Design Study of Helium Cooled Fast Reactor with Natural Uranium Fuel Base
Gas Cooled Fast Reactor (GFR) is one of six selected of IV generation reactor. GFR has direct Brayton cycle, uses fast neutron and operates in the high temperature (850oC).This condition gives benefit to produce hydrogen. As we know that hydrogen is the one of promising energy because it cannot prod...
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| Format: | Final Project |
| Language: | Indonesia |
| Online Access: | https://digilib.itb.ac.id/gdl/view/13641 |
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| Institution: | Institut Teknologi Bandung |
| Language: | Indonesia |
| Summary: | Gas Cooled Fast Reactor (GFR) is one of six selected of IV generation reactor. GFR has direct Brayton cycle, uses fast neutron and operates in the high temperature (850oC).This condition gives benefit to produce hydrogen. As we know that hydrogen is the one of promising energy because it cannot produce CO2, CO, SO2 and global warming. GFR has high safety, proliferation resistant and economical. In this case, we will burn natural uranium (U-238) for 60 years and put them in 6 regions which have same volume. Hence, in the next 15 year, GFR produce plutonium and this plutonium will be moved from first region to the second region, the fuel from second region is moved to the third region etc. In this experiment, we use GFR with 2400 MWth, helium as coolant and Stainless Steel 316 (SS316) as cladding. In this research, we did some simulation with SRAC, a code developed by the Japan Atomic Energy Research Institute (JAERI), to know the neutron design, and then we will present the result using Microsoft Excel. |
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