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A Comparative Study of Th-U233 and Th-Pu Molten-Salt Reactor (MSR) with 2-region core
Ifthacharo M.a, Permana S.a, Saputra G.a
a Master Program of Physics Department, Faculty of Mathematics and Natural Science, Bandung Institute of Technology, Bandung, 40132, Indonesia
[vc_row][vc_column][vc_row_inner][vc_column_inner][vc_separator css=”.vc_custom_1624529070653{padding-top: 30px !important;padding-bottom: 30px !important;}”][/vc_column_inner][/vc_row_inner][vc_row_inner layout=”boxed”][vc_column_inner width=”3/4″ css=”.vc_custom_1624695412187{border-right-width: 1px !important;border-right-color: #dddddd !important;border-right-style: solid !important;border-radius: 1px !important;}”][vc_empty_space][megatron_heading title=”Abstract” size=”size-sm” text_align=”text-left”][vc_column_text]© 2020 Published under licence by IOP Publishing Ltd.Sustainable closed fuel cycle and inherent safety are one of the key aspects of Generation IV reactor design. Hence Molten salt reactor (MSR) is chosen as one of the candidates of Generation IV reactor concepts. FUJI-U2 or MSR-2R is a 2-region core MSR design that was proposed as a possible simplification of FUJI-U3 (3-region core). Taking into consideration that uranium-233 doesn’t exist naturally, FUJI-U2 utilize both plutonium and uranium-233 as a fissile material. To understand the characteristics further, a comparative study of 2-region core MSR with Th-U233 and Th-Pu as fuel has been carried out. Nuclear analysis code SRAC2006 with the nuclear data library of JENDL4.0 was used, and CITATION was employed to validate the core. The design parameters set for each region are fuel composition, core radius, and fuel fraction. The simulation burn up calculation is set to 2000 days in total, with 21 step each for 100 days cycle. Neutron multiplication factor, fuel elemental, burn up calculation, conversion ratio, and neutron flux in each core will be discussed.[/vc_column_text][vc_empty_space][vc_separator css=”.vc_custom_1624528584150{padding-top: 25px !important;padding-bottom: 25px !important;}”][vc_empty_space][megatron_heading title=”Author keywords” size=”size-sm” text_align=”text-left”][vc_column_text]Burn up calculations,Closed fuel cycles,Comparative studies,Design parameters,Fuel compositions,Generation IV reactors,Neutron multiplication,Nuclear data library[/vc_column_text][vc_empty_space][vc_separator css=”.vc_custom_1624528584150{padding-top: 25px !important;padding-bottom: 25px !important;}”][vc_empty_space][megatron_heading title=”Indexed keywords” size=”size-sm” text_align=”text-left”][vc_column_text][/vc_column_text][vc_empty_space][vc_separator css=”.vc_custom_1624528584150{padding-top: 25px !important;padding-bottom: 25px !important;}”][vc_empty_space][megatron_heading title=”Funding details” size=”size-sm” text_align=”text-left”][vc_column_text][/vc_column_text][vc_empty_space][vc_separator css=”.vc_custom_1624528584150{padding-top: 25px !important;padding-bottom: 25px !important;}”][vc_empty_space][megatron_heading title=”DOI” size=”size-sm” text_align=”text-left”][vc_column_text]https://doi.org/10.1088/1742-6596/1493/1/012015[/vc_column_text][/vc_column_inner][vc_column_inner width=”1/4″][vc_column_text]Widget Plumx[/vc_column_text][/vc_column_inner][/vc_row_inner][/vc_column][/vc_row][vc_row][vc_column][vc_separator css=”.vc_custom_1624528584150{padding-top: 25px !important;padding-bottom: 25px !important;}”][/vc_column][/vc_row]