Delayed Neutrons Effect on Power Reactor with Variation of Fluid Fuel Velocity at MSR Fuji-12

International Conference on Advances in Nuclear Science and Engineering 2015

Aji, Indarta Kuncoro^1 ; Pramuditya, Syeilendra^2 ; Novitrian^2 ; Irwanto, Dwi^2 ; Waris, Abdul^2

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

40132, Indonesia^1

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

40132, Indonesia^2

关键词: Calculation process;    Delayed neutrons;    Fission cross section;    Fuel compositions;    Neutron kinetics;    Neutronic calculations;    Successive over relaxation;    Vertical direction;   

Others  :  https://iopscience.iop.org/article/10.1088/1742-6596/799/1/012004/pdf
DOI  :  10.1088/1742-6596/799/1/012004

来源: IOP

【 摘 要 】

As the nuclear reactor operate with liquid fuel, controlling velocity of the fuel flow on the Molten salt reactor very influence on the neutron kinetics in that reactor system. The effect of the pace fuel changes to the populations number of neutrons and power density on vertical direction (1 dimension) from the first until fifth year reactor operating had been analyzed on this research. This research had been conducted on MSR Fuji-12 with a two meters core high, and LiF-BeF2-ThF4-233UF4as fuel composition respectively 71.78%-16%-11.86%-0.36%. Data of reactivity, neutron flux, and the macroscopic fission cross section obtained from ouput of SRAC (neutronic calculation code has been developed by JAEA, with JENDL-4.0 as data library on the SRAC calculation) was being used for the calculation process of this research. The calculation process of this research had been performed numerically by SOR (successive over relaxation) and finite difference methode, as well as using C programing language. From the calculation, regarding to the value of power density resulting from delayed neutrons, concluded that 20 m/s is the optimum fuel flow velocity in all the years reactor had operated. Where the increases number of power are inversely proportional with the fuel flow speed.