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

6th Asian Physics Symposium

Waris, Abdul^1 ; Aji, Indarta K.^2 ; Pramuditya, Syeilendra^1 ; Widayani^1 ; Irwanto, Dwi^1

Nuclear Physics and Biophysics Research Division, Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, Jl. Ganesa 10, Bandung

40132, Indonesia^1

Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, Jl. Ganesa 10, Bandung

40132, Indonesia^2

关键词: Collision probability method;    Conversion ratio;    Criticality condition;    Generation IV nuclear energy systems;    miniFUJI;    Neutron spectra;    Nuclear data library;    Reactor designs;   

Others  :  https://iopscience.iop.org/article/10.1088/1742-6596/739/1/012004/pdf
DOI  :  10.1088/1742-6596/739/1/012004

来源: IOP

【 摘 要 】

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-ThF4-233UF4as a fuel salt. In the present study, the use of LiF4-ThF4-PuF4as fuel salt instead of LiF-BeF2-ThF4-UF4will 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 the233U fuel.