Conversion and Purification Technology from the U-Th concentrate produced by kelris Nuclear Raw Materials Processing Technology table scale.
3. R & D Recovery uranium from process effluent by solvent extraction, electrochemical and ion exchange methods.
4. R & D refining graphite by hydrometallurgical and pyrometallurgical methods from natural graphite
5. R&D of nuclear fuel analysis methods in various matrices
6. R&D of PWR Pin Fabrication Technology with Enriched Sintered Pellet
7. High Burn Up Nuclear Fuel Technology R&D
8. R&D of HTGR Nuclear Fuel Fabrication Technology
9. Research and Development on Reactor Fuel Fabrication Technology Research based on UMo
10. R&D of UZr-based Research Reactor Fuel Fabrication Technology
11. Nuclear Fuel Performance Modeling
12. Performance Analysis of USi .-based Fuel Element Plates
13. PWR . Pin Test Fuel Performance Analysis
14. Separation of Cs-137 Radionuclide Sources from Post-Irradiated Nuclear Fuels for Radiation Monitoring Portals at Airports and Industries
15. Separation of Sr-90 Radionuclide Sources for Nuclear Battery Candidates
16. Surface Modification of Al, Zr and SS Based Structural Materials to Improve Hardness, Corrosion Resistance and Wear Resistance of Materials
17. Development of Post-irradiation Test Facility Structural Materials: metal alloys, polymers, composites
18. Development of Test Support Systems for Nuclear Fuels and Post-Irradiated Structural Materials: Test Equipment, Manipulators, Incell Cranes, and others
19. Strength Analysis of Post-Irradiation Test Facility Structure
20. Synthesis of Oxide Layer on Zircaloy-4 Alloy to Improve High Temperature Oxidation Resistance of PWR Type Fuel Cladding by Anodizing Method.
Application Requirements:
- Identity Card
- File Data Transkrip
- Agreement
- Proposal
- Letter of Introduction
- CV
- Photo
