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Effect of void-fraction on characteristics of several thorium fuel cycles in BWR
Waris A.a, Shafii M.A.a, Pramuditya S.a, Kurniadi R.a, Novitriana, Su’Ud Z.a
a Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, 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]Study on effect of void-fraction on characteristics of several thorium fuel cycles in boiling water reactor (BWR) has been carried out. Four fuel cycle scenarios are evaluated and the comparison with once-through-cycle BWR was also conducted. The 1367 nuclides have been employed in the time independent burnup calculation scheme where 129 of them are heavy metals (HMs). The burnup code was facilitated with the calculation method for determining the required 233U concentration for criticality of the system inherently. The code was coupled with SRAC 2002 cell calculation code to compose a time independent-cell burnup code. In the cell calculation, 26 HMs, 66 fission products (FPs) and one pseudo FP have been utilized. The JENDL 3.2 library has been employed in this study. The results show that the profile of the required 233U concentration for criticality depends on the neutron spectra and the microscopic cross-section. However, the profile of the conversion ratio likely depends on the number density of heavy nuclides. © 2012 Elsevier Ltd. All rights reserved.[/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,Burnup calculation,BWR,Calculation code,Conversion ratio,Fuel cycle,Heavy nuclides,JENDL3.2,Neutron spectra,Number density,SRAC 2002,Thorium fuel cycles,Thorium fuels[/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]BWR,SRAC 2002,Thorium fuel,Time-independent burnup,Void fraction[/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]This study is fully funded by Institut Teknologi Bandung’s Research Grant No. 174/K01.07/PL/2007 and Institut Teknologi Bandung’s IMHERE Program 2011.[/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/10.1016/j.enconman.2012.01.026[/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]