Comparative studies of nuclear fuel cell (U-Pu)N and (U-Pu)Zr using OpenMC software

Monado, Fiber and Ariani, Menik (2023) Comparative studies of nuclear fuel cell (U-Pu)N and (U-Pu)Zr using OpenMC software. AIP Conference Proceedings, 2619 (1). pp. 1-8. ISSN 0094243X, 15517616

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Abstract

This study analyzes pin-shaped fuel cells in two types of fuel mixtures, namely Uranium-Plutonium-Nitride and Uranium-Plutonium-Zirconium. Each fuel is varied by changing the percentage of Uranium-235 content as much as 1% to 10%. Using the Monte Carlo method in the OpenMC program code, calculations were performed to obtain the effective multiplication factor, rate of fission reaction, and distribution of neutron flux for two years of burn-up. The calculation results for the effective multiplication factor and the rate of fission reaction show that the greater the enrichment of uranium, the greater the value of these parameters. In the neutron flux distribution calculation fuel cells have the highest value in the middle area of the fuel, and its value gets smaller toward the edge of the cell. By doing this, fuel cell analysis so that later it can be used as a reference in the preparation of fuel cells in the reactor core that is safe and efficient.

Item Type:	Article
Subjects:	Q Science > QC Physics > QC1-999 Physics
Divisions:	08-Faculty of Mathematics and Natural Science > 45102-Physics (S2)
Depositing User:	Dr Fiber Monado
Date Deposited:	20 Jun 2023 02:05
Last Modified:	20 Jun 2023 02:05
URI:	http://repository.unsri.ac.id/id/eprint/111758

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