Delayed neutrons effect on power reactor with variation of fluid fuel velocity at MSR Fuji-12

Indarta Kuncoro Aji, Syeilendra Pramuditya, Novitrian, Dwi Irwanto, Abdul Waris

研究成果: Contribution to journalConference article査読

2 被引用数 (Scopus)


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-ThF4-233UF4 as 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.

ジャーナルJournal of Physics: Conference Series
出版ステータス出版済み - 2 28 2017
イベント5th International Conference on Advances in Nuclear Science and Engineering, ICANSE 2015 - Bandung, インドネシア
継続期間: 11 18 201511 20 2015

All Science Journal Classification (ASJC) codes

  • 物理学および天文学(全般)


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