TY - GEN
T1 - Analysis of fluid fuel flow to the neutron kinetics on molten salt reactor FUJI-12
AU - Aji, Indarta Kuncoro
AU - Waris, Abdul
AU - Permana, Sidik
N1 - Publisher Copyright:
© 2015 AIP Publishing LLC.
PY - 2015/9/30
Y1 - 2015/9/30
N2 - Molten Salt Reactor is a reactor are operating with molten salt fuel flowing. This condition interpret that the neutron kinetics of this reactor is affected by the flow rate of the fuel. This research analyze effect by the alteration velocity of the fuel by MSR type Fuji-12, with fuel composition LiF-BeF2-ThF4-233UF4 respectively 71.78%-16%-11.86%-0.36%. Calculation process in this study is performed numerically by SOR and finite difference method use C programming language. Data of reactivity, neutron flux, and the macroscopic fission cross section for calculation process obtain from SRAC-CITATION (Standard thermal Reactor Analysis Code) and JENDL-4.0 data library. SRAC system designed and developed by JAEA (Japan Atomic Energy Agency). This study aims to observe the effect of the velocity of fuel salt to the power generated from neutron precursors at fourth year of reactor operate (last critical condition) with number of multiplication effective; 1.0155.
AB - Molten Salt Reactor is a reactor are operating with molten salt fuel flowing. This condition interpret that the neutron kinetics of this reactor is affected by the flow rate of the fuel. This research analyze effect by the alteration velocity of the fuel by MSR type Fuji-12, with fuel composition LiF-BeF2-ThF4-233UF4 respectively 71.78%-16%-11.86%-0.36%. Calculation process in this study is performed numerically by SOR and finite difference method use C programming language. Data of reactivity, neutron flux, and the macroscopic fission cross section for calculation process obtain from SRAC-CITATION (Standard thermal Reactor Analysis Code) and JENDL-4.0 data library. SRAC system designed and developed by JAEA (Japan Atomic Energy Agency). This study aims to observe the effect of the velocity of fuel salt to the power generated from neutron precursors at fourth year of reactor operate (last critical condition) with number of multiplication effective; 1.0155.
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U2 - 10.1063/1.4930795
DO - 10.1063/1.4930795
M3 - Conference contribution
AN - SCOPUS:85006219542
T3 - AIP Conference Proceedings
BT - 5th International Conference on Mathematics and Natural Sciences, ICMNS 2014
A2 - Purqon, Acep
A2 - Hwu, Reuben Jih-Ru
A2 - Hidayat, Taufiq
A2 - Arimura, Hidetaka
PB - American Institute of Physics Inc.
T2 - 5th International Conference on Mathematics and Natural Sciences, ICMNS 2014
Y2 - 2 November 2014 through 3 November 2014
ER -