UTILIZATION OF ENRICHED URANIUM ON MOLTEN SALT REACTOR TYPE FUJI-U1 DAN FUJI-U3

• Main Author: ASEP SOFYAN (NIM : 10212074)
• Format: Final Project
• Language: Indonesia
• Online Access: https://digilib.itb.ac.id/gdl/view/25844
• Institution: Institut Teknologi Bandung

Molten Salt Reactor is one of the fourth generation design concept. One type of MSR reactor developed is MSR type Fuji-U3 in Japan. Fuel used in the form of a molten salt with a composition of 71.76% LiF, 16% BeF2, 12% ThF4, and 0.24% UF4 where the fissile material used is 233U. In this research, neutronics analysis is performed on MSR Fuji-U1 and Fuji-U3 reactors using Thorium and Enriched Uranium as fuel. The research was conducted by using PIJ and CITATION module in SRAC 2006 program and using JENDL 4.0 nuclide data. The research was conducted by changing the composition of the fuel to obtain the composition that qualifies the criticality of the reactor with some variation of reactor operating time. Based on the results of calculations on the Fuji-U1 reactor type by varying the fuel volume fraction 39%, 27% and 45%, the UF4 concentration required for critical reactors for 20 years is 8.6%, 4.3% and 9.7% respectively of the total fuel composition. In the Fuji-U3 type reactor which has 3 variations of fuel zone with the volume fraction of fuel, the UF4 concentration required for critical reactors during 2000 EFPD and 30 years is 3.57% and 7.68% respectively. The resulting power distribution tends to flatten in the radial and axial direction of the reactor core as in the reference which using 233U as fuel. In addition, the analysis based on conversion ratio, neutron spectrum of energy, power distribution and flux distribution. <br /> <br /> Keywords: fissile, neutronics