ANALYSIS OF NON-PROLIFERATION AND NEUTRONIC ASPECTS ON MOLTEN SALT REACTOR (MSR) FUJI-U3 AND MOLTEN SALT FAST REACTOR TYPE (MSFR)
Molten Salt Reactor (MSR) and Molten Salt Fast Reactor (MSLR) is the fourth generation reactor design. Fuji-U3 is one of MSR developed by Japan. The fuel that is used in MSR is molten salt composed of 71.76 mol% LiF, 16 mol % BeF2, 12 mol% ThF4, and 0.24 mol% 233UF4. While for MSFR, 77.5 mol% LiF, 1...
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| Format: | Theses |
| Language: | Indonesia |
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| Online Access: | https://digilib.itb.ac.id/gdl/view/27467 |
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| Institution: | Institut Teknologi Bandung |
| Language: | Indonesia |
| Summary: | Molten Salt Reactor (MSR) and Molten Salt Fast Reactor (MSLR) is the fourth generation reactor design. Fuji-U3 is one of MSR developed by Japan. The fuel that is used in MSR is molten salt composed of 71.76 mol% LiF, 16 mol % BeF2, 12 mol% ThF4, and 0.24 mol% 233UF4. While for MSFR, 77.5 mol% LiF, 19.985 mol% Th-232F4, and 2.515 mol% U-233F4 is used. In this research, non-proliferation, neutronic, and hydraulic thermal analysis on MSR Fuji-U3 and MFSR is done with its respective fuel. The SRAC 2006 simulation tool with nuklida JENDL 4.0 is used for this research. Different simulation is run with different composition of fuel for MSR and MSFR until the condition for reactor reactivity and non-proliferation aspect are met. Moreover, the analysis based on convertion ratio, effective multiplication factor, Doppler effect and power distribution are also investigated. Paramtre surveys were curried out by variying the composition UF4, LiF and fuel temperature. Analysis aspect of nuclear non-proliferation based on the composition of the fuel, isotope composition of uranium and plutonium material. |
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