NEUTRONIC AND NUCLIDE COMPOSITION ANALYSIS on MOLTEN SALT REACTOR BASED ON FUJI-U3 TYPE
Reactor Generation IV is development from previous generation. Reactor FUJI U3 have high safety design and melting fuel will not happen because the fuel is already in liquid. In this research will be done neutronic analysis by program SRAC 2006. Graphite moderator is different from moderator on PWR...
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| Format: | Final Project |
| Language: | Indonesia |
| Online Access: | https://digilib.itb.ac.id/gdl/view/23734 |
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| Institution: | Institut Teknologi Bandung |
| Language: | Indonesia |
| Summary: | Reactor Generation IV is development from previous generation. Reactor FUJI U3 have high safety design and melting fuel will not happen because the fuel is already in liquid. In this research will be done neutronic analysis by program SRAC 2006. Graphite moderator is different from moderator on PWR (Pressurized Water Reactor) because on PWR the moderator is water (liquid) but in Molten Salt Reactor the moderator is solid. In this research will be analysis by SRAC program version 2002 and 2006. And the library is JENDL-3.2, JENDL-3.3, JENDL-4.0. The composition from the molten salt are 7LiF – BeF2 – 232ThF4 – 233UF4 ( 71.76 %mol – 16 % mol – 12 % mol – 0.24 % mol ). And from the composistion we will get the nuclide density for input parameter, which is one of the required parameter for the output such as multiplication factor, conversion ratio, neutron spectrum, and nuclide density from fision product. After that, we will see the influence of the temperature used in the fuel to analyse Doppler coefficient and the temperature we used are 838 K, 900 K, and 1000 K. |
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