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Homogenous (Th,Pu)O2 Fuel Utilization on High Temperature Test Reactor 30MWt
Hidayati A.N.a, Waris A.a, Irwanto D.a, Pramutadi A.a
a Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, 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]© 2019 Published under licence by IOP Publishing Ltd.HTTR (High Temperature Test Reactor) is one of the Generation IV nuclear reactor that has been built in Japan. This study will discuss about several neutronic aspect on HTTR 30 MWt such as effective multiplication factor (k-eff) whole of active core, conversion ratio, spectrum of neutrons and the power distribution of the reactor core at the beginning and at the end of the period by using homogenous (Th,Pu)O2 fuel assembly. 3D triangular geometrical type of active core has been selected for neutronic calculation by using SRAC2006 code with nuclear data bases JENDL4.0 which is developed by JAERI. The results shows that core optimum when (Th,Pu)O2 with PuO2 fraction is 6,7% and will give the optimum k-eff during the operation time. The spectrum neutron result shows that (Th,Pu)O2 is dominant at fast energy. The power distribution results show that it can be stable for long operation period, both at beginning of life (BOL) and end of life (EOL).[/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](Th,Pu)O2,Effective multiplication factor,Generation iv nuclear,High temperature test reactors,HTTR,JENDL 4.0,Neutronic calculations,SRAC 2006[/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](Th,Pu)O2,HTTR,JENDL 4.0,SRAC 2006[/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/10.1088/1742-6596/1204/1/012133[/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]