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

Research output: Contribution to journalConference articlepeer-review

Abstract

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.

Original languageEnglish
Article number012004
JournalJournal of Physics: Conference Series
Volume739
Issue number1
DOIs
Publication statusPublished - Sep 23 2016
Externally publishedYes
Event6th Asian Physics Symposium 2015, APS 2015 - Bandung, Indonesia
Duration: Aug 19 2015Aug 20 2015

All Science Journal Classification (ASJC) codes

  • Physics and Astronomy(all)

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