Preliminary Study on LiF4-ThF4-PuF4 Utilization as Fuel Salt of miniFUJI Molten Salt Reactor

Abdul Waris, Indarta K. Aji, Syeilendra Pramuditya, Widayani, Dwi Irwanto

研究成果: Contribution to journalConference article査読

抄録

miniFUJI reactor is molten salt reactor (MSR) which is one type of the Generation IV nuclear energy systems. The original miniFUJI reactor design uses LiF-BeF2-ThF4-233UF4 as a fuel salt. In the present study, the use of LiF4-ThF4-PuF4 as fuel salt instead of LiF-BeF2-ThF4-UF4 will be discussed. The neutronics cell calculation has been performed by using PIJ (collision probability method code) routine of SRAC 2006 code, with the nuclear data library is JENDL-4.0. The results reveal that the reactor can attain the criticality condition with the plutonium concentration in the fuel salt is equal to 9.16% or more. The conversion ratio diminishes with the enlarging of plutonium concentration in the fuel. The neutron spectrum of miniFUJI MSR with plutonium fuel becomes harder compared to that of the 233U fuel.

本文言語英語
論文番号012004
ジャーナルJournal of Physics: Conference Series
739
1
DOI
出版ステータス出版済み - 9 23 2016
外部発表はい
イベント6th Asian Physics Symposium 2015, APS 2015 - Bandung, インドネシア
継続期間: 8 19 20158 20 2015

All Science Journal Classification (ASJC) codes

  • 物理学および天文学(全般)

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