TY - JOUR
T1 - Comparative Studies on Plutonium and Minor Actinides Utilization in Small Molten Salt Reactors with Various Powers and Core Sizes
AU - Waris, Abdul
AU - Aji, Indarta Kuncoro
AU - Pramuditya, Syeilendra
AU - Novitrian,
AU - Permana, Sidik
AU - Su'Ud, Zaki
N1 - Funding Information:
This study is supported by Institut Teknologi Bandung (ITB) research grant 2013 and Indonesian Ministry of Education and Culture, Directorate General of Higher Education (DGHE) Competitive Research Grant 2013.
Publisher Copyright:
© 2014 The Authors.
PY - 2015/5/1
Y1 - 2015/5/1
N2 - Molten salt reactor (MSR) has many advantages such as safety improvement and ability for waste burning. In the present study, the use of plutonium and minor actinides (MA) in small MSRs with various powers and core sizes has been investigated. For the small MSRs with 50 MWth, 100 MWth, 150 MWth, 200 MWth, and 250 MWth of power output, the criticality condition can be achieved if the reactor grade plutonium and MA content in loaded fuel are 7.56%, 6.76%, 6.56%, 6.56%, and 6.56%, respectively. The plutonium and MA utilization in small MSR results in the hardening of neutron spectrum compared to that of the standard 25 MWth miniFUJI MSR with Th-233U fuel. Furthermore, the neutron spectra become harder with the augmenting of Pu and MA contents in loaded fuel as well as the increasing of the output power.
AB - Molten salt reactor (MSR) has many advantages such as safety improvement and ability for waste burning. In the present study, the use of plutonium and minor actinides (MA) in small MSRs with various powers and core sizes has been investigated. For the small MSRs with 50 MWth, 100 MWth, 150 MWth, 200 MWth, and 250 MWth of power output, the criticality condition can be achieved if the reactor grade plutonium and MA content in loaded fuel are 7.56%, 6.76%, 6.56%, 6.56%, and 6.56%, respectively. The plutonium and MA utilization in small MSR results in the hardening of neutron spectrum compared to that of the standard 25 MWth miniFUJI MSR with Th-233U fuel. Furthermore, the neutron spectra become harder with the augmenting of Pu and MA contents in loaded fuel as well as the increasing of the output power.
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U2 - 10.1016/j.egypro.2014.11.855
DO - 10.1016/j.egypro.2014.11.855
M3 - Conference article
AN - SCOPUS:84970965549
SN - 1876-6102
VL - 71
SP - 62
EP - 68
JO - Energy Procedia
JF - Energy Procedia
T2 - 4th International Symposium on Innovative Nuclear Energy Systems, INES 2013
Y2 - 6 November 2013 through 8 November 2013
ER -